Text

2016-10 Final Outlines
	ML16336A575
Person / Time
Site:	Diablo Canyon
Issue date:	10/20/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16336A575 (42)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

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 3 3 3 3 3 3 18 6 Emergency &

Abnormal 2 1 2 2 N/A 1 2 N/A 1 9 4 Plant Evolutions Tier Totals 4 5 5 4 5 4 27 10 1 2 3 2 2 3 2 3 3 2 3 3 28 5 2.

Plant 2 1 1 1 1 0 1 1 1 1 1 1 10 3 Systems Tier Totals 3 4 3 3 3 3 4 4 3 4 4 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 with justification; 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 a category 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.

G* Generic K/As

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

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

1 2 3 1 2 000007 Reactor Trip - Stabilization - X EK1.05 Knowledge of the operational implications 3.3 39 Recovery / 1 of decay power as a function of time as they apply to the reactor trip. (CFR 41.8 / 41.10 / 45.3) 000008 Pressurizer Vapor Space X AA1.02 Ability to operate and / or HPI pump to 4.1 40 Accident / 3 control PZR level/pressure as they apply to the Pressurizer Vapor Space Accident. (CFR 41.7 /

45.5 / 45.6) 000009 Small Break LOCA / 3 X EA2.38 Ability to determine or interpret the 3.9 41 Existence of head bubble as they apply to a small break LOCA: (CFR 43.5 / 45.13) 000011 Large Break LOCA / 3 X EA2.13 Ability to determine or interpret the 3.7* 42 difference between overcooling and LOCA indications as they apply to a Large Break LOCA.

(CFR 43.5 / 45.13) 000015/17 RCP Malfunctions / 4 X AK3.01 Knowledge of the reason for the potential 2.5* 43 damage from high winding and/or bearing temperatures as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow).

(CFR 41.5, 41.10/45.6/45.13) 000022 Loss of Rx Coolant Makeup / 2 X AK1.03 Knowledge of the operational implications 3.0 44 of the relationship between charging flow and PZR level as they apply to Loss of Reactor Coolant Makeup. (CFR 41.8 / 41.10 / 45.3) 000025 Loss of RHR System / 4 X AA1.23 Ability to operate and / or monitor RHR 2.8 45 heat exchangers as they apply to the Loss of Residual Heat Removal System: (CFR 41.7 / 45.5

/ 45.6) 000026 Loss of Component Cooling X G2.2.39 Knowledge of less than or equal to one 46 Water / 8 hour Technical Specification action statements for systems. (CFR: 41.7 / 41.10 / 43.2 / 45.13)

G2.4.11 - Knowledge of abnormal condition 4.0 procedures. (IR 4.0) 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 X EK2.06 Knowledge of the interrelations between 2.9* 47 breakers, relays, and disconnects following an ATWS. (CFR 41.7 / 45.7) 000038 Steam Gen. Tube Rupture / 3 X EK1.02 Knowledge of the operational implications 3.2 48 of leak rate vs. pressure drop as they apply to the SGTR. (CFR 41.8 / 41.10 / 45.3) 000040 (W/E12) Steam Line Rupture - X G2.4.49 Ability to perform without reference to 4.6 49 Excessive Heat Transfer / 4 procedures those actions that require immediate operation of system components and controls.

(CFR: 41.10 / 43.2 / 45.6)

G2.4.2 - Knowledge of system set points, 4.5 interlocks and automatic actions associated with EOP entry conditions.

000054 Loss of Main Feedwater / 4 X AK3.03 Knowledge of the reasons for manual 3.8 50 control of AFW flow control valves as they apply to the Loss of Main Feedwater (MFW). (CFR 41.5,41.10 / 45.6 / 45.13) 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 X AA2.09 Ability to determine and interpret the 2.7 51 operational status of reactor building cooling unit as they apply to the Loss of Offsite Power:

Replaced with AA2.21 - Ability to determine and interpret the following as they apply to the Loss of 3.6 Offsite Power: EDG voltage and frequency indicators 000057 Loss of Vital AC Inst. Bus / 6 X G2.4.3 Ability to identify post-accident 3.7 52 instrumentation. (CFR: 41.6 / 45.4) 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 X AK3.04 Knowledge of the reasons for the effect 3.5 53 on Nuclear Service water discharge flow header of a loss of CCW as they apply to the Loss of Nuclear Service Water. (CFR 41.4, 41.8 / 45.7 )

AK3.03 - Guidance actions contained in EOP for 4.0 Loss of nuclear service water (ASW) 000065 Loss of Instrument Air / 8 X AA1.05 Ability to operate and / or monitor the 3.3* 54 following as they apply to the Loss of Instrument Air. (CFR 41.7 / 45.5 / 45.6) RPS W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 W/E05 Inadequate Heat Transfer - Loss X EK2.1 Knowledge of the interrelations between 3.7 55 of Secondary Heat Sink / 4 the (Loss of Secondary Heat Sink) and Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR: 41.7 / 45.7) 000077 Generator Voltage and Electric X AK2.05 Knowledge of the interrelations between 3.1 56 Grid Disturbances / 6 Generator Voltage and Electric Grid Disturbances and Pumps. (CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)

K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18/6

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

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 X AK3.02 Knowledge of the reasons for the 2.9 57 relationship between PZR pressure increase and reactor makeup/letdown imbalance as they apply to the Pressurizer level Control Malfunctions. (CFR 41.5, 41.10/45.6/45.13) 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 Fuel Handling Accident / 8 X AA2.01 AK2.01Knowledge of the 2.9 58 interrelations between the Fuel Handling Incidents and fuel handling equipment.

(CFR 41.7 / 45.7)

Ability to determine and interpret the following as they apply to the Fuel 3.2 Handling Incidents: ARM system indications 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid Radwaste Rel. / 9 X AA1.02 Ability to operate and / or monitor 3.3 59 the ARM system as they apply to the Accidental Liquid Radwaste Release.

NOTE: ARM should be PRM as rad monitor for liquid radwaste is a process, not area monitor at DCPP (CFR 41.7 /

45.5 / 45.6) 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 Control Room Evac. / 8 000069 Loss of CTMT Integrity / 5 X G2.1.7 Ability to evaluate plant 4.4 60 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5

/ 45.12 / 45.13) 000074 Inad. Core Cooling / 4 X EK3.08 Knowledge of the reasons for the 4.1 61 Securing RCPs as they apply to the Inadequate Core Cooling. (CFR 41.5 /

41.10 / 45.6 / 45.13) 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 X EK1.2 Knowledge of the operational 3.4 62 implications of the Normal, abnormal and emergency operating procedures associated with (SI Termination).as they apply to the (SI Termination) (CFR: 41.8 /

41.10, 45.3)

W/E03 LOCA Cooldown - Depress. / 4 X EK2.1 EK2.2 - Knowledge of the 3.7 63 interrelations between the (LOCA Cooldown and Depressurization) and the facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility..

(CFR: 41.7 / 45.7) (KA statement/importance for EK2.2 not EK2.1)

W/E13 Steam Generator Over-pressure / 4 X EA2.1 Ability to determine and interpret the 2.9 64 facility conditions and selection of appropriate procedures during abnormal and emergency operations as they apply to the (Steam Generator Overpressure)

(CFR: 43.5 / 45.13)

W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 X EK2.1 Knowledge of the interrelations 3.0 65 between the (High Containment Radiation) and the Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR: 41.7 / 45.7)

K/A Category Point Totals: 1 2 2 1 2 1 Group Point Total: 9/4

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

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 4 003 Reactor Coolant Pump X A1.08 Ability to predict and/or monitor 2.5 1 changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including Seal water temperature.

(CFR: 41.5 / 45.5)

G2.2.4 Ability to explain the variations 003 Reactor Coolant Pump X in control board/control room l layouts, 3.6 systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10 /

45.1 / 45.13)

G2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the 3.1 2 status of limiting conditions for operations. (CFR: 41.10 / 43.2 /

45.13) 004 Chemical and Volume X A1.09 Ability to predict and/or monitor 3.6 3 Control changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including RCS pressure and temperature. (CFR: 41.5 / 45.5) 005 Residual Heat Removal X K5.05 Knowledge of the operational 2.7* 4 implications of the plant response during "solid plant": pressure change due to the relative incompressibility of water as they apply the RHRS. (CFR:

41.5 / 45.7) 006 Emergency Core Cooling X K4.14 Knowledge of ECCS design 3.9 5 feature(s) and/or interlock(s) which provide for Cross-Connection of HPI/LPI/SIP. (CFR: 41.7) 007 Pressurizer Relief/Quench X K5.02 Knowledge of the operational 3.1 6 Tank implications of the method of forming a steam bubble in the PZR as they apply to PRTS. (CFR: 41.5 / 45.7) 008 Component Cooling Water X G2.2.25 Knowledge of the bases in 3.2 7 Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2)

G2.1.28 Knowledge of the purpose 4.1 and function of major system components and controls. (CFR: 41.7) 008 Component Cooling Water X K3.03 Knowledge of the effect that a 4.1 8 loss or malfunction of the CCWS will have on the RCP. (CFR 41.7) 010 Pressurizer Pressure Control X A4.03 Ability to manually operate 4.0 9 and/or monitor PORV and block valves in the control room. (CFR: 41.7

/ 45.5 to 45.8)

012 Reactor Protection X K2.01 Knowledge of bus power 3.3 10 supplies to the RPS channels, components, and interconnections.

(CFR: 41.7) 012 Reactor Protection X K6.03 Knowledge of the effect of a 3.1 11 loss or malfunction of the trip logic circuits will have on the RPS. (CFR:

41.7 / 45/7) 013 Engineered Safety Features X K2.01 Knowledge of bus power 3.6* 12 Actuation supplies to ESFAS/safeguards equipment control. (CFR 41.7) 013 Engineered Safety Features X K5.02 Knowledge of the operational 2.9 13 Actuation implications of safety system logic and reliability as they apply to the ESFAS.

(CFR: 41.5 / 45.7) 022 Containment Cooling X A3.01 Ability to monitor automatic 4.1 14 operation of the CCS, including initiation of safeguards mode of operation. (CFR: 41.7 / 45.5) 026 Containment Spray X K1.01 Knowledge of the physical 4.2 15 connections and/or cause effect relationships between the CSS and ECCS. (CFR: 41.2 to 41.9 / 45.7 to 45.8) 039 Main and Reheat Steam X A3.02 Ability to monitor automatic 3.1 16 operation of the MRSS, including isolation of the MRSS. (CFR: 41.5 /

45.5) 039 Main and Reheat Steam X K4.06 Knowledge of MRSS design 3.3 17 feature(s) and/or interlock(s) which prevent reverse steam flow on steam line break. (CFR: 41.7) 059 Main Feedwater X K3.02 Knowledge of the effect that a 3.6 18 loss or malfunction of the MFW will have on the AFW system. (CFR: 41.7

/ 45.6) 061 Auxiliary/Emergency X K6.02 Knowledge of the effect of a 2.6 19 Feedwater loss or malfunction of Pumps will have on the AFW components. (CFR: 41.7 /

45.7) 062 AC Electrical Distribution X A1.01 Ability to predict and/or monitor 3.4 20 changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including the significance of D/G load limits. (CFR:

41.5 / 45.5) 062 AC Electrical Distribution X A4.03 Ability to manually operate 2.8 21 and/or monitor synchro scope, including an understanding of running and incoming voltages in the control room. (CFR: 41.7 / 45.5 / to 45.8)

063 DC Electrical Distribution X G2.4.1 Knowledge of EOP entry 4.6 22 conditions and immediate action steps. (CFR: 41.10 / 43.5 / 45.13)

G2.4.6Knowledge of EOP mitigation 3.7 strategies. (CFR: 41.10 / 43.5 /

45.13) 064 Emergency Diesel Generator X K1.02 Knowledge of the physical 3.1 23 connections and/or cause effect relationships between the ED/G system and the D/G cooling water system. (CFR: 41.2 to 41.9 / 45.7 to 45.8) 073 Process Radiation Monitoring X A2.01 Ability to (a) predict the impacts 2.5 24 of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or failed power supply. (CFR: 41.5 / 43.5

/ 45.3 / 45.13) 076 Service Water X K2.08 Knowledge of bus power 3.1* 25 supplies to ESF-actuated MOVs.

(CFR: 41.7)

K2.01 Knowledge of bus power 2.7 supplies to Service Water.

078 Instrument Air X A4.01 Ability to manually operate 3.1 26 and/or monitor pressure guages in the control room. (CFR: 41.7 / 45.5 to 45.8) 103 Containment X A2.03 Ability to (a) predict the impacts 3.5* 27 of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Phase A and B isolation. (CFR: 41.5 / 43.5 /

45.3 / 45.13) 103 Containment X A2.05 Ability to (a) predict the impacts 2.9 28 of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Emergency Containment entry. (CFR:

41.5 / 43.5 / 45.3 / 45.13)

K/A Category Point Totals: 2 3 2 2 3 2 3 3 2 3 3 Group Point Total: 28/5

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

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 4 001 Control Rod Drive 002 Reactor Coolant X K6.06 Knowledge of the effect or a loss 2.5 29 or malfunction on Sensors and Detectors.

(CFR: 41.7 / 45.7) 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation X K2.01 Knowledge of bus power supplies 3.3 30 to NIS channels, components, and interconnections. (CFR: 41.7) 016 Non-Nuclear Instrumentation X K5.01 Knowledge of the operational 2.7 31 implication of separation of control and protection circuits as they apply to the NNIS. (CFR: 41.5 / 45.7)

K3.01 -Knowledge of the effect that a 3.4*

loss or malfunction of the NNIS will have on the following: RCS 017 In-Core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling X A1.02 Knowledge of the physical 2.5 32 connections and/or cause effect relationships between the Spent Fuel Pool Cooling System and RHRS. (CFR:

41.2 to 41.9 / 45.7 to 45.8)

A1.01 Ability to predict and/or monitor changes in parameters (to prevent 2.7 exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including: Spent fuel pool water level 034 Fuel Handling Equipment X A4.02 Ability to manually operate and/or 3.5 33 monitor neutron levels in the control room. (CFR: 41.7 / 45.5 to 45.8) 035 Steam Generator X A3.01 Ability to monitor automatic 4.0 34 operation of the S/G including S/G water level control. (CFR: 41.7 / 45.5) 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste

071 Waste Gas Disposal X G2.1.30 Ability to locate and operate 4.4 35 components, including local controls.

(CFR: 41.7 / 45.7) 072 Area Radiation Monitoring X K4.01 Knowledge of ARM system design 3.3* 36 feature(s) and/or interlock(s) which provide for containment ventilation isolation. (CFR: 41.7) 075 Circulating Water 079 Station Air X K1.01 Knowledge of the physical 3.0 37 connections and/or cause effect relationships between the SAS and IAS.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 086 Fire Protection X A2.04 Ability to (a) predict the impacts of 3.3 38 failure to actuate the FPS when required, resulting in fire damage on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of failure to actuate the FPS when required, resulting in fire damage: (CFR: 41.5 / 43.5 / 45.3 / 45.13)

K/A Category Point Totals: 1 1 0 1 1 1 1 1 1 1 1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

Knowledge of administrative requirements for temporary 2.1.15 2.7 66 management directives, such as standing orders, night orders, Operations memos, etc. (CFR: 41.10 / 45.12) 2.1.32 Ability to explain and apply system limits and precautions. 3.8 67

1. (CFR: 41.10 / 43.2 / 45.12)

Conduct of 2.1.45 Ability to identify and interpret diverse indications to 4.3 68 Operations validate the response of another indication. (CFR: 41.7 /

43.5 / 45.4)

Subtotal 2.2.42 Ability to recognize system parameters that are entry- 3.9 69 level conditions for Technical Specifications. (CFR: 41.7 /

41.10 / 43.2 / 43.3 / 45.3) 2.2.43 3.0 Knowledge of the process used to track inoperable alarms.

2. 2.2.44 Ability to interpret control room indications to verify the 4.2 70 Equipment status and operation of a system, and understand how Control operator actions and directives affect plant and system conditions. (CFR: 41.5 / 43.5 / 45.12)

Subtotal 2.3.11 Ability to control radiation releases. (CFR: 41.11 / 43.4 / 3.8 71 45.10)

Knowledge of radiation monitoring systems, such as fixed 2.3.15 2.9 72 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR:

3. 41.12 / 43.4 / 45.9)

Radiation Control Subtotal 2.4.4 Ability to recognize abnormal indications for system 4.5 73 operating parameters that are entry-level conditions for emergency and abnormal operating procedures. (CFR:

41.10 / 43.2 / 45.6) 4.

Emergency 2.4.32 Knowledge of operator response to loss of all 3.6 74 Procedures / annunciators. (CFR: 41.10 / 43.5 / 45.13)

Plan 2.4.37 Knowledge of the lines of authority during implementation 3.0 75 of the emergency plan. (CFR: 41.10 / 45.13)

Subtotal

Tier 3 Point Total 10 7 ES-401 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

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 18 3 3 6 Emergency &

Abnormal 2 N/A N/A 9 2 2 4 Plant Evolutions Tier Totals 27 5 5 10 1 28 3 2 5 2.

Plant 2 10 0 2 1 3 Systems Tier Totals 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 2 1 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).