ML110970550

Initial Exam 2010-302 Draft Administrative Documents

ML110970550
Person / Time
Site:	Brunswick
Issue date:	04/06/2011
From:	NRC/RGN-II
To:	Progress Energy Carolinas
References
50-324/10-302, 50-325/10-302
Download: ML110970550 (17)

Text

ES-401, Rev. 9 BWR Examinatlon Outline Form ES4OI-1 Facility: BRUNSWICK Date of Exam: December 2010 RO K/A Category Points SRO-Oniy Points Tier Group KKKKKKAAAAG A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

= = = = = = = =

1. i 3J3 20 3 4 7 Emergency &

2 i Ii i 7 1 2 3 Abnormal Plant N/A I N/A Evolutions Tier Totals 4 5 6 4 27 6 10 i 233231 22332 26 2 3 5

2. 11211111111 2 12 0 1 2 3 Plant Systems Tier Totals 5 3 4 2 3 3 4 4 3 38 3 5 8

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

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

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

The final point total for each group and tier may deviate by ti from that specified in the table based on NRC revisions. The final RO exam must total 75 poInts and the SRO-only exam must total 25 poInts.

3. Systemslevolutlons within each group are identified on the associated outline; systems or evolutions that do notapply-at-thefacility-shouId-bedeieted-andjustitIedoperationally-irnportantsitespeciflcsystems-thatare not inciuded on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K!A statements.

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

5. Absent a plant-specific priority, only those K/As having an importance rating (iR) of 2.5 or higher shall be selected, Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

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

7. *The generic (C) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRS) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category In the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note

1. I does not apply). Use duplicate pages for RO and SRO-only exams.

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

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC Rb SRO 295001 AK3.0l Partial or Complete Loss of Forced 3.4 Core Flow Circulation / 1 & 4 3.6 [J [] } fl [] [] H H [] [] H Reactor water level response 295003AK3.06 Partial or Complete Loss of AC / 6 3.7 3.7 fl LI LI H H H H H Containment isolation 295004AA1 .03 Partial or Total Loss of DC Pwr / 6 3.4 3.6 [] H H H H ) [] [] [] [] A.C. electrical distribution 295005AA2.06 Main Turbine Generator Trip / 3 2.6 2.7 f LI H H H El H li LI LI H Feedwater temperature 295006AK1.02 SCRAM/i 3.4 Shutdown margin l] [1 H H H H Li Li H LI H 295016AK3.01 Control Room Abandonment / 7 4.1 4.2 H H l H H H H H H H H Reactor SCRAM 295018G2.1.32 Partial or Total Loss of CCW /8 3.8 4.0 H LI El H H H H LI H H Ability to explain and apply all system limits and precautions.

295019AK2.1l Partial or Total Loss of Inst. Air/8 2.5 2.6 H I El El H H H H Li H H Radwaste 295021 AK1.02 Loss of Shutdown Cooling / 4 3.3 3.4 1HH HE [ID LI EIHH Thermal stratification 295023AK2.03 Refueling Acc Coohng Mode /8 3.4 3.6 HHHHHHHHHH Radiation monitoring equipment 295024EK3.01 High Drywell Pressure /5 3.6 4.0 H1HIZEHH LI [1 [1 LI Drywall spray operation: Mark-I&ll Page 1 of 2 517/2010 10:57AM

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 295025EK1 .04 High Reactor Pressure /3 3.6 3.9 [] [] [] Li [1 Li [1 [] [] Decay heat generation 295026EK2.02 Suppression Pool High Water Temp. I 3.6 3.8 5

[] J Li Li Li [] [] [] Li Li Suppression pool spray: Plant-Specific 295028EK2.01 High Drywell Temperature / 5 3.7 4.1 Li IJ Li Li LI Li Li Li Li [] fl Drywell spray: Mark-I&ll 29603032.4.30 Low Suppression Pool Wtr Lvi /5 2.7 4.1 Li LI LI Li Li Li LI Li [] [1 Knowledge of events related to system operationslstatus that must be reported to internal orginizations or outside agencies.

295031 EA1 .01 Reactor Low Water Level/2 4.4 4.4 Li Li Li L] Li [1 Li LI Li Li Low pressure coolant injection (RHR): Plant-Specific.

295037EA2.01 SCRAM Condition Present and Power 4.2 4.3 Li Li LiLi LI Li Li Reactor power Above APRM Downscale or Unknown Li Li Li

/1 295038EA1.07 High Off-site Release Rate /9 3.6 3.8 Li Li Li Li Li Li J Li Li [] Li Control room ventilation: Plant-Specific 60000032.4.6 Plant Fire On Site / 8 3.7 4.7 Li Li LI Li Li Li Li Li Li Li Knowledge symptom based EOP mitigation strategies.

700000AA2.07 Generator Voltage and Electric Grid 3.6 4.0 Distrurbancecs Li Li Li LILILILI iLi Li Li Operational status of engineered safety features Page 2 of 517/2010 10:57AM

ES-401, REV 9 T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR 1(1 1(2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SIRO 295008G2.l.25 High Reactor Water Level / 2 3.9 4.2 El El LI LI LI LI LI LI LI LI Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

295014AA1.06 Inadvertent Reactivity Addition / 1 3.3 LI LI LI Li LI LI EI LI LI LI U Reactor/turbine pressure regulating system 295015AK1.02 Incomplete SCRAM! 1 3.9 4.1 [] I [] [E (] [ [] [] Cooldown effects on reactor power 295020AP2.03 Inadvertent Cont. Isolation /5 & 7 3.7 3.7 U] U] U] LI LI UI LI U] U] [] Reactor power 295033EK3.02 High Secondary Containment Area Radiation Levels! 9 3.5 3.6 U [Z LI LI L] LILILI[l U)) Reactor SCRAM 295034EK3.05 Secondary Containment Ventilation 3.6 3.9 High Radiation /9 LI fl j J ]j ] U] Manual SCRAM and depressurization: Plant. Specific....

295036EK2.O1 Secondary Containment High Sump/Area Water Level / 5 3.1 3.2 U)) U)) U]LI Secondary containment equipment and floor drain system Page 1 of 5/7/2010 10:57AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 203000K2.O1 RHR/LPCI: Injection Mode 3.5 3.5 Pumps fl Li Li C] C] [1 Li Li C] Li 203(X)0K2.03 RHRILPCI: Injection Mode 2.7 2.9 [] j [] [] [] Li L] [J [] [] C] Initiation logic 20500002.2.44 Shutdown Cooling 4.2 4.4 [] [] [] [] [] [] C] C] [] [] Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 206000A3.01 HPCI 3.6 3.5 C] [] [] [] [] C] [] Li] )) [] [] Turbine speed: BWR-2,3,4 206000A3.05 HPCI 4.3 4.3 Li Li C)) Li [1 [] C] C)) j [] C] Reactor water level: BWR-2,3,4 209001K3.03 LPCS 2.9 0[][] ] C] C)) [] C)) C] [] C)) C]) Emergency generators 211000K5.01 SLC 2.7 2.9 []Lij C)) Li LiLi Effects of the moderator temperature coefficient of reactivity on the boron 211000K5.06 SLC 3.0 32 Li C)) Li Li [] Li Li Li C)) Li C)) Tank level measurement 212000A4.07 RPS 4.0 3.9 C)) (C] C)) ]C] Li Li C)) Li Li )) C)) System status lights and alarms 215003A2.02 IRM 3.5 3.7 Li Li Li Li Li Li Li Li Li Li IRM mop condition 215004G2.4.2 Source Range Monitor 4.5 4.6 Li Li Li Li Li Li Li Li Li Li Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

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ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

Rb SRO 215005K4.08 APRM I LPRM 2.7 3.1 H L] LI 11 H Li [I H LI [] [] Sampling of overall core power in each APRM (accomplished through LPRM assignments and symmetrical rod patterns) 217000K6.04 RCIC 3.5 3.5 El

[] H H [] [] [ H [] Condensate storage and transfer system 2180001<4.04 ADS 3.5 3.6 [] LI H LI Li [] [] H H [J Insures adequate air supply to ADS valves: Plant-Specific 2230021<1 08 PCIS/Nuclear Steam Supply Shutoff 3.4 3.5 } H H H H H H H H H H Shutdown cooling systemlRHR 239002K3.01 SRVs 3.9 4.0 J H H H H H H H H Reactor pressure control 2390021<3.03 SRVs 4.3 44 H H H H H H Li [] LI Ability to rapidly depressurize the reactor 259002A4.01 Reactor Water Level Control 3.8 3.6 H H El H H H H H H H All individual component controllers in the manual mode 259002A4.1l Reactor Water Level Control 3.5 3.3 Kigh level lockout reset controls: Plant-Specific H H H H H H H H H H 261000A1.07 SGTS 2.8 2.9 H LI H H H H II H H LI H SBGTS train temperature 262001 1<2.01 AC Electrical Distribution 3.3 3.6 LI [i H H H H H H H LI [I Off-site sources of power 282002P3.01 UPS (As/DC) 2.8 3.1 Transfer from preferred to alternate source H H H H H H H Li Li H Page 2 of 3 5/7/2010 10:57 AM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 263000K5.O1 DC Electrical Distribution 2.6 2.9 [] [j hj [] [] [ [] [] [] Hydrogen generation during battery charging 264000A1.09 EDGs 3.0 3.1 [] [] [] [J [] Li j [] Li Maintaining minimum load on emergency generator (to

. prevent reverse power) 300000K1.02 Instrument Air 2.7 2.8 Service air Li Li Li [] Li Li Li Li Li 400000A2.O1 Component Cooling Water 3.3 ELLiL1L Loss of CCW pump Page 3 of 3 5)7/2010 10:57AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME/SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 202002A4.01 Recirculation Flow Control 33 3.1 [] Li Li Li Li LI LI MG sets 2040001<4.02 RWCU 2.7 2.9 [] [J [] Lj Li Li Li Li Li Piping over-pressurization protection: Plant-Specific 214000K3.03 RPIS 3.1 3.2 Li [] [ LI Li Li Li Li Li Li Li RMCS: Plant-Specific 215002A2.04 RBM 2.7 2.8 Li Li Li Li LI [1 Li LI Li [1 Powersupp1ylosses:BWR-3,45 223O01G22.4 Primary CTMT and Aux. 3.6 3.6 [] [J [] [] Li fl [J (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

226001A1.04 RHRLPCI: CTMT Spray Mode 33 3.6 Li Li Li Li Li [1 [i Li Li Li Li Suppression pool temperature: Mark-I-Il 230000K2.02 RHR/LPCI: Torus/Pool Spray Mode 2.8 2.9 fl ] Li Li Li Li Li LI Li Li Li Pumps 2340001<6.01 Fuel Handling Equipment 2.7 3.2 Electrical power Li Li Li Li Li Fi Li Li Li Li Li 2590011<3.04 Reactor Feedwater 2.5 2.5 Li Li l1 Li Li Li Li LI Li Li Li RWCU 271000K5.06 Offgas 2.7 2.7 Catalytic recombination Li Li Li Li E?1 Li Li LI Li Li Li 2720001<1.08 Radiation Monitoring 3.9 3.6 ] Li Li Li Li Li Li Li Li Li Li Reactor protection system Page lot 2 5/7/2010 10:57AM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR 1(1 1(2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 288000A3O1 Plant Ventilation 3.8 3.8 LI LI LI LI LI El ] Li LI Isolation/initiation signals Page 2 of 2 5/7/2010 10:57 AM

ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 02.1.43 Conduct of operations 4.1 4.3 J [] C] C] [] C] [=1 Cl Cl Ability to use procedures to determine the effects on reactivity of plant changes G2.1.7 Conduct of operations 4.4 4.7 C] C] C] C] C] [] [] [J C] [J Ability to evaluate plant performance and make operational iudgments based on operating characteristics, reactor behavior and instrument interpretation.

02.2.2 Equipment Control 4.6 4.1 C] C] Cl Cl Cl C] Cl Cl Cl C] Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

G2.2.3 Equipment Control 3.8 3.9 [1 Li LI C] Cl Li Cl Cl LI Cl (multi-unit license) Knowledge of the design, procedural and operational differences between units.

02.3.11 Radiation Control 3.8 4.3 C] C] C] C] C] [] [] C] C] [] Ability to control radiation releases.

Ga3.12 Radiation Control 32 3.7 C] [] Cl [] C] fl [] [] [] [] Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.13 Radiation Control 3.4 3.8 ri [] Cl Cl [] [] [] [] [] Knowledge of radiological safety procedures pertaining to licensed operator duties 02.4.16 Emergency Procedures/Plans 3.5 4.4 Knowledge of EOP implementation hierarchy and H C] LI Cl Cl LI Cl LI C] Cl II coordination with other support procedures or guidelines.

02.4.39 Emergency Procedures/Plans 3.9 3.8 [] [] C] [] C] [] [] C] [] C] Knowledge of the ROs responsibilities in emergency plan implementation.

G2.4.6 Emergency Procedures/Plans 3.7 4.7 j

[1 [1 C] Cl Cl Cl [] [] Cl [] Knowledge symptom based EOP mitigation strategies.

Page 1 of 1 517/2010 10:57AM

ES-401, REV 9 SHO TtG1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295004AA2.04 Partial or Total Loss of DC Pwr /6 3.2 3.3 Li El [1 El [1 El l] El LI LI System lineups 29500602.1.27 SCRAM Ii 3. 4 ] El [] [] El [] LI El El El Knowledgeof system purpose and orfunctiori.

29501 602.4.31 Control Room Abandonment 17 4.2 4.1 [1 L El C] C] [] El El El El Knowledge of annunciators alarms, indications or response procedures 29501902.4.18 Partial or Total Loss of Inst. Air! 8 3.3 4.0 El El El El El El El El El Knowledge of the specific bases for EOPs.

29502302.1.20 RefuelingAccCoolingMode/8 4.6 4.6 C] C] El El El El El El El El Abilitytoexecuteproceduresteps.

295028EA2.01 High Drywell Temperature /5 4.0 4.1 C] C] El C] El El ] El El El Drywell temperature 295037EA2.05 SCRAM Condition Present and Power 4.2 Above APRM Downscale or Unknown 4.3 LI El El El El [] El [I El El El Control rod position

/1 Page 1 of 1 517/2010 10:57AM

ES-401, REV 9 SRO T1G2 BIR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR 1(1 K2 K3 K4 K5 K6 At A2 AS A4 G TOPIC:

RO SRO 295008G22.38 High Reactor Water Level / 2 3.6 4.5 Li LI [1 LI El LI Knowledge of conditions and limitations in the facility license.

295020G2.2.40 Inadvertent Cont. Isolation /5 & 7 3.4 4.7 LI LI LI LI LI [1 Li El LI LI Ability to apply technical specifications for a system.

295034EA2.02 Secondary Containment Ventilation 3.7 4.2 High Radiation /9 Li J Li [] j] [] [] [] [] Cause of high radiation levels Page 1 of 1 517/2010 10:57AM

ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTLINE FORM ES4O1-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 20300062.4.21 Rt-IRJLPCI: Injection Mode 4.0 4.6 [] [1 [] ü LI LI LI LI [] [] Knowledge of the parameters and logic used to assess the status of safety functions 21500562.1.20 APAM / LPRM 4.6 4.6 Ability to execute procedure steps.

[] {J fl [J LI LI LI LI LI []

261000A2.05 SGTS 3.0 3.1 Fan trips

[] [] [] [] [J [] fj [] [J []

263000A2.02 DC Electrical Distribution 2.6 2.9 [J [I LI LI [I LI LI [El [] [] Loss of ventilation during charging 400000G2.1 .25 Component Cooling Water 3.9 4.2 LI LI LI LI [I [I LI LI LI L] Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

Page 1 of 1 517/2010 10:57AM

ES-401, REV 9 SRO T2G2 BWR EXAMINATiON OUTLiNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 23300002.2.37 Fuel Pool Cooling/Cleanup 3.6 4.6 [J [] LI [] U fl [] [] Ability to determine operability andlor availability of safety related equipment 23900102.2.3 Main and Reheat Steam 3.8 3.9 [] fl [] [] [] [] [j (multi-unit license) Knowledge of the design, procedural and operational differences between units.

288000A2.01 Plant Ventilation 3.3 3.4 El LI U El U [] [] ] [] [] [] High drywell pressure: Plant-Specific Page lot 1 517/2010 10:57AM

ES4O1, REV 9 SRO T3 8W 1 EXAMINATION OUTLINE FORM ES-401-1 KA NAME? SAFETY FUNCTION: IR K1 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 .23 Conduct of operations 4.3 4.4 c] El El El El El El C] [] Ability to perform specific system and integrated plant procedures during all modes of plant operation.

G2.1 .3 Conduct of operations 3.7 3.9 [J [] C] C] C] El El El El Knowledge of shift or short term relief turnover practices.

G2.2.23 Equipment Control 3.1 4.6 El C] El [] El El El C] El [] Ability to track Technical Specification limiting conditions for operations.

G22.43 Equipment Control 3.0 3.3 C] [] C] El El El El El El H Knowledge of the process used to track inoperable alarms G2.3.14 Radiation Control 3.4 3.8 El El El El El El El El El El Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.5 Radiation Control 2.9 2.9 El LI El El El El El El El El Ability to use radiation monitoring systems G2.4.28 Emergency Procedures/Plans 3.2 4.1 [} El LI El El El El El El El I] Knowledge of procedures relating to emergency response to sabotage.

Page 1 of 1 5/7/2010 10:57AM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Brunswick Date of Examination: December 2010 Examination Level: RO SRO-l 1 Operating Test Number: DRAFT Administrative Topic Type Describe activity to be performed (see Note) Code*

R, M Batten, Ground Calculation Conduct of Operations R, M Evaluate Overtime Eligibility Conduct of Operations R, M Sunieilance Acceptance Criteria Review Equipment Control R, M, P Determine Stay Times in a High Radiation Area Radiation Control R, N (SRO-! only) Protective Action Recommendations (PAR)

Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for RO5; 4 for SROs & RO retakes)

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

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

ES-301 Control RoomIln-Plant Systems Outline Form ES-301-2 Facility: Brunswick Date of Examination: Dec 2010 Exam Level: RD SRO-l Operating Test No.: DRAFT Control Room Systems© (8 for RO); (7 for SRO-l)

System / JPM Title Type Code* Safety Function

a. Vent DW w/stack Rad Mon failure 5, P, A 9

b. SULCV in service after scram 5, P,M, L, A 2

c. Resetting CO-FIC-49 5, N 8

d. SLC Initiation w/RWCU failure S, A, D, E 1

e. Crosstie 480V E-Busses S, D, E 6

f. Reopen MSIVs using hard card 5, D 3

g. RCIC start in Pressure Control with isolation failure S, N, A 4

h. (RO only) Reset Nitrogen Backup System S, P 5 In-Plant Systems@ (3 for RO/SRO-l)

i. SBGT Deluge Reset R, D 8

j. Vent the Scram Air Header R, A, E, D I

k. Heater Drain Pump Injection R, E, D 2

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

Type Codes Criteria for RD I SRO-I I SRO-U (A)Iternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irectfrombank 91814 (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature - I - I 1 (control room system)

(L)ow-Power I Shutdown I I I I I (N)ew or (M)odified from bank including 1 (A) 2I 2I 1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)

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