ML112650284

Initial Exam 2011-301 Final Administrative Documents

ML112650284
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/21/2011
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
Download: ML112650284 (51)

Text

ES-20I - Examination Preparation Checklist - Form- ES-201 -1 Facility: McGuire Date of Examination: June 27 30, 2011 Examinations Developed by: Facility Target Chief Date* Task Description (Reference) Examiners Initials

-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-ls, ES-401-112, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d)

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

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

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

-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)

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-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 reviewed with facility licensee (C.3.k)

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

Target dates are keyed to the examination date identified in the corporate notification letter.

They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[ ] Applies only to examinations prepared by the NRC.

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

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

. Initials 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. t

c. 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 are T appropriate. if

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

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 and rotation schedule without compromising exam integrity; and ensure that each applicant U can be tested using at least one new or significantly modified scenario, that no L scenarios are duplicated from the applicants audit test(s), and scenarios will not be A repeated on subsequent days. DL T c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and 0 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 (3)* no tasks are duplicated from the applicants audit test(s) -t.

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

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.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in 0

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the appropriate exam section.

b. Assess whether the 10CFR 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.

4

e. 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 . 4

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

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

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ES-201, Page 27 of 28

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

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 administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC

• (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knodge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered n4 Z.D!I From the date that I entered into this security agreement until the completion of examination administration, I did not during the week(s) ofli 4

instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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/tfr W ES-201, Page 27 of 28

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

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

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) 1 ofJm4 Z Oi if. From the date that I entered into this security agreement until the completion instruct, evaluate, or provide performance feedback to those applicants who were administered these of examination administration, I did not licensing examinations, except as specifically noted below and authorized by the NRC.

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

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

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

PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNAT RE (1) DATE SlGNATUR7) DATE NOTE

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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 date of my signature I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner I understand that I am not to instruct evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration except as specifically noted below and 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 indirect feedback) Furthermore, I am aware of the physical security measures anct requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations anWor an enforcement action against me or the facility licensee I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised

2. Post-ExamInation To the best of my knowJdge I did not drvulge to any unauthorized persons any information concerning the NRC llcensing examinations administered dunng the week(s) ofZJaa,tqzO(( From the date that I entered into this secunty agreement until the completion of examination administration I did not Instruct evaluate or provide performance feedback to those applicants who were administered these licensing examinations except as specifically noted below and authonzed by the NRC PRINTED NAME JOB TITLE! RESPONSIBILITY TU (1) DATE SIGNATURE ATE NOTE II3t sficY 8.

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

1. Pre-Examination

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

2. Post-Examination To the best of my knowledge I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 4Zo(f From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201, Page 27 of 28

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (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* Safety System / JPM Title Function A. 010 Pressurizer Pressure Control System S,D,P,L 3 Place LTOP in Service B. 028 Hydrogen Recombiner and Purge Control System S,D,P,EN,A 5 Manually Align Phase B HVAC Equipment C. 004 Chemical and Volume Control System S,N,A I Emergency Borate the RCS D. EPE 074 Inadequate Core Cooling S,M,EN,A 4P Establish NC System Feed and Bleed E. 045 Main Turbine Generator System S,D,A 4S Perform the Main Turbine Overspeed Trip Test F. APE 067 Plant Fire On Site S,N,A 8 Restore from a Fire in the Unit 1 Cable Spreading Room G. 006 Emergency Core Cooling System S,D,EN 2 Increase Pressure in Cold Leg Accumulator 1A H. 062 AC Electrical Distribution S,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 NUREG-1 021, Revision 9

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 overlap those 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 a cooldown and depressurization in accordance with OP/11A16100/SD-4, (Cooldown to 240 Degrees F). The operator will be told that the 1A and lB NCPs are operating, that NC System pressure is 347 psig and NC System temperature is 310-320°F. The operator will be asked to place the LTOP System in operation in accordance with Enclosure 4.1 of OP/1/A/6100/SO-10, (Controlling Procedure for LTOP Operation), and monitor for proper operation.

JPM B This is a bank JPM. The operator will be told that they are the Unit 2 BOP, and that Unit 1 has experienced a Large Break LOCA. The operator will be directed to check Phase B HVAC equipment in accordance with Enclosure 2, (Phase B HVAC Equipment), of EP/1/A15000/E-0, (Reactor Trip or Safety Injection). During the performance of Enclosure 2, the operator will recognize that neither train of the VE and VX Systems automatically started (Alternate Path). The operator will be expected to manually start the 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 Reactor Makeup System failure has resulted automatic Control Rod insertion, that MCB Annunciator 1AD-2, A9, CONTROL ROD BANK LO LIMIT, has alarmed, that AP/1/A15500/38 (Emergency Boration) has been entered, and that the lB BA Transfer Pump is OOS. The operator will be directed to initiate Emergency Boration by performing Step 12 of AP/1/A15500/38 (Emergency Boration). When the operator attempts 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 from the FWST.

JPM D This is a modified JPM that uses Bank JPM PS-NC-46 as its basis. The operator will be told that a Reactor Trip on Lo-Lo S/G Level has occurred due to the loss of both Main Feedwater Pumps, that the CA System will not start, that EP/1/A15000/FR-H.1 (Loss of Secondary Heat Sink) has been implemented, and that Feed and Bleed initiation criteria has been met. The operator will be directed to initiate an NC System Feed and Bleed by performing 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-301-2 DRAFT (RLF!NALJ the operator attempts to verify that a high pressure injection flowpath exists, it will be observed that INI-9A and lOB (Cold Leg Injection Isolation Valves) have failed to open automatically (Alternate Path). The operator will be expected to establish an RCS feed and bleed flowpath such that all NCPs off, flow is High Pressure Injection flow is established 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 is starting up after a refueling outage, that the Turbine/Generator is off line and rolling at 1800 RPM in preparation for performing PT111A14250/004C (Turbine OPC and Mechanical Overspeed Trip Test), that all prerequisite conditions have been met, that two operators have been stationed at the Turbine as required, and that communications have been established with all involved. The operator will be directed to complete the Turbine OPC and Mechanical Overspeed Trip Test per PT/i /A/4250/004C (Turbine OPC and Mechanical Overspeed Trip Test), starting with Step 12.7. The operator will raise Turbine speed to OPC setpoint, and then raise speed until the Turbine Overspeed trip should be actuated (Alternate Path). The operator is expected to recognize the turbine has 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 fire has been reported in the Unit I Cable Spreading Room. The operator will be told that the 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 will also be told that several control room switch manipulations have been made, that the Fire Brigade has reported that the fire is no longer active, and that Station Management has indicated that the crew may return Control Room controls to normal as identified within Enclosure 17. The operator will be directed to restore the Control Room controls to normal by performing Step 2i.a through e of Enclosure 17 (AB 750 Unit I Cable Spreading Room Fire Unit 1 and Unit 2 Actions) of AP/i/A15500/45 (Plant Fire). The operator 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 by directing that its motor breaker be opened (Alternate Path). The operator will then open the remaining Pzr PORV isolation valves, direct that the motor breaker for 1CA-7AB be closed, and open the manual loaders for the main Steam Line PORVs while the valves remain 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 IA Cold Leg Accumulator pressure is approximately 590 psig and holding. The operator will be directed to increase the IA Cold Leg Accumulator pressure to 625+/-5 psig per OP/i /A16200/009 (Accumulator Operation) Enclosure 4.3 (Adjusting Accumulators Pressure). The operator will be expected to align N 2 to CLA 1A and raise pressure to greater 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 has occurred 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 been implemented 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 Steps 43.n-q of AP/1/A/5500/07 (Loss of Electrical Power), Case I (Loss of Normal Power to I ETA and I ETB). The operator will be expected to re-energizes all four 6900V Buses per AP/I/A15500/07.

NUREG-I 021, Revision 9

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

JPM I This is a modified JPM that uses Bank JPM CF-CA-256. The Operator will be told that Unit I is at 100% power when the OAC alarm M1AI 276 (Ui CA Temp at Chk Vlv ICA

37) is received, that the temperature in the TD CA Pump discharge to the 1D SIG is 223°F, and that the CRS has determined the #1 Turbine Driven CA Pump should be started to cool the piping to the 1 D SIG. The operator will be directed to locally start the Unit 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 to locally start the #1 TD CA Pump and align the CA System valves to provide the required cooling.

JPM J This is Bank JPM SS-RFY-019. The operator will be told that the control power for the IA 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 have been 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 Halon Fire Suppression System to the IA DIG Room, per OP/0/A16400/002B (Halon Fire Protection System) Enclosure 4.3 (Local Manual Actuation of DIG Halon). The operator will 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 a Loss 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 been dispatched to 1 ETA to swap 1 EMXA4. The operator will be asked to obtain the Brown Folder at SSF and complete Enclosure I, (Unit 1 SSF-ECA-0.0 Actions), which will require the re-establishment of NCP Seal Water flow. The re-establishment of NCP Seal Water flow is a Time Critical Task (8 minutes) as identified in PT/0/A146001113, (Operator Time Critical Task Verification), Enclosure 13.11, (Initiate SSF NCP Seal Injection and Swap to the SSF).

NUREG-l 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (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 procedure Conduct of Operations steps M,R JPM: Perform a Manual Shutdown Margin Calculation 2.1.25 (3.9) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

M,R JPM: Calculate Dilution Needed for a Specified Rod Change 2.2.3 (3.8) Knowledge of the design, procedural, and Equipment Control operational differences between units.

D R JPM: Use Main Generator Capability Curve 2.4.34 (4.2) Knowledge of RO responsibilities Emergency performed outside the main control room Procedures/Plan during an emergency and the resultant N, R operational effects.

JPM: Independently Verify Spent Fuel Pool Level Adjustment NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (4)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1)

(N)ew or (M)odified from bank (> 1) (3)

(P)revious 2 exams ( 1; randomly selected) (0)

NUREG-l 021, Revision 9

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

RO Admin JPM Summary Ala This is a modified version bank JPM ADM-NRC-AI-011. The operator will be told that Unit 1 was shutdown to Mode 3, 15 minutes ago, that they are the OATC, that the reactivity computer (REACT) is out of service, and that preparations are being made to commence a plant cooldown. The operator will be directed to perform a Shutdown Margin Calculation per 0P101A161001006 Enclosure 4.5 (Shutdown Margin Unit Shutdown, Modes 5, 4, or 3 Without Xenon Credit), and identify whether or not the cooldown can be initiated under the present conditions. The operator by completing Enclosure 4.5 of 0P111A161001006 (Reactivity Balance Calculation) will determine the Effective Boron Concentration to assure SDM to be 1382 ppm, and identify that the NC System 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. The operator will be given a set of initial conditions and told that it is desired to insert the Bank D Control Rods about 35 steps. The Operator will be given the Core Data Book and asked to manually determine the amount of Reactor Makeup Water 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 power increase to 100% is imminent. The operator will be directed to determine the maximum permissible generator load, the maximum reactive load the desired voltage per the Generator Voltage Operating Schedule assuming a power factor of 0.85 is maintained constant during the power increase. The operator will select the correct Generator Capability Curve and use it to determine the maximum permissible generator load and reactive load; and then determine the desired voltage per the Generator Voltage Operating Schedule.

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

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (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 and Conduct 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, such Conduct of Operations as graphs, curves, tables, etc.

M,R JPM: Calculate Reactor Vessel Head Venting Time 2.2.18 (3.9) Knowledge of the process for managing Equipment Control maintenance activities during shutdown operations, such as risk assessments, work M, R prioritization, etc.

JPM: Perform a Thermal Margin Determination 2.3.4 (3.7) Knowledge of radiation exposure under Radiation Control normal or emergency conditions.

D, R JPM: Take On-Site Protective Actions During a General Emergency 2.4.41 (4.6) Knowledge of emergency action level Emergency 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 retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1)

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

(P)revious 2 exams ( 1; randomly selected) (0)

NUREG-l 021, Revision 9

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

SRO Admin JPM Summary Ala This is a modified JPM using bank JPM ADM-NRC-Al-004 as its basis. With the plant at 99% power, the operator will be told that the Unit I QAC failed and is not operating, and that the crew has implemented PT/I/A14600/021A (Loss of Operator Aid Computer while in Mode I). The operator will be directed to calculate QPTR in accordance with Enclosure 13.5, Part A of PT/i/A14600/21A. The operator will be expected to calculate QPTR, and determine that Technical Specification 3.2.4 (Quadrant Power Tilt Ratio) has been exceeded, and identify any required Technical Specification ACTION.

Aib This is a modified JPM using Bank JPM-ADM-NRC-Al-018 as its basis. The operator will be told that McGuire Unit I is in a Post-Accident situation, that they are available for assignment within the Operational Support Center (OSC), and given a set of NC System and Containment conditions, along with a copy of EP/1/A15000/FR-l.I (Response to Voids in Reactor Vessel). The operator will be directed to calculate maximum head venting time in accordance with Enclosure I of FR-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. The operator will be told that Unit 1 was shutdown 24 days ago for a mid-cycle outage after 200 days of operation, that Unit I is currently in Mode 5 with the NC system is 145 F and A Train ND in service; and that preparations are being made to lower NC system level to 9 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/i 1A161 O0/SD-20 (Draining the NC System). The operator will be 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 Hot Leg Centerline and make the appropriate notifications. The operator will be expected to complete Attachment 12.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers) with a new thermal margin calculated and documented on Attachment 12.7 (Shutdown Assessment Status) and on MC-6, as well as make the required notifications to the CCC and STA.

A3 This is a Bank JPM. The operator will be told that a General Emergency has been declared and that, as the OSM, they have initiated and completed the immediate actions of Enclosure 4.1 of RP/0/A15700/004 (General Emergency). Additionally, the operator will be told that On-Site Protective Actions are being considered in accordance 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 by completing 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 of events that span a few hours, and asked to classify the event. The operator will be expected to recognize that a Site Area Emergency exists upon entry into the EOP network.

NUREG-1 021, Revision 9

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

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

Initials

1. GENERAL CRITERIA a b*

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

b. There is no day-to-day repetition between this and other operating tests to be administered 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 is within 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 system response and other examiner cues p_ 4

- 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 I the 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.

a. Author David Lazarony, Western Technical Services, Inc.

,4 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.

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

NUREG-1 021, Revision 9

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

Facility: McGuire Date of Exam: 6/27/11 Scenario Numbers: 1 23 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 of service, but it does not cue the operators into expected events. U!

2. The scenarios consist mostly of related events. CL. j V 1 :i 4

3. Each event description consists of

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

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

. the symptoms/cues that will be visible to the crew ,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 without a credible preceding incident such as a seismic event. Jj.L t;;

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

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete P 21 evaluation results commensurate with the scenario objectives. f

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

have sufficient time to carry out expected activities without undue time 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 fr deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity 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 other scenarios 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 the form along with the simulator scenarios). Pt..

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

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 j

2. 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 NUREG-1 021, Revision 9

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 Scenarios P V NO1i-i-i NOli-l-2 Nil-i -3 T M P E (Spare) 0 I L N T N CREW CREW CREW I T POSITION POSITION POSITION A C L M A T U N 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 0 0 C P 0 C P 0 C P 0 C P RX 0 1 1 0 NOR 1 1,2 3 1 1 1 8 4 4 2 SROU-1 I/C 2,3, 3,4, 4,5, 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 2,3, 35 7 4 4 2 I/C 4,5 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 2,5 3,4, 2 SROI-1 I/C 5 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 2,5 34 5 4 4 2 SROI-2 I/C 5

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 RO applicants. 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 the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

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

NUREG 1021 Revision 9

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

Facility: McGuire Date of Exam: 6/27/11 Operating Test No.: Ni i-i A E Scenarios P V NO11-i-i NOii-i-2 Nii-i-3 T M P E (Spare) 0 L N T N CREW CREW CREW CREW I T POSITION POSITION POSITION POSITION A I C L M A T U N Y j)

T P S A B S A B S A B S A B R I U E R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P 2 1 1 1 0 NOR 1 1 1 1 1 45 35 5 4 4 2 RO-1 I/C MAJ 6 6 2 2 2 1 TS 0 0 2 2 RX 1 1 1 0 NOR 1 1 1 1 1 2,5 34 2 RO-2 I/C 4 MAJ 6 6 2 2 2 1 TS 0 0 2 2 RX 2 1 1 1 0 NOR 1 1 1 1 1 45 35 5 4 4 2 RO-3 I/C 8

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

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

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

NUREG 1021 Revision 9

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

Facility: McGuire Date of Exam: 6/27/li Operating Test No.: Nil-i A E Scenarios P V NOii-l-l NOii-i-2 Nll-i-3 T M P E (Spare) 0 L N T N CREW CREW CREW I T POSITION POSITION POSITION A C L M A T u N Y T P 5 A B S A B S A B S A B R I U E R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P R)( 0 1 1 0 NOR 1 2 1 1 1 SROU-1 9 4 4 2 I/C 2,3, 12, 4,5, 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 2,3, 7 4 4 2 SROU-2 I/C 1,5 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 2,5 1,2, 4 2 SROI-1 I/C 6 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 2,5 6 4 4 2 SROI-2 I/C 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 RO applicants. 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 the ATC positions, including at least two instrument or component (lIC) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

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

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

NUREG 1021 Revision 9

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

Facility: McGuire Date of Exam: 6/27/il Operating Test No.: Nil-i A E Scenarios P V NOii-i-i NOii-i-2 Nii-l-3 T M P £ (Spare) 0 I L N T N CREW CREW CREW CREW I T POSITION A I POSITION POSITION POSITION C L M A T u N 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 0 0 C P 0 C P 0 C P 0 C P RX 4 1 1 1 0 NOR 1 1 1 1 RO-1 I/c 4,5, 1,5 5 4 4 2 8

MAJ 6 6 2 2 2 TS 0 0 2 2 RX 1 1 1 1 1 0 NOR 4 1 1 1 1 RO-2 I/c 2,5 2,3 4 4 4 2 MAJ 6 6 2 2 2 1 TS 0 0 2 2 RX 4 1 1 1 0 NOR 1 1 1 1 RO-3 IC 4,5, 1,5 5 4 4 2 8

MAJ 6 6 2 2 2 1 TS 0 0 2 2 Instructions:

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

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

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

NUREG 1021 Revision 9

ES-301 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, 2,3,4 2,3,5 Events and 1-8 1-8 1-7 5,6, .5,6, 4,5,6 6,7, 1-7 7,8 8 8 Conditions Comply With and Use 1,2,3 1,2,4 1, 24 235 1-8 1-8 1-7 5,6, 56 4,5,6 6,7, 1-7 Procedures (1) 7 7:8 6,7 8 8 Operate Control 1,2,4 1, 2,3,4 1,2,5 2,3,5 NA NA NA .5,6, 4,5,6 .6,7, 1-7 Boards (2) 6, 7,8

.6,7 8 8 Communicate and 18 18 17 1-8 1-8 1-7 1-8 1-8 1-7 Interact Demonstrate Supervisory Ability 1-8 1-8 1-7 NA NA NA NA NA NA (3)

Comply With and Use 3,4 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 the examiners to evaluate every applicable competency for every applicant.

NUREG-l 021, Revision 9

2011 MNS SR IRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/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)

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

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

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

Ability to (a) predict the impacts of the following Depressurizing of RCS while it is hot malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5/43/5/45/3/45/5) 2.4.31 Residual Heat Removal System (RHRS) TIG 2/1 RO 4.2 SRO 4.1 4 SYSOO5 SYSOO5 GENERIC Knowledge of annunciator alarms, indications, or response procedures. (CFR:

41.10/45.3)

Residual Heat Removal System (RHRS) T/G 2/1 RO 2.5 SRO 2.6 5 SYSOO5 K6.03 Knowledge of the effect of a loss or malfunction on the RHR heat exchanger following will have on the RHRS: (CFR: 41.7 / 457) - --

Emergency Core Cooling System (ECCS) T/G 2/1 RO 4.1 SRO 4.1 6 SYSOO6 A3.03 6 ESFAS-operated valves Ability to monitor automatic operation of the ECCS, including: (CFR: 41.7 / 45.5)

Emergency Core Cooling System (ECCS) T/G 2/1 RO 2.8 SRO 2.9 7 SYSOO6 K5.02 Knowledge of the operational implications of the following Relationship between accumulator volume and pressure concepts 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/SRO K/A Description SYSOO7 2.4.31 Pressurizer Relief TanklQuench Tank System (PRTS) T/G 2/1 RO 4.2 SRO 4.1 8

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

41.10 /45.3)

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

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

SYSOI2 A2.02 Reactor Protection System (RPS) T/G 2/1 RO 3.6 SRO 3.9 10 10 Ability to (a) predict the impacts of the following Loss of instrument power malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 / 45.3 / 45.5)

SYSOI2 K2.O1 Reactor Protection System (RPS) T/G 2/1 RO 3.3 SRO 3.7 11 11 Knowledge of bus power supplies to the following: (CFR: RPS channels, components, and interconnections 41.7)

SYSOI3 K2.O1 Engineered Safety Features Actuation System (ESFAS) T/G 2/1 RO 3.6* SRO 3.8 12 12 ESFAS/safeguards equipment control Knowledge of bus power supplies to the following: (CFR:

41.7)

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

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

SYSO22 K4.03 Containment Cooling System (CCS) T/G 2/1 RO 3.6* SRO 4.0 14 14 Automatic containment isolation Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)

Page2of 15

2011 MNS SR. RC Examination ES 401, Rev9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description SYSO26 Al .02 Containment Spray System (CSS) T/G 2/1 RO 3.6* SRO 3.9 15 15 Ability to predict and/or monitor changes in parameters Containment temperature (to prevent exceeding design limits) associated with operating the CSS controls including: (CFR: 41.5 / 45.5)

SYSO39 A2.05 Main and Reheat Steam System (MRSS) T/G 2/1 RO 3.3 SRO 3.6 16 16 Ability to (a) predict the impacts of the following Increasing steam demand, its relationship to increases in reactor power malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:_(CFR: 41.5 / 43.5 / 45.3 / 45.13)

SYSO39 K4.05 Main and Reheat Steam System (MRSS) TIG 2/1 RO 3.7 SRO 3.7 17 17 Knowledge of MRSS design feature(s) and/or interlock(s) Automatic isolation of steam line which provide for the following: (CFR: 41.7)

SYSO59 A3.06 Main Feedwater (MFW) System T/G 2/1 RO 3.2* SRO 3.3 18 18 Feedwater isolation Ability to monitor automatic operation of the MEW, including: (CFR: 41.7 / 45.5)

SYSO6I K2.02 Auxiliary I Emergency Feedwater (AFW) System TIG 2/1 RO 37* SRO 3.7 19 19 Knowledge of bus power supplies to the following: (CFR: AFW electric drive pumps 41.7)

A4.04 AC Electrical Distribution System T/G 2/1 RO 2.6 SRO 2.7 20 SYSO62 20 Local operation of breakers Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 / to 45.8)

SYSO62 K3.03 AC Electrical Distribution System T/G 2 / 1 RO 3.7 SRO 3.9 21 21 DC system Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following: (CFR:

41.7 / 45.6)

Page3of 15

2011 MNSSR RC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-213 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description SYSO63 K3.0l DC Electrical Distribution System TIG 2/1 RO 3*7* SRO 4.1 22 22 Knowledge of the effect that a loss or malfunction of the ED/G DC electrical system will have on the following: (CFR:

41.7 / 45.6)

SYSO64 Al .04 Emergency Diesel Generator (ED!G) System T/G 2/1 RO 2.8 SRO 2.9 23 23 Ability to predict and/or monitor changes in parameters Crankcase temperature and pressure (to prevent exceeding design limits) associated with operating the ED/G system controls including: (CFR:

41.5 / 45.5)

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

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

SYSO73 KI .01 Process Radiation Monitoring (PRM) System TIG 2/1 RO 3.6 SRO 3.9 25 25 Knowledge of the physical connections and/or cause- Those systems served by PRMs effect relationships between the PRM system and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

SYSO76 A4.04 Service Water System (SWS) T/G 2/1 RO 35* SRO 3.5 26 26 Ability to manually operate and/or monitor in the control Emergency heat loads room: (CFR: 41.7 / 45.5 to 45.8)

SYSIO3 A3.01 Containment System T/G 2/1 RO 3.9 SRO 4.2 27 27 Ability to monitor automatic operation of the containment Containment isolation system, including: (CFR: 41.7/45.5)

SYSIO3 2.4.6 Containment System TIG 2/1 RO 3.7 SRO 4.7 28 28 SYS1O3 GENERIC Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13)

Page4of 15

2011 MNS SR RC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-213 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description SYSOO2 KI .17 Reactor Coolant System (RCS) T/G 2/2 RO 3.5 SRO 38 29 29 Knowledge of the physical connections and/or cause- MT/G effect relationships between the RCS and the following systems: (CFR: 41.2 to 41.9 I 45.7 to 45.8)

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

30 30 Knowledge of bus power supplies to the following: (CFR: PZR heaters 41.7)

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

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

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

32 32 Detector failure Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 / 43.5 /

45.3 I 45.5)

SYSO29 A3.01 Containment Purge System (CPS) T/G 2/2 RO 3.8 SRO 4.0 33 Ability to monitor automatic operation of the Containment CPS isolation Purge System including: (CFR: 41.7 I 45.5)

Al .02 Spent Fuel Pool Cooling System (SFPCS) TIG 2/2 RO 2.8 SRO 3.3 34 5YS033 Ability to predict and/or monitor changes in parameters Radiation monitoring systems (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including: (CFR: 41.5 / 45.5)

Page5of 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 Importance RO/SRO K/A Description SYSO34 2.2.39 Fuel Handling Equipment System (FHES) TIG 2/2 RO 39 SRO 4.5 35 SYSO34 GENERIC Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7 /41.10/43.2 /45.13)

SYSO35 K6.O1 Steam Generator System (SIGS) T/G2/2 RO 3.2 SRO 3.6 36 36 Knowledge of the effect of a loss or malfunction on the MSIVs following will have on the S/GS: (CFR: 41.7 /45.7)

SYSO7I K5.04 Waste Gas Disposal System (WGDS) T/G 2/2 RO 2.5 SRO 3.11 37 Knowledge of the operational implication of the following Relationship of hydrogen/oxygen concentrations to flammability concepts as they apply to the Waste Gas Disposal System:_(CFR: 41.5/45.7)

SYSO79 A4.01 Station Air System (SAS) T/G 2/2 RO 2.7 SRO 2.7 38 38 Ability to manually operate and/or monitor in the control Cross-tie valves with lAS room: (CFR: 41.7/45.5to45.8)

T/G 1/1 SRO 3.4 39 EPEOO7 EAI .01 Reactor Trip RO 3.7 Ability to operate and monitor the following as they apply T/G controls to a reactor trip: (CFR 41.7 / 45.5 / 45.6)

APEOO8 AK2.01 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck 0 T/G 1/1 RO 2.7* SRO 2.7 40 40 Knowledge of the interrelations between the Pressurizer Valves Vapor Space Accident and the following: (CFR 41.7 /

45.7)

Small Break LOCA T/G 1/1 RO 3.0 SRO 33*

41 EPEOO9 EK2.03 41 Knowledge of the interrelations between the small break S/Gs LOCA and the following: (CFR 41.7 / 45.7)

Page6of 15

2011 MNS SR RC Examination ES 401, Rev9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description EPEOII EKIOl Large Break LOCA TIG ill RO 4.1 SRO 4.4 42 42 Knowledge of the operational implications of the following Natural circulation and cooling, including reflux boiling.

concepts as they apply to the Large Break LOCA: (CFR 41.8/41.10/45.3)

APEOI 51017 AK2.10 Reactor Coolant Pump (RCP) Malfunctions TIG 1/1 RO 18* SRO 2.8 43 Knowledge of the interrelations between the Reactor RCP indicators and controls Coolant Pump Malfunctions (Loss of RC Flow) and the following: (CFR 41.7 /45.7)

APEO22 AAI .07 Loss of Reactor Coolant Makeup T/G 1/1 RO 2.8* SRO 2.7 44 Ability to operate and / or monitor the following as they Excess letdown containment isolation valve switches and indicators apply to the Loss of Reactor Coolant Makeup: (CFR 41.7

/ 45.5 / 45.6)

APEO25 AA2.01 Loss of Residual Heat Removal System (RHRS) TIG 1 /1 RO 2.7 SRO 2.9 45 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)

APEO27 2.1.31 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1/1 RO 4.6 SRO 4.3 46 46 Ability to locate control room switches, controls, and indications, and to APEO27 GENERIC determine that they correctly reflect the desired plant lineup. (CFR: 41.10 /

45.12)

EPEO29 2.2.25 Anticipated Transient Without Scram (ATWS) T/G 1/1 RO 3.2 SRO 4.2 47 EPEO29 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)

EPEO38 EAI .11 Steam Generator Tube Rupture (SGTR) T/G 1/1 RO 3.8 SRO 3.9 48 48 Ability to operate and monitor the following as they apply S/G level indicators toa SGTR: (CFR41.7/45.5/45.6)

Page7of 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 Importance RO/SRO K/A Description APEO4O AK3.O1 Steam Line Rupture TIC 1/1 RO 4.2 SRO 4.5 49 Knowledge of the reasons for the following responses as Operation of steam line isolation valves they apply to the Steam Line Rupture: (CFR 41 .5,41.10 /

45.6 145.13)

APEO54 AA2.03 Loss of Main Feedwater (MFW) TIC 1/1 RO 4.1 SRO 4.2 50 50 Ability to determine and interpret the following as they Conditions and reasons for AFW pump startup apply to the Loss of Main Feedwater (MFW): (CFR: 43.5 /

45.13)

EPEO55 EK1.02 Loss of Offsite and Onsite Power (Station Blackout) TIC 1/1 RO 4.1 SRO 4.4 51 51 Knowledge of the operational implications of the following Natural circulation cooling concepts as they apply to the Station Blackout: (CFR 41.8/41.10/45.3)

APEO56 2.2.40 Loss of Offsite Power TIC ill RO 3.4 SRO 4.7 52 52 Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 / 43.5 APEO56 GENERIC

/45.3)

APEO57 AK3.01 Loss of Vital AC Electrical Instrument Bus TIC 1/1 RO 4.1 SRO 53 4.1 Knowledge of the reasons for the following responses as Actions contained in EOP for loss of vital ac electrical instrument bus they apply to the Loss of Vital AC Instrument Bus: (CFR 41.5,41.10 / 45.6 / 45.13)

APEO62 AA2.01 Loss of Nuclear Service Water TIC 1/1 RO 2.9 SRO 3.5 54 Ability to determine and interpret the following as they Location of a leak in the SWS apply to the Loss of Nuclear Service Water: (CFR: 43.5 /

45.13)

Page8of 15

2011 MNS SR IRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description APEO65 AK3.08 Loss of Instrument Air T/G 1/1 RO 3.7 SRO 3.9 55 Knowledge of the reasons for the following responses as Actions contained in EOP for loss of instrument air they apply to the Loss of Instrument Air: (CFR 41.5,41.10

/45.6 /45.13)

WEO5 EKl.3 Loss of Secondary Heat Sink TIG 1/1 RO 3.9 SRO 4.1 56 56 Knowledge of the operational implications of the following Annunciators and conditions indicating signals, and remedial actions concepts 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)

APEOO3 AA2.03 Dropped Control Rod T/G 1/2 RO 3.6 SRO 3 57 Ability to determine and interpret the following as they Dropped rod, using in-core/ex-core instrumentation, in-core or loop apply to the Dropped Control Rod: (CFR: 43.5/45.13) temperature measurements APEO24 AK2.O1 Emergency Boration T/G 1/2 RO 2.7 SRO 2.7 58 58 Knowledge of the interrelations between Emergency Valves Boration and the following: (CFR 41.7 / 45.7)

APEO59 AA2.05 Accidental Liquid Radioactive-Waste Release T/G 1 I 2 RO 3.6 SRO 3.9 59 Ability to determine and interpret the following as they The occurrence of automatic safety actions as a result of a high PRM system apply to the Accidental Liquid Radwaste Release: (CFR: signal 43.5 / 45.13)

APEO6I AK3.02 Area Radiation Monitoring (ARM) System Alarms T/G 1/2 RO 3.4 SRO 3.6; 60 60 Guidance contained in alarm response for ARM system Knowledge of the reasons for the following responses as they apply to the Area Radiation Monitoring (ARM)

System Alarms: (CFR 41.5,41.10 / 45.6 / 45.13) -

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

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

Page9of 15

2011 MNS SR ARC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-213 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description WEO8 EKl.2 Pressurized Thermal Shock T/G 1/2 RO 3.4 SRO 4.0 62 62 Knowledge of the operational implications of the following Normal, abnormal and emergency operating procedures associated with concepts as they apply to the (Pressurized Thermal (Pressurized Thermal Shock).

Shock)

(CFR:41.8/41.10,45.3) V WEI 3 EKI .3 Steam Generator Overpressure T/G 1/2 RO 3.0 SRO 3.2 63 63 Knowledge of the operational implications of the following Annunciators and conditions indicating signals, and remedial actions V

concepts as they apply to the (Steam Generator associated with the (Steam Generator Overpressure).

Overpressure)

(CFR: 41.8 /41.10, 45.3)

WEI4 EAI.1 High Containment Pressure T/G 1/2 RO 3.7 SRO 3.7 64 64 Ability to operate and / or monitor the following as they Components, and functions of control and safety systems, including apply to the (High Containment Pressure) instrumentation, signals, interlocks, failure modes, and automatic and manual (CFR: 41.7 / 45.5 / 45.6) features.

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

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

GEN2.1 2.1.17 GENERIC Conduct of Operations T/G 3/0 RO 3.9 SRO 4.0 66 -

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

45.12/45.13)

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

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

/45.12)

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

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

Page 10 of 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 Importance RO/SRO K/A Description GEN2.2 2.2.14 GENERIC - Equipment Control T/G 3/0 RO 3.9 SRO 4.3; 69 69 Equipment Control Knowledge of the process for controlling equipment configuration or status.

(CFR:41.10/43.3/45.13)

GEN2.2 2.2.3 GENERIC - Equipment Control T/G /0 RO 3.8 SRO 3.9 70 70 Equipment Control (multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5 / 41.6 / 41.7 / 41.10 / 45.12)

GEN2.3 2.3.5 GENERIC - Radiation Control TIG 3/0 RO 2.9 SRO 2.9 71 71 Radiation Control Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.11 /41.12/43.4/45.9)

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

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

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

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

43.5/45.13)

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

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

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

Emergency Procedures / Plan Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.10/43.2 / 45.6)

Pagellof 15

2011 MNS SR JRC Examination ES 401, Rev 9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description SYSOO6 2.4.20 Emergency Core Cooling System (ECCS) TIG 2/1 RO 3.8 SRO 4.

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

SYSIO3 2.4.41 Containment System TIG 2/1 RO 2.9 SRO 4.6 77 SYSIO3 GENERIC Knowledge of the emergency action level thresholds and classifications. (CFR:

41.10/43.5/45.11)

SYSO59 A2.12 Main Feedwater (MFW) System TIG 2/1 RO 3.1* SRO 32 78 78 Ability to (a) predict the impacts of the following Failure of feedwater regulating valves malfunctions or operations on the MEW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 /43.5 / 45.3 / 45.13)

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

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

45.13)

SYSO73 A2.02 Process Radiation Monitoring (PRM) System T/G 2/1 RO 2.7 SRO 3.2 80 80 Detector failure Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to cor- rect, control, or mitigate the consequences of those malfunctions 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 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description SYSO34 A1.02 Fuel Handling Equipment System (FHES) T/G 2/2 RO 2.9 SRO 3.7 81 81 Ability to predict and/or monitor changes in parameters Water level in the refueling canal (to prevent exceeding design limits) associated with operating the Fuel Handling System controls including:

(CFR: 41.5/45.5)

SYSO72 2.4.31 Area Radiation Monitoring (ARM) System TIG 2/2 RO 4.2 SRO 4.1 82 82 SYSO72 GENERIC Knowledge of annunciator alarms, indications, or response procedures. (CFIR:

41.10/45.3) 5YS086 A2.O1 Fire Protection System (FPS) TIG 2/2 RO 2.9 SRO 3.1 83 83 Ability to (a) predict the impacts of the following Manual shutdown of the FPS malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 I 43.5 / 45.3 /

45.13)

EPEOO7 EA2.04 Reactor Trip T/G 1/1 RO 4.4 SRO 4.6 84 84 If reactor should have tripped but has not done so, manually trip the reactor Ability to determine or interpret the following as they apply to a reactor trip: (CFR 41.7 / 45.5 / 45.6) and carry out actions in ATWS EOP EPEOO9 EA2.11 Small Break LOCA TIG 1/1 RO 3.8 SRO 4.1 85 85 Ability to determine or interpret the following as they apply Containment temperature, pressure, and humidity to a small break LOCA: (CFR 43.5 /45.13)

EPEOI 1 2.4.31 Large Break LOCA T/G 1/1 RO 4.2 SRO 4.1 86 86 Knowledge of annunciator alarms, indications, or response procedures. (CFR:

EPEOI 1 GENERIC 41.10 /45.3)

Page 13 of 15

2011 MNS SR JRC Examination ES 401, Rev9 Combined PWR Written Examination Outline Form ES-401-2/3 Question K/A Number K/A System Tier/Group Importance RO/SRO K/A Description APEO56 AA2.72 Loss of Offsite Power T/G 1/1 RO 4.1 SRO 4.3 87 87 Ability to determine and interpret the following as they Auxiliary feed flow apply to the Loss of Offsite Power: (CFR: 43.5 / 45.13)

APEO57 2.1.23 Loss of Vital AC Electrical Instrument Bus T/G 1/1 RO 4.3 SRO 4.4 88 88 APEO57 GENERIC Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)

SYSO62 2.1.20 AC Electrical Distribution System TIG 2/1 RO 4.6 SRO 4.6 89 89 Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)

SYSO62 GENERIC APEOO3 AK3.04 Dropped Control Rod TIG 1/2 RO 3.8* SRO 4.11 90 90 Actions contained in EOP for dropped control rod Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: (CFR 41 .5,41.10 I 45.6 I 45.13) 2.2.12 Fuel Handling Incidents TIG 1/2 RO 3.7 SRO 4.11 91 APEO36 91 Knowledge of surveillance procedures. (CFR: 41.10/45.13)

APEO36 GENERIC AA2.10 Steam Generator (SIG) Tube Leak T/G 1/2 RO 3.2 SRO 4.11 92 APEO37 92 Tech-Spec limits for RCS leakage Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: (CFR: 43.5 /

45.13)

APEO67 2.2.25 Plant Fire On Site T/G 1/2 RO 3.2 SRO 4.

93 APEO67 GENERIC Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2) 2.1.20 GENERIC Conduct of Operations T/G 3/0 RO 4.6 SRO 4.6 94 GEN2.1 -

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

Page 14 of 15

2011 MNS SR ARC Examination ES 401, Rev9 Combined PWR Written Examination Outline Form ES-401-213 Question K/A Number K/A System Tier/Group Importance ROISRO K/A Description 95 GEN2.1 2.1.35 GENERIC Conduct of Operations T/G 3/0 RO 2.2 SRO 3.9 95 Conduct of Operations Knowledge of the fuel-handling responsibilities of SROs. (CFR: 41.10 I 43.7).

GEN2.2 2.2.18 GENERIC Equipment Control TIG 3/0 RO 2.6 SRO 3.9 96 -

96 Equipment Control Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc. (CFR:

41.10/43.5/45.13) 97 GEN2.2 2.2.19 GENERIC - Equipment Control T/G 3/0 RO 2.3 SRO 3.4 97 Equipment Control Knowledge of maintenance work order requirements. (CFR: 41.10/43.5/

45.13)

GEN2.3 2.3.4 GENERIC Radiation Control T/G 3/0 RO 3.2 SRO 3.7 98 -

98 Radiation Control Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR:41.12143.4145.10)

GEN2.4 2.4.11 GENERIC Emergency Procedures! Plan T/G 3/0 RO 4.0 SRO 4.2 99 -

99 Emergency Procedures / Plan Knowledge of abnormal condition procedures. (CFR: 41.10 /43.5 /45.13)

GEN2.4 2.4.23 GENERIC Emergency Procedures I Plan T/G 3/0 RO 3.4 SRO 4.4 100 -

100 Emergency Procedures / Plan Knowledge of the bases for prioritizing emergency procedure implementation during 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 Rejection Group Selected KA 2/ 1 SYSO61 K2.03 Q(19) MNS has no diesel driven AFW pumps. New K/A randomly selected by Chief Examiner 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 (SYSO34 G2.2.39) randomly selected with concurrence of Chief Examiner. HCF 3/28/11 1 I1 APEO54 AA2.08 Q(50) Rejected KA due to inability to write a discriminating question with this KA. New KA (APEO54 AA2..03) randomly selected with concurrence from Chief Examiner. HCF 3/28/11 1/2 APEOS9 AA2.02 Q(59) Rejected KA due to inability write a valid question for the KA. New KA (APEO59 AA2.05) 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 (WEO8 EK1.2) 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 selected new 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/A randomly 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. New system 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 with concurrence 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 APEO37-AA2.10 (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 were repeated from the last 2 NRC licensing exams, consult the NRR CL program office).

5. Question duplication from the license screening/audit exam was controlled as 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; or the licensee certifies that there is no duplication; or other (explain)

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

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

36 I 10 39 I 15 4f

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

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

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

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-t

b. Facility Reviewer(*)

c. NRC Chief Examiner (#) E,LL-,,1 Le. .

Z, /

d. NRC Regional Supervisor Note:

• The facility reviewers initials/signature are not applicable for NRC-developed examinations.

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

ES-401 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 Explanation Focus Dist. Link units ward K/A Only Instructions

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Q#

1.

LOK 2.

LOD 3._Psychometric_Flaws

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

(F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 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 required knowledge for the RO to understand pump startlstop operation. Accepted question.

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 H 2 N S Ken had a problem. First said the question did not match k)a. then said distractors a and b were not plausible. Ken said he looked at it this morning and came to that conclusion. (Reviewed question with S.G. Concluded that question matched the K/A and distractors 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 the rupture 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 un needed information in the stem. Based on what the question is

. asking, do you need all of the information. Could not locate information/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 is plausible. I could not locate lesson plan identified. Made changes to the stem. (OK) 9 H 2 B E Is it possible to identify the channels that failed.. Not able to locate lesson plan. Identified pressure channels as suggested. Did not really matter based on new design. (OK) 10 U Distractors A & C are not plausible. Do not know of any indications where a reactor trip would be required for the conditions given.

Added information to the stem ( instrument power or control power). Question should not have been UNSAT. Licensee provided information as to why. (E only) 11  ? 1 x N U LOD. It appears that the only information need to answer the question is to know the bases of the OT delta T. Immediately eliminates two distractors. Please explain the pressure transient and why this is considered plausible. Could there be two correct answers? What makes this a comprehension level question?

Question should have been SAT not IJNSAT. Information provided by the licensee provided support for it being a SAT question, (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 Explanation Focus 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 16 H

H 3

2 B/M

[ s [NRC Exam 2009 N S? Need be make sure that this is an RO question. Concern that applicant may say that the actions are directed by the SRO while taking actions in AP. Could not locate learning objective with direct tie. Although, I do think the question can be answered with system knowledge. Information identified in Foldout page provides instruction on what needs to be performed. The Foldout page is 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 be a 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 with licensee. 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 change LOD. 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 28 F 2

[ fNf S (OK) (6/1)

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

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

Q# LOK LOD (F/H) (1-5) Stem Cues Focus T/F f Cred.

Dist.

Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Link units ward K/A Only 29 H X N  ? Not sure distractors A and D are plausible. Need to discuss. Made change 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 of heaters?? Will look at AP-24. Will revisit on 5/20. S & I reviewed question in detail with licensee and concluded that question was 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 following identifies the Minimum # of Loops Tavg detectors failures to cause and 2. Re worded stem. Will provide control builders 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 anyone think core alteration would continue? Will bring back in the morning. Will need a new question. (5119). Reviewed proposed question still need a new question. (5120). Wrote new question. (OK). (5125) 36 H 2 B U/E Distractor C is not plausible. Distractor D needs work. Explain why/or how steam line drains would be used for cooldown and what procedure you would use. Provided information in procedure which indicated TDCA could be used. Question should have been 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. Licensee stated that they think it was an oversite on their part. After making 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)

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

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 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 considered run-out conditions. Increased flow rate to 3200. Concluded that if runout condition occurred, pump amps would indicate high and remain stable. Ok with change and question. (OK) r 47 H

F

[ 2 X

B N

S U

(OK) (6/1)

Consider using valves other that condenser steam dumps.. Steam dumps are not safety related. Revised stem to included TS Bases Credited Changed addressed concern of safety related VS non safety related. (OK).

zzzz:_

49 H X L+/-(0(611)

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 you do not ask why this occurs. You only state that it occurs in I second. K/A doesnt match. Changed stem to address concern and match KIA (OK)

I[Z[ZZZ 51 H 3 N S Review question to make sure there is no unnecessary information provided (is CA isolated to all S/Gs and VI header pressure 0 PSIG needed). Removed CA from stem. (OK) 52 H N U Why is this question considered an RO question? The question is asking an RO applicant to answer the question passed on SRO responsibilities. Did note that question is tied to learning objective for RO. A second part needs to be added to distractors A&B to make them plausible. Wrote new question. New question is ok. Decided to keep the question as is based on the fact that references are provided. May be challenging, however it is tied to 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-7 and 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 Explanation Focus Dist. Link unitsi ward K/A Only 55 H 3 N  ? Please identify where the reasons are identified in the AP. Also make sure that there is not more than one correct answer. Could C be correct if Train B is not successful? Provided information to address 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).

57 H 2 Need to discuss power decrease verses QPTR increase to X N S? ensure plausibility of distractors A and B. Addressed Concerns. (OK) 58 F 2 X N E Stem of the question appears be confusing. Are the bullets really needed or located in the correct place. Could we not make the question more challenging by not providing the valve numbers in the stem by asking the applicant to: describe the actions directed in the procedures for establishing flow in the event in cant be established via 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 doesnt appear to be correct). Need to look at the bases/reasons for the steps identified in the procedure. Made correction to stem and modified distractors. Provided documentation identifying the reasons. Question is now OK. (5123) 61 H 2 B  ? Not sure how you came up with the numbers. Need to explain in detail. Do not know where 21% came from when the value given in the table indicates 23%. Licensee provided detailed information as 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 identify in step (5) FR-P.1 where it directs placing spray in service. Provide procedural situation/guidance where heater would be placed in service to prevent exceeding a parameter/limit. information where placing heaters in service would. Prove plausibility of distractors A

& B. Not enough information provided. Changed distractors based on information provided in FR-P.1 that is to be performed after the soak is completed Step 4. Based on two implausible distractors questions should have been a U. Revised question is OK. 5124.

63 H 2 f f f B 5? Consider changing NR level from 99% to 95%. Made change as suggested. (OK) 5/24.

j j j

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 Explanation Focusj Dist. Link units ward K/A Only 64 F 2 X N E As written the question doesnt appear to match the K/A. Are the conditions given in the distractors interlocks which would prevent operating components/equipment? Will select a new K/A and question (5124) Question should have been a U. Provided a new question. (OK) (5/25).

65 F 2 1j x f] B/M E NRC 2009 Exam Q 66 Modified. Make sure grammar is correct is stem (is/are) Made correction. (OK) (5I25).

66 F 2 X N E/S Discuss the wording in bullets 2 & 3: is seen before needed and the alarm was not expected but NOT pre-identified You as specifically discussed it was or it was not .... The licensee wanted to leave as is because it added creditability to the distractors. 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 for both units. One unit increasing power following lowering of power the other unit increasing power following maintenance /special testing and JITT completed for all return to power Wrote new question. Old question should have been a U. New question is OK. (5/25) 69 F 1 N S? LOD. The procedure reads having the Verifer observe the Doers initial action is preferable to having individuals operate the component. Need to discuss. Is only needed in distractors C & D.

Revised question to address verify valve position that require supervisor 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 Explanation Focus Dist. Link units ward K/A Only 76 F Question can be answered with system knowledge only.

X N U Both caution statements which are in ES-i .3 are system knowledge based.

This Q is U because it is NOT SRO only.

Agreed with our comment. Provided a new question. Question as provided appears to be sat. Ned to look at a few more things. 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) 78 F 2 X Consider adding an indication of SG level. This should E prevent the applicant from making an assumption. In which case, based on assumptions made regarding SG level, a different answer may be correct. Changed the stem to read.... Based on the above conditions, NCsystem Feed and bleed must be initiated within . Changed distractors. Question is OK.

79 E Distractor C is not plausible. Changed distractor C. Question is OK.

80 H X Given the circumstance, it is obvious that the release must U be stopped/suspended. Therefore A and B are not plausible.

Please identify alarms that will be received as a result of the count rate failing to read less than background.

Consider rewriting the stem to state in addition to stopping the release, which one of the following must the SRO do?

May be able to add something about EMF-44 tripping and causing WL-320, WP-35, and WM-46 to isolate.

The question is UNSAT due to two implausible distractors Based on information provided the VQ system release was in progress and certain equipment was operable it would allow for a continuous release. Question should not have been UNSAT. Question OK as provided.

81 H 3 N S (OK) (5/26)

(OK)(5126) 82 F 3 B S 83 H 2 ( 2009 NRC exam Q 92.lt is not reasonable to believe that a B U manual abort of the Halon system cant be manually undone.

Distractors B and D indicate this would occur. These distractors are not plausible. The question is UNSAT due to two implausible distractors. Is there a reset switch associated with this? Agreed with comment and there was overlay with JPM. Will provide new question (5118).

New question is ok. Need to provide definition of different 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 Explanation Focus Dist. Link units ward K/A Only 84 H X B2 is a true statement therefore it could be argued as correct 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 information need 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 that that procedure would provide directions to resolve the issue. Once power is restored, the control room operator can look at control board 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 a change in peacking factors and what affects AFD? Made changes.

Provided information on why part A.l was SRO. Question is OK.

91 H N S? I do not have a problem with the question, however, need to make sure it is not a direct lookup. Replaced .99 with .98. Nothing major. Question is Ok.

92 H N 5? Need additional information on how you arrived at 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated with T.S. based on conditions given. Provided TS information indicating plausibility of using 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Question is OK.

93 H X X N U 30 minutes is not a plausible distractor. Not able to locate a 30 minute requirement any place in the procedure as indicated, Is it not common knowledge that closing the PORV block affects the operability of PORV? Need to explain in more details why this question is SRO only. Could not locate background docunment.

Provided information requested which proved question was SAT. 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 Explanation Focus Dist. Link units ward K/A Only 96 F 2 N S Changed to a 2 based on discussion. This is the responsibility of the SRO in the WCC.

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

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

99 H B U Question can be answered with RO only knowledge. TS states that four loops (iNCP per loop) shall be operable in Modes I & 2. RO knowledge. RO would also know that once high temperatures are reached, action must be taken to trip the pump Will provide a new question (5118). Reviewed new question. Determined it was acceptable. (5/19) 100 F B U NRC 2009 exam, Q 93. Do not see where bases are being addressed. Wrote new question. Will look at question next week. Reviewed new question. (OK). (5126).

ES-403 Written Examination Grading Form ES-403-1 Quality 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 fl4 /A

2. Answer key changes and question deletions justified 2 and documented 3 fT4 VA 4j

3. Applicants scores checked for addition errors (reviewers_spot_check>_25%_of examinations) 1q, , ,

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as_applicable,_+/-4%_on_the_SRO-only)_reviewed_in_detail

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

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity 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 (*) y/ii/iíí

d. NRC Supervisor (*)

(*) The facility reviewers 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