Text

12 Draft Outlines
	ML120180158
Person / Time
Site:	Grand Gulf
Issue date:	12/02/2011
From:	; NRC Region 4
To:	; Entergy Operations
References
	50-416/11-301
	Download: ML120180158 (36)
	v • d • e

ES-401 BWR Examination Outline - RO Form ES-401-1 Facility: Grand Gulf Nuclear Station Date of Exam: December 2, 2011 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 1 5 2 4 2 6 20 7 Emergency &

Abnormal Plant 2 1 1 1 2 1 1 7 3 Evolutions Tier Totals 2 6 3 6 3 7 27 10 1 4 3 4 3 1 3 2 2 2 1 1 26 5 2.

Plant 2 1 0 2 2 1 1 1 1 1 1 1 12 3 Systems Tier Totals 5 3 6 5 2 4 3 3 3 2 2 38 8

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

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

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

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

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

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

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

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

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

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

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

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

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

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

1 2 3 1 2 295001 Partial or Complete Loss of Forced X 2.4.11 Knowledge of abnormal condition procedures. 4.0 4 Core Flow Circulation / 1 & 4 55.41(b)(10)

F Ability to operate and/or monitor the following as 295003 Partial or Complete Loss of AC / 6 X they apply to PARTIAL OR COMPLETE LOSS OF 3.6 35 A.C. POWER: AA1.04 D.C. electrical distribution H

system 55.41(b)(7) 295004 Partial or Total Loss of DC Pwr / 6 X Knowledge of the interrelations between PARTIAL 3.0 14 OR COMPLETE LOSS OF D.C. POWER and the following: AK2.02 Batteries 55.41(b)(8) F Ability to operate and/or monitor the following as 295005 Main Turbine Generator Trip / 3 X they apply to MAIN TURBINE GENERATOR TRIP: 3.6 20 AA1.05 Reactor/turbine pressure regulating system H

55.41(b)(4) & (10) 295006 SCRAM / 1 X 2.4.2 Knowledge of system set points, interlocks and 4.5 25 automatic actions associated with EOP entry conditions. 55.41(b)(7) & (10) F 295016 Control Room Abandonment / 7 X 2.1.25 Ability to interpret reference materials, such as 3.9 36 graphs, curves, tables, etc. 55.41(b)(10)

H 295018 Partial or Total Loss of CCW / 8 X 2.4.11 Knowledge of abnormal condition procedures. 4.0 50 55.41(b)(10)

F Ability to operate and/or monitor the following as 295019 Partial or Total Loss of Inst. Air / 8 X they apply to PARTIAL OR COMPLETE LOSS OF 3.5 8 INSTRUMENT AIR: AA1.01 Backup air supply H

55.41(b)(4)

Knowledge of the interrelations between LOSS OF 295021 Loss of Shutdown Cooling / 4 X SHUTDOWN COOLING and the following: AK2.01 3.6 53 Reactor water temperature 55.41(b)(10) & (14)

H Knowledge of the reasons for the following responses 295023 Refueling Acc / 8 X as they apply to REFUELING ACCIDENTS: AK3.02 3.4 59 Interlocks associated with fuel handling equipment F

55.41(b)(6)

Knowledge of the interrelations between HIGH 295024 High Drywell Pressure / 5 X DRYWELL PRESSURE and the following: EK2.02 3.7 24 HPCS 55.41(b)(7)

H Ability to determine and/or interpret the following as 295025 High Reactor Pressure / 3 X they apply to HIGH REACTOR PRESSURE: EA2.03 3.9 15 Suppression pool temperature 55.41(b)(10)

H 295026 Suppression Pool High Water X 2.2.39 Knowledge of less than or equal to one hour 3.9 60 Temp. / 5 Technical Specification action statements for systems.

55.41(b)(10) F 295027 High Containment Temperature / 5 Knowledge of the operational implications of the 295028 High Drywell Temperature / 5 X following concepts as they apply to HIGH DRYWELL 3.5 58 TEMPERATURE: EK1.01 Reactor water level H

measurement 55.41(b)(10)

Knowledge of the interrelations between LOW 295030 Low Suppression Pool Wtr Lvl / 5 X SUPPRESSION POOL WATER LEVEL and the 3.7 21 following: EK2.02 RCIC 55.41(b)(8) & (10)

F

Ability to operate and/or monitor the following as 295031 Reactor Low Water Level / 2 X they apply to REACTOR LOW WATER LEVEL: 3.6 54 EA1.10 Control rod drive 55.41(b)(7) & (10)

F Knowledge of the reasons for the following responses 295037 SCRAM Condition Present X as they apply to SCRAM CONDITION PRESENT 4.1 16 and Reactor Power Above APRM AND REACTOR POWER ABOVE APRM Downscale or Unknown / 1 H DOWNSCALE OR UNKNOWN: EK3.03 Lowering reactor water level 55.41(b)(10) 295038 High Off-site Release Rate / 9 X Knowledge of the interrelations between HIGH OFF- 3.7 55 SITE RELEASE RATE and the following: EK2.05 Site emergency plan 55.41(b)(10) F 600000 Plant Fire On Site / 8 X 2.4.49 Ability to perform without reference to 4.6 56 procedures those actions that require immediate operation of system components and controls. F 55.41(b)(10)

Ability to determine and/or interpret the following as 700000 Generator Voltage and Electric Grid X they apply to GENERATOR VOLTAGE AND 3.5 57 Disturbances / 6 ELECTRIC GRID DISTURBANCES: AA2.01 H

Operating point on the generator capability curve 55.41(b)(10)

K/A Category Totals: 1 5 2 4 2 6 Group Point Total: 20

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

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

1 2 3 1 2 Knowledge of the interrelations between LOSS OF 295002 Loss of Main Condenser Vac / 3 X MAIN CONDENSER VACUUM and the following: 3.1 9 AK2.07 Offgas system 55.41(b)(4)

H 295007 High Reactor Pressure / 3 Knowledge of the reasons for the following responses as 295008 High Reactor Water Level / 2 X they apply to HIGH REACTOR WATER LEVEL: 3.2 39 AK3.07 HPCS isolation 55.41(b)(7)

F 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 Ability to operate and/or monitor the following as they 295014 Inadvertent Reactivity Addition / 1 X apply to INADVERTENT REACTIVITY ADDITION: 3.3 52 AA1.06 Reactor/turbine pressure regulating system H

55.41(b)(7) & (10) 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 Knowledge of the operational implications of the 295020 Inadvertent Cont. Isolation / 5 & 7 X following concepts as they apply to INADVERTENT 3.5 40 CONTAINMENT ISOLATION: AK1.02 H

Power/reactivity control 55.41(b)(7) & (10)

Ability to operate and/or monitor the following as they 295022 Loss of CRD Pumps / 1 X apply to LOSS OF CRD PUMPS: AA1.01 CRD 3.1 61 hydraulic system 55.41(b)(7)

H 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 Ability to determine and/or interpret the following as 295033 High Secondary Containment X they apply to HIGH SECONDARY CONTAINMENT 3.8 10 Area Radiation Levels / 9 AREA RADIATION LEVELS: EA2.01 Area radiation H

levels 55.41(b)(10) 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High X 2.1.28 Knowledge of the purpose and function of major 4.1 37 Differential Pressure / 5 system components and controls. 55.41(b)(7)

H 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 1 1 1 2 1 1 Group Point Total: 7

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

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

1 2 3 4 5 6 1 2 3 4 Knowledge of the effect that a loss or 203000 RHR/LPCI: Injection X malfunction of the RHR/LPCI: INJECTION 4.2 17 Mode MODE (PLANT SPECIFIC) will have on H

following: K3.03 Automatic depressurization logic 55.41(b)(7)

Ability to predict and/or monitor changes in X parameters associated with operating the 3.8 38 RHR/LPCI: INJECTION MODE (PLANT F

SPECIFIC) controls including: A1.03 System flow 55.41(b)(8)

Knowledge of electrical power supplies to the 205000 Shutdown Cooling X following: K2.02 Motor operated valves 2.5 1 55.41(b)(8)

F 206000 HPCI 207000 Isolation (Emergency)

Condenser Knowledge of electrical power supplies to the 209001 LPCS X following: K2.03 Initiation logic 55.41(b)(8) 2.9 41 F

Ability to (a) predict the impacts of the 209002 HPCS 2.8 62 following on the HIGH PRESSURE X CORE SPRAY SYSTEM (HPCS) ; and H (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.05 D.C.

electrical failure: BWR-5,6 55.41(b)(7) &

(10) 211000 SLC X 2.1.31 Ability to locate control room switches, 4.6 11 controls, and indications, and to determine that they correctly reflect the desired plant lineup. H 55.41(b)(6) & (7)

Knowledge of the effect that a loss or 212000 RPS X malfunction of the following will have on the 3.6 19 REACTOR PROTECTION SYSTEM: K6.01 H

A.C. electrical distribution 55.41(b)(4) & (6) &

(7) 215003 IRM X Knowledge of INTERMEDIATE RANGE 2.9 2 MONITOR (IRM) SYSTEM design feature(s) and/or interlocks which provide for the H following: K4.04 Varying system sensitivity levels using range switches 55.41(b)(7)

Knowledge of the effect that a loss or 215004 Source Range Monitor X malfunction of the following will have on the 2.6 22 SOURCE RANGE MONITOR (SRM)

H SYSTEM: K6.05 Trip units 55.41(b)(7)

Ability to manually operate and/or monitor in 215005 APRM / LPRM X the control room: A4.06 Verification of proper 3.6 42 functioning/ operability 55.41(b)(7)

H Knowledge of the physical connections and/or X cause effect relationships between AVERAGE 3.3 63 POWER RANGE MONITOR/LOCAL H

POWER RANGE MONITOR SYSTEM and the following: K1.16 Flow converter/comparator network 55.41(b)(7) 217000 RCIC X Ability to monitor automatic operations of the 3.5 18 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: A3.01 Valve H operation 55.41(b)(7)

Ability to (a) predict the impacts of the X following on the REACTOR CORE 2.9 64 ISOLATION COOLING SYSTEM (RCIC);

H and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.09 Loss of vacuum pump 55.41(b)(7) & (10) 218000 ADS X Knowledge of AUTOMATIC 3.8 43 DEPRESSURIZATION SYSTEM design feature(s) and/or interlocks which provide for F the following: K4.02 Allows manual initiation of ADS logic 55.41(b)(7)

Knowledge of the physical connections and/or X cause-effect relationships between 3.9 65 AUTOMATIC DEPRESSURIZATION H

SYSTEM and the following: K1.05 Remote shutdown system 55.41(b)(7)

Ability to predict and/or monitor changes in 223002 PCIS/Nuclear Steam X parameters associated with operating the 3.7 66 Supply Shutoff PRIMARY CONTAINMENT ISOLATION H

SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including: A1.02 Valve closures 55.41(b)(7)

Knowledge of the effect that a loss or 239002 SRVs X malfunction of the RELIEF/SAFETY VALVES 3.9 67 will have on following: K3.01 Reactor pressure H

control 55.41(b)(7) 259002 Reactor Water Level X Ability to monitor automatic operations of the 3.0 3 Control REACTOR WATER LEVEL CONTROL SYSTEM including: A3.06 Reactor water level F setpoint setdown following a reactor scram 55.41(b)(7)

Knowledge of the effect that a loss or 261000 SGTS X malfunction of the STANDBY GAS 3.2 26 TREATMENT SYSTEM will have on the H

following: K3.05 Secondary containment radiation/ contamination levels 55.41(b)(8) 262001 AC Electrical X Knowledge of A.C. ELECTRICAL 3.0 72 Distribution DISTRIBUTION design feature(s) and/or interlocks which provide for the following: H K4.01 Bus lockouts 55.41(b)(8) 262002 UPS (AC/DC) X Knowledge of the physical connections and/or 2.8 7 cause effect relationships between UNINTERRUPTABLE POWER SUPPLY H (A.C./D.C.) and the following: K1.01 Feedwater level control 55.41(b)(4) & (7)

Knowledge of the effect that a loss or 263000 DC Electrical X malfunction of the D.C. ELECTRICAL 3.4 68 Distribution DISTRIBUTION will have on following: K3.03 H

Systems with D.C. components (i.e. valves, motors, solenoids, etc.) 55.41(b)(6) & (7)

Knowledge of the operational implications of 264000 EDGs X the following concepts as they apply to 3.4 27 EMERGENCY GENERATORS H

(DIESEL/JET): K5.05 Paralleling A.C. power sources 55.41(b)(7) & (10)

Knowledge of the connections and / or cause 300000 Instrument Air X effect relationships between INSTRUMENT 2.8 23 AIR SYSTEM and the following: K1.04 H

Cooling water to compressor 55.41(b)(4)

X Knowledge of electrical power supplies to the 2.8 69 following: K2.01 Instrument air compressor 55.41(b)(4) F Knowledge of the effect that a loss or 400000 Component Cooling X malfunction of the following will have on the 2.7 70 Water CCWS: K6.07 Breakers, relays, and H

disconnects 55.41(b)(7)

K/A Category Point Totals: 4 3 4 3 1 3 2 2 2 1 1 Group Point Total: 26

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline - RO Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

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

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS Knowledge of the operational implications 201005 RCIS X 3.5 12 of the following concepts as they apply to ROD CONTROL AND INFORMATION H SYSTEM (RCIS): K5.09 High power setpoints BWR-6 55.41(b)(5) & (7) 201006 RWM Knowledge of the effect that a loss or 202001 Recirculation X 3.5 28 malfunction of the following will have on the RECIRCULATION SYSTEM : K6.01 H Jet pumps 55.41(b)(2) & (3) 202002 Recirculation Flow Control Ability to predict and/or monitor changes 204000 RWCU X 2.9 29 in parameters associated with operating the REACTOR WATER CLEANUP H SYSTEM controls including: A1.07 RWCU drain flow 55.41(b)(3) & (10) 214000 RPIS 215001 Traversing In-core Probe 215002 RBM Knowledge of the effect that a loss or 216000 Nuclear Boiler Inst. X 3.9 30 malfunction of the NUCLEAR BOILER Instrumentation will have on following: H K3.24 Vessel level monitoring 55.41(b)(3)

& (7) 219000 RHR/LPCI: Torus/Pool Cooling X 2.4.4 Ability to recognize abnormal 4.5 5 Mode indications for system operating F parameters that are entry-level conditions for emergency and abnormal operating procedures. 55.41(b)(10) 223001 Primary CTMT and Aux.

Ability to manually operate and/or 226001 RHR/LPCI: CTMT Spray Mode X 3.8 13 monitor in the control room: A4.12 Containment/drywell pressure 55.41(b)(7) F

& (10) 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam X Knowledge of MAIN AND REHEAT 2.5 44 STEAM SYSTEM design feature(s) F and/or interlocks which provide for the following: K4.08 Removal of non condensable gases from reactor head area 55.41(b)(3) 239003 MSIV Leakage Control

Ability to monitor automatic operations of 241000 Reactor/Turbine Pressure X 3.8 71 Regulator the REACTOR/TURBINE PRESSURE REGULATING SYSTEM including: H A3.08 Steam bypass valve operation 55.41(b)(4) & (5)

Knowledge of the effect that a loss or 245000 Main Turbine Gen. / Aux. X 2.7 45 malfunction of the MAIN TURBINE GENERATOR AND AUXILIARY F SYSTEMS will have on following: K3.05 Reactor feedwater pump 55.41(b)(4) 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring X Knowledge of RADIATION 3.6 46 MONITORING System design feature(s) F and/or interlocks which provide for the following: K4.03 Fail safe tripping of process radiation monitoring logic during conditions of instrument failure 55.41(b)(7) & (11)

Ability to (a) predict the impacts of the 286000 Fire Protection 3.2 51 following on the FIRE PROTECTION X SYSTEM ; and (b) based on those F predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.08 Failure to actuate when required 55.41(b)(4) & (10) 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals X Knowledge of the physical connections 3.2 6 and/or cause effect relationships between H REACTOR VESSEL INTERNALS and the following: K1.09 LPCI 55.41(b)(3) &

(8)

K/A Category Point Totals: 1 0 2 2 1 1 1 1 1 1 1 Group Point Total: 12

ES-401 Generic Knowledge and Abilities Outline (Tier 3) - RO Form ES-401-3 Facility: Grand Gulf Nuclear Station Date of Exam: December 2, 2011 Category K/A # Topic RO SRO-Only IR # IR #

2.1.1 Knowledge of conduct of operations requirements. 3.8 31 55.41(b)(10) F 1.

Conduct 2.1.2 Knowledge of operator responsibilities during all 4.1 74 of Operations modes of plant operation. 55.41(b)(10) H 2.1.44 Knowledge of RO duties in the control room during 3.9 47 fuel handling such as responding to alarms from the fuel handling area, communication with the fuel F storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation. 55.41(b)(10)

Subtotal 3 2.2.12 Knowledge of surveillance procedures. 55.41(b)(10) 3.7 75 F

2. 2.2.35 Ability to determine Technical Specification Mode of 3.6 48 Equipment Operation. 55.41(b)(5) H Control 2.2.43 Knowledge of the process used to track inoperable 3.0 32 alarms. 55.41(b)(10) F Subtotal 3 2.3.4 Knowledge of radiation exposure limits under normal 3.2 33 or emergency conditions. 55.41(b)(10) F

3. 2.3.13 Knowledge of radiological safety procedures 3.4 49 Radiation pertaining to licensed operator duties, such as response to radiation monitor alarms, containment F Control entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. 55.41(b)(8) & (10)

Subtotal 2 2.4.6 Knowledge of EOP mitigation strategies. 55.41(b)(10) 3.7 34 F

4.

Emergency 2.4.29 Knowledge of the emergency plan. 55.41(b)(10) 3.1 73 Procedures /

F Plan Subtotal 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As - RO Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/1 263000 A4.02 Could not write a question (#68) for this KA that would not be double-jeopardy with the context of an already-written (and preferred) question (#14). Additionally, we could not write an operationally valid question for either of the two remaining A4 KAs; therefore, we randomly and systematically selected 263000 K3.03 as the replacement KA.

3 2.4.46 Could not write an operationally valid question (#73) for this KA without the question being a system specific one. Per ES-401, Section D.2.a (1st para.) this is unacceptable for Tier 3 questions.

Randomly and systematically selected 2.4.29 as the replacement KA.

SYSTEMS DELETED 201002 Reactor Manual Control System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

201004 Rod Sequence Control System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

201006 Rod Worth Minimizer System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

214000 Rod Position Information System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

215002 Rod Block Monitor System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

206000 High Pressure Coolant Injection (HPCI) - System is not part of BWR-6 design.

207000 Isolation (Emergency) Condenser - System is not part of BWR-6 design.

230000 RHR/LPCI: Torus/Pool Spray Mode - System is not part of the BWR-6 Mark III Containment design.

ES-401 BWR Examination Outline - SRO Form ES-401-1 Facility: Grand Gulf Nuclear Station Date of Exam: December 2, 2011 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 20 4 3 7 Emergency &

Abnormal Plant 2 7 0 3 3 Evolutions Tier Totals 27 4 6 10 1 26 2 3 5 2.

Plant 2 12 0 3 3 Systems Tier Totals 38 2 6 8

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