ML111150924
| ML111150924 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/29/2011 |
| From: | Constellation Energy Nuclear Group |
| To: | David Silk Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML103200302 | List: |
| References | |
| TAC U01838 | |
| Download: ML111150924 (19) | |
Text
ES-402 Written Examination Outline Form ES-401-2 Facility: Ginna Date of Exam:
04/2011 RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A G
Total G*
1 2
3 5
6
- 1.
Emergency 1
3 3
3 3
18 3
3 Plant 2
1 1
2 1
9 2
2 Evaluations Tier Totals 4 4
5 4
27 5
5 1
3 2
2 3
28 2
3
- 2.
Plant 2
1 1
1 10 0
1 2
Systems Tier Totals 4
3 3
4 4
3 4
38 3
5
- 3. Generic Knowledge & Abilities 3
4 10 2
3 4
3 2
2 1
2 2
Note
- 1.
Ensure that at least two topics from every applicable ~'JA 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 twof.
- 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 that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate KIA 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 KAs 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 KIA categories.
7.*
The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KIA's
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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 KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10CFR55.43 Total 6
4 10 5
3 8
7
ES-402 Form ES-401-2 Ginna Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function I K1 I K2 I K31 A1 I A2 I G KIA Topic(s)
M2.12 - Ability to determine and interpret the following as 008 I Pressurizer Vapor they apply to the Space Accident I 3 Pressurizer Vapor Space Accident: PZR level indicators M2.15 - Ability to determine and interpret the following as 027 I Pressurizer Pressure they apply to the Control System Malfunction Pressurizer Pressure Control 13 Malfunctions: Actions to be taken if PZR pressure instrument fails h
EA2.16 - Ability to determine or interpret the following as 038 I Steam Generator they apply to a SGTR:
Tube Rupture I 3 Actions to be taken if SIG goes solid and water enters steam line 2.4.47 - Emergency Procedures I Plan: Ability to 026 I Loss of Component Cooling Water 18 diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
2.2.39 - Equipment Control:
077 I Generator Voltage Knowledge of less than or and Electric Grid equal to one hour technical Disturbances specification action statements for "'TI::l"'
2.4.8 - Emergency Procedures I Plan:
015/17 I Reactor Coolant Knowledge of how abnormal Pump Malfunctions I 4 operating procedures are used in conjunction with EOP's.
EK1.05 - Knowledge of the operational implications of the following concepts as 029 I Anticipated Transient Without Scram (A TWS) 11 x
they apply to the A TWS:
definition of negative temperature coefficient as applied to large PWR coolant 3.7 76 4.0 77 4.6 78 4.2 79 4.5 80 4.5 81 2.8 39
ES-402 Form ES-401-2 Ginna Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#lName Safety Function KIA Topic(s)
AK1.02 - Knowledge of the operational implications of 027 1 Pressurizer Pressure Control System Malfunction 13 X
the following concepts as they apply to Pressurizer Pressure Control Malfunctions: Expansion of liquids as temperature increases EK1.3 - Knowledge of the operational implications of the following concepts as they apply to the (LOCA E04 I LOCA Outside Containment I 3 x
Outside Containment)
Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Outside Contain EK2.1 - Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the E11 I Loss of Emergency Coolant Recirculation 1 4 X
following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
AK2.02 - Knowledge of the 077 I Generator Voltage and Electric Grid Disturbances x
interrelations between Generator Voltage and Electric Grid Disturbances and the following: Breakers, rei 2.8 40 3.5 41 3.6 42 3.1 43
ES-402 Form ES-401-2 Ginna Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#lName Safety Function KiA Topic(s)
EK2.2 - Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:
Facility's heat removal E05/lnadequate Heat systems, including primary Transfer - Loss of x
coolant, emergency coolant, Secondary Heat Sink / 4 the decay heat removal systems, and relations between the proper operation of these systems to the operation of the faci
, AK3.03 - Knowledge of the reasons for the following responses as they apply to 065/ Loss of Instrument Air
/8 x
the Loss of Instrument Air:
Knowing effects on plant operation of isolating certain equipment from instrument air EK3.1 - Knowledge of the reasons for the following responses as they apply to the (Uncontrolled Depressurization of all Steam Generators) Facility E 12 / Steam Line Rupture Excessive Heat Transfer / 4 x
operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
AK3.01 - Knowledge of the reasons for the following 057 / Loss of Vital AC Electrical Instrument Bus /
6 x
responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus 3.9 44 2.9 45 3.5 46 4.1 47
ES-402 Form ES-401-2 Ginna Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 007 I Reactor Trip Stabilization - Recovery I 1 011 1Large Break LOCA 13 026 I Loss of Component Cooling Water I 8 0561 Loss of Off-site Power 16 058 I Loss of DC Power I 6 022 1 Loss of Reactor Coolant Makeup 12 055 1 Station Blackout 1 6 13 EA 1.04 - Ability to operate and monitor the following as they apply to a reactor trip:
3.6 48 RCP operation and flow rates EA 1.05 - Ability to operate and monitor the following as they apply to a Large Break LOCA: Manual and/or 4.3 49 automatic transfer of suction of charging pumps to borated source M 1.01 - Ability to operate and 1or monitor the following as they apply to the Loss of Component Cooling Water:
3.1 50 CCW/nuclear service water indications AA2.43 - Ability to determine and interpret the following as they apply to the Loss of 3.9 51 Offsite Power: Occurrence of a turbine tri M2.01 - Ability to determine and interpret the following as they apply to the Loss of DC Power: That a loss of dc power has occurred; 3.7 52 verification that substitute power sources have come on line M2.02 - Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup:
Cha 2.1.19 - Conduct of Operations: Ability to use plant computers to evaluate 3.9 or com status.
2.4.3 - Emergency Procedures I Plan: Ability to identify post-accident 3.7 55 instrumentation.
E8-402 Form E8-401-2 Ginna Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function I K1 I K2 I K31 A1 I A2 I G KIA Topic(s) 038 I 8team Generator Tube Rupture I 3 2.4.8 - Emergency Procedures I Plan:
Knowledge of how abnormal operating procedures are used in conjunction with EOP's.
KIA CategoryTotals 3
3 3
Group Point Total:
I Imp. I Q# I 3.8 56 18/6
ES-402 Form ES-401-2 Ginna Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#/Name Safety Function 1 K1 1 K21 K3 1 A1 1 A2 1 G KIA Topic(s)
E 13 I Steam Generator 3.4 82 Overpressure I 4 037 I Steam Generator 3.4 83 Tube Leak 13 E07 I Saturated Core 3.6 84 Cooling 14 076 I High Reactor Coolant 4.0 85 Activity 19 E09 I Natural Circulation x
3.0 57 Operations I 4 036 I Fuel Handling x
2.9 58 Incidents 18 AK3.17 - Knowledge of the reasons for the following 068 I Control Room responses as they apply to x
3.7 59 Evacuation I 8 the Control Room Evacuation: Injection of boric acid into the RCS
ES-402 Form ES-401-2 Ginna Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#lName Safety Function 003 / Dropped Control Rod
/ 1 E03 / LOCA Cooldown and Depressurization / 4 E07 / Saturated Core Cooling /4 001 / Continuous Rod Withdrawal/1 051 / Loss of Condenser Vacuum /4 067 / Plant Fire On-site / 8 KJA CategoryTotals I K1 I K2 I K3 I A1 I A2 I G x
KJA Topic(s)
AA1.01 - Ability to operate and / or monitor the following as they apply to the Dropped Control Rod:
Demand position counter and converter EA2.1 - Ability to determine and interpret the following as they apply to the (LOCA Cooldown and Depressurization) FadIity conditions and selection of appropriate procedures during abnormal and ions.
2.1.27 - Conduct of Operations: Knowledge of system purpose and / or function.
AA1.02 - Ability to operate and I or monitor the following as they apply to the Continuous Rod Withdrawal:
Rod in-out-hold switch AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum:
Conditions requiring reactor and/or turbine AK3.02 - Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site Steps called out in the site fire protection plan, FPS manual, and fire zone manual Group Point Total:
I Imp. I Q# I 2.9 60 3.4 61 3.9 62 3.6 63 3.9 64 2.5 65
ES-402 Form ES-401-2 Ginna Written Examination Outline Plant Systems - TiE~r 2 Group 1 System #IN KJA Topic(s)
G I A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on 010 Pressurizer those predictions, use Pressure Control procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Heater failures A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those 076 Service Water predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or
. Loss of SWS 2.4.46 - Emergency 061 Procedures / Plan:
Auxiliary/Emergency Ability to verify that the Feedwater alarms are consistent with the conditions.
2.4.4 - Emergency Procedures I Plan:
Ability to recognize abnormal indications for 064 Emergency system operating Diesel Generator parameters which are entry-level conditions for emergency and abnormal operating 3.6 86 3.7 87 4.1 88 4.7 89
ES-402 Form ES-401-2 System #/Name 073 Process Radiation Monitoring 062 AC Electrical Distribution 012 Reactor Protection 064 Emergency Diesel Generator 061 Auxiliary/Emergency Feedwater 073 Process Radiation Monitoring 022 Containment Cooling x
x x
x x
x Ginna Written Examination Outline Plant Systems - Tier 2 Group 1 KiA Topic(s) 2.1.7 - Conduct of Operations: Ability to evaluate plant performance and make operational judgments 4.7 90 based on operating characteristics, reactor behavior, and instrument internr'::'T.::Il*'l'In K1.03 - Knowledge of the physical connections and/or cause-effect relationships between 3.5 1
the ac distribution system and the following
- DC distribution K1.05 - Knowledge of the physical connections and/or cause effect relationships between 3.8 2 the RPS and the following systems:
ESFAS K2.01 - Knowledge of bus power supplies to 2.7 3 the following: Air 3.2 4 3.6 5 system will have on the following: Radioactive effluent releases K3.01 - Knowledge of the effect that a loss or malfunction of the CCS will have on the following: Containment 2.9 6 equipment subject to damage by high or low temperature, humidity, and
ES-402 Form ES-401-2 Ginna Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)
K4.01 - Knowledge of PRTS design feature(s) 007 Pressurizer x
and/or interlock(s) which 2.6 7 Relief/Quench Tank provide for the following:
Quench tank cooli K4.04 - Knowledge of RCPS design feature(s) 003 Reactor vOiOlalnl and/or interlock(s) which x
2.8 8 Pump provide for the following:
Adequate cooling of RCP motor and seals K5.01 - Knowledge of the operational implications of the 010 Pressurizer following concepts as x
3.5 9 Pressure Control the apply to the PZR PCS: Determination of condition of fluid in PZR, steam tables K5.05 - Knowledge of the operational implications of the 006 Emergency x
following concepts as 3.4 10 Core Cooling they apply to ECCS:
Effects of pressure on a solid ~\\I~T"'m K6.01 - Knowledge of the effect of a loss or 013 Engineered malfunction on the Safety Features x
2.7 11 following will have on the Actuation ESFAS: Sensors and detectors K6.05 - Knowledge of the effect of a loss or 004 Chemical and malfunction on the x
2.5 12 Volume Control following CVCS components: Sensors and detectors A 1.02 - Ability to predict and/or monitor changes in parameters (to 005 Residual Heat prevent exceeding x
3.3 13 Removal design limits) associated with operating the RHRS controls including: RHR
. flow rate
ES-402 Form ES-401-2 System #/Name 063 DC Electrical Distribution 026 Containment Spray 076 Service Water 008 Component Cooling Water Ginna Written Examination Outline Plant Systems - Tier 2 Group 1 KIA Topic(s)
A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the dc x
2.5 14 electrical system controls including:
Battery capacity as it is affected by discharge rate A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use 3.9 15 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use 2.7 16 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header ure A3.05 - Ability to monitor automatic operation of the CCWS, including:
Control of the electrically 3.0 17 operated, automatic isolation valves in the CCWS
ES-402 Form ES-401-2 Ginna Written Examination Outline Plant Systems - TiE~r 2 Group 1 System #lName KIA Topic(s)
A3.01 - Ability to monitor automatic operation of 078 Instrument Air 1 18 the lAS, including: Air re A4.04 - Ability to manually operate and/or 039 Main and monitor in the control 3.8 19 Reheat Steam room: Emergency feedwater um turbines A4.12 - Ability to manually operate and monitor in the control 059 Main Feedwater 3.4 20 room: Initiation of automatic feedwater isolation 2.2.42 - Equipment Control: Ability to recognize system 103 Containment 3.9 21 parameters that are entry-level conditions for Technical 2.4.6 - Emergency 063 DC Electrical Procedures / Plan:
3.7 22 Distribution Knowledge of EOP 2.2.36 - Equipment Control: Ability to analyze the effect of 012 Reactor maintenance activities, 3.1 23 Protection such as degraded power sources, on the status of limiting conditions for ns.
K5.01 - Knowledge of the operational implications of the 061 following concepts as Auxiliary/Emergency x
3.6 24 the apply to the AFW:
Feedwater Relationship between AFW flow and RCS heat transfer
ES-402 Form ES-401-2 Ginna Written Examination Outline Plant Systems - Tier 2 Group 1 System #lName KIA Topic(s)
A2.12 - Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those 006 Emergency predictions, use Core Cooling procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions requiring actuation of ECCS K4.01 Knowledge of SWS design feature(s) and/or interlock( s) which provide for the following:
076 Service Water x
Conditions initiating automatic closure of closed cooling water auxiliary building header su return valves.
A3.02 - Ability to monitor 010 Pressurizer automatic operation of Pressure Control the PZR PCS, including:
PZR K 1.04 - Knowledge of the physical connections and/or cause-effect 078 Instrument Air x
relationships between the lAS and the following systems: Cooling water to com r
KIA Category Totals Group Point Total:
4.5 25 2.5 26 3.6 27 2.6 28 28/5
ES-401 Form ES-401-2 System #lName 035 Steam Generator 034 Fuel Handling Equipment 014 Rod Position Indication 056 Condensate x
System 034 Fuel Handling Equipment 086 Fire Protection Ginna Written Examination Outline Plant Systems - Tier 2 Group 2 KIA Topic(s)
A2.02 - Ability to (a) predict the impacts of the following mal functions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Reactor tri rbine 2.4.3 - Emergency Procedures / Plan:
Ability to identify post accident instrumentation.
2.2.22 - Equipment Control: Knowledge of limiting conditions for operations and safety limits.
K 1.03 - Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following ms: MFW.
A 1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Fuel Handling System operating the controls including: Water level in the refueling canal A3.01 - Ability to monitor automatic operation of the Fire Protection System including:
Starting mechanisms of fire water urn 4.4 91 3.9 92 4.7 93 2.6 29 2.9 30 2.9 31
ES-401 Form ES-401-2 Ginna Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KIA Topic(s)
K3.02 - Knowledge of the effect that a 1055 or 029 Containment Purge x
malfunction of the Containment Purge System will have on the 2.9 32 following: Containment A4.06 - Ability to 045 Main Turbine Generator manually operate and/or monitor in the control room: Turbine stop 2.8 33 valves A2.03 - Ability to predict and/or monitor changes in parameters (to 016 Non-nuclear Instrumentation prevent exceeding design limits) associated with operating the NNIS 3
34 controls including:
I nterruption of transmitted K4.01 - Knowledge of 035 Steam Generator x
S/GS design feature(s) and/or interlock(s) which provide for the following:
3.6 35 S/G level control 027 Containment Iodine Removal x
K2.01 - Knowledge of bus power supplies to the fol Fans 3.1 36 K5.73 - Knowledge of the following operational 001 Control Rod Drive x
implications as they apply to the CRDS:
Need for maintenance of 2.7 37 stable plant conditions rod exercis 2.4.46 - Emergency 071 Waste Gas Disposal Procedures / Plan:
Ability to verify that the alarms are consistent 4.2 38 with the conditions.
KIA Category Totals
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Ginna ory KA#
2.1.3 2.1.31
- 1. Conduct of 2.1.28 Operations 2.1.42 2.1.39 Subtotal 2.2.35 2.2.43
- 2. Equipment Control 2.2.14 Subtotal Date:
04/2011 I
Topic Knowledge of shift or short-term relief turnover practices.
Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
Knowledge of the purpose and function of major system components and controls.
Knowledge of new and spent fuel movement procedures.
Knowledge of conservative decision making practices.
Ability to determine Technical Specification Mode of Operation.
Knowledge of the process used to track inoperable alarms.
Knowledge of the process for contrOlling equipment configuration or status.
RO SRO-Only IR Q#
IR Q#
3.7 66 4.6 67 4.1 75 3.4 94 4.3 98 3
2 3.6 68 3.0 69 4.3 95 2
1
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Knowledge of radiation monitoring I
systems, such as fixed radiation 2.3.15 monitors and alarms, portable survey 2.9 70 instruments, personnel monitoring equipment, etc.
I 2.3.11 Ability to control radiation releases.
3.8 71 Ability to comply with radiation work i
2.3.7 permit requirements during normal or 3.5 74 abnormal conditions.
- 3. Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.7 96 Ability to use radiation monitoring systems, such as fixed radiation 2.3.5 monitors and alarms, portable survey 2.9 99 instruments, personnel monitoring I
equipment, etc.
Subtotal 3
2 Knowledge of RO tasks performed 2.4.34 outside the main control room during an emergency and the resultant 4.2 72 operational effects.
Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, 2.4.21 core cooling and heat removal, reactor 4.0 73
- 4. Emergency coolant system integrity, containment Procedures I conditions, radioactivity release control, Plan etc.
I 2.4.29 IKnowledge of the emergency plan.
4.4 97 2.4.25 Knowledge of fire protection procedures.
3.7 100 Subtotal 2
2 Tier 3 Point Total:
10 7
ES-401 Record of Rejected KIA's Form ES-401-4 Randomly Selected I
Tier 1Group Reason for Rejection KA 0271 AA2.05 I
1 11 replaced by 027 1 Topic will result in excessive overlap with Question 86 AA2.15 0271 AK1.01 1 11 replaced by 027 1 Topic will result in excessive overlap with Question 9 AK1.02 E07 12.4.34 replaced There are no RO actions outside the control room related to this 1/2 by E07 12.4.1 061 12.4.49 replaced 2/1 by 061 12.4.46 0761 A2.01 replaced 2/1 by 0761 A2.02 103 1 2.1.25 replaced 2/1 I
by 103 12.2.42 0061 A2.05 replaced 2/1 by 006 1A2.12 071 12.4.6 replaced 2/2 I
by 071 12.4.46 071 12.4.8 replaced 2/2 by 071 12.4.46 G31 2.3.4 replaced 3/3 by G3/2.3.11 076 1 K4.03 replaced 211 by 076 1K4.01 0641 K2.02 replaced 2/1 by 0641 K2.01 0031 K4.02 replaced 2/1 by 0031 K4.04 061 1K5.02 replaced 2/1 by 061 1K5.01 G2/2.2.18 replaced 3/2 by G2 12.2.35 G4 12.4.39 replaced 3/4 by G4 12.4.21 EPE Topic selected is RO knowledge and inappropriate for SRO level. Additionally, there are no immediate actions associated with this system This topic is duplicated with SRO question 87 No applicable references to support a test item for system selected There is no guidance related to the topic selected There are no EOPs related to this system KA selected not appropriate for system topic. No AOP/EOP Duplicated on SRO question 96 The subject KIA isn't relevant at the subject facility.
Exact duplicate ()f KA on original 2010 Exam. Will replace with K2.01 and scramble distractors No design features or interlocks to support this topic KA solicits GFES style test item, resulted in LOD=1 test item.
No RO level knowledge of this topic to yield a test item above LOD=1 No RO Job Specific responsibilities that are different than normal job i