ML093640747
| ML093640747 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/08/2009 |
| From: | Division of Nuclear Materials Safety II |
| To: | Duke Energy Carolinas |
| References | |
| 50-369/09-302, 50-370/09-302 | |
| Download: ML093640747 (12) | |
Text
FACILITY NAME: McGuire Section 1 REPORT NUM BER: 05000369,370/2009302 DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:
1!1' Draft Written Exam sample plan (ES-401-1/2)
.. ~D Draft Administrative Topics Outline (ES-301-1)
~~D Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)
Location of Electronic Files:
Draft RO/SRO Written Outline:
Draft RO Written Exam Outline ES-401-2.pdf (Attached)
Admin Topics RO:
NA Admin Topics SRO:
NA Control Room Systems Outline RO/SROi:
NA Control Room Systems Outline SROU:
NA Submitted By:
~.
VerifiedBY~~
FACILITY NAME: McGuire Section 1 REPORT NUMBER: 05000369,370/2009302 DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:
lEI' Draft Written Exam sample plan (ES-401-1/2)
.~D Draft Administrative Topics Outline (ES-301-1)
~~D Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)
Location of Electronic Files:
Draft RO/SRO Written Outline:
Draft RO Written Exam Outline ES-401-2.pdf (Attached)
Admin Topics RO:
NA Admin Topics SRO:
NA Control Room Systems Outline RO/SROi:
NA Control Room Systems Outline SROU:
NA Submitted By:
~o'c~ verifiedBY~£)~
ES 401, Rev 9 Question 1
1801 2
1802 3
1803 4
1804 5
1805 6
1806 7
1807
~\\
2009 RO NRC R.
ike Examination f) fJ *. Jql--r. f II N IJ L Combined PWR Written Examination Outline KIA Number KIA Description SYS003 A1.02 KIA System*
Reactor Coolant Pump System (RCPS)
Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2 11 RO 2.9 SRO 2.9 Ability to predict and/or monitor changes in parameters RCP pump and motor bearing temperatures..........................
(to prevent exceeding design limits) associated with operating the RCPS controls including: (CFR: 41.5/45.5)
SYS003 A3.01 Reactor Coolant Pump System (RCPS)
Ability to monitor automatic operation of the RCPS, including: (CFR: 41.7 145.5)
Seal injection flow.
SYS004 KS.49 Chemical and Volume Control System T/G 2 1 1 RO 3.3 SRO 3.2 T/G 2 11 RO 2.7 SRO 3.3 Knowledge of the operational implications of the following concepts as they apply to the CVCS: (CFR: 41.5/45.7)
Purpose and method of hydrogen removal from RCS before opening system:
explosion hazard, nitrogen purge.....................
SYSOOS 2.4.S0 Residual Heat Removal System (RHRS)
T/G 2 11 RO 4.2 SRO 4.0 SYS005 GENERIC Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10/43.5/45.3)
SYS006 K2.01 Emergency Core Cooling System (ECCS)
Knowledge of bus power supplies to the following: (CFR:
41.7)
ECCS pumps SYS006 K2.04 Emergency Core Cooling System (ECCS)
Knowledge of bus power supplies to the following: (CFR:
41.7)
ESFAS-operated valves SYS007 A1.01 Pressurizer Relief Tank/Quench Tank System (PRTS)
T/G 2/1* RO 3.6.
SRO 3.9 T/G 2 11 RO 3.6 SRO 3.8 T/G 211 RO 2.9 SRO 3.1 Ability to predict and/or monitor changes in parameters (to prevent exceeding deSign limits) associated with operating the PRTS controls including: (CFR: 41.5/45.5)
Maintaining quench tank water level within limits Page 1 of 11 ES 401, Rev 9 Question 1
1801 2
1802 3
1803 4
1804 5
1805 6
1806 7
1807 2009 RO NRC ~.ke Examination
/) 1L{ql!-r f fl N IJ L Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS003 A1.02 Reactor Coolant Pump System (RCPS)
T/G 2 I 1 RO 2.9 Ability to predict and/or monitor changes in parameters RCP pump and motor bearing temperatures..........................
(to prevent exceeding design limits) associated with operating the RCPS controls including: (CFR: 41.5/45.5)
SYS003 A3.01 Reactor Coolant Pump System (RCPS)
T/G 2 I 1 RO 3.3 Ability to monitor automatic operation of the RCPS, including: (CFR: 41.7/45.5)
Seal injection flow...............................................
SYS004 K5.49 Chemical and Volume Control System T/G 2 I 1 RO 2.7 SRO 2.9 SRO 3.2 SRO 3.3 Knowledge of the operational implications of the following concepts as they apply to the CVCS: (CFR: 41.5/45.7)
Purpose and method of hydrogen removal from RCS before opening system:
explosion hazard, nitrogen purge.....................
SYS005 2.4.50 Residual Heat Removal System (RHRS)
T/G 2 I 1 RO 4.2 SRO 4.0 SYS005 GENERIC Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10/43.5/45.3)
SYS006 K2.01 Emergency Core Cooling System (ECCS)
Knowledge of bus power supplies to the following: (CFR:
41.7)
ECCS pumps SYS006 K2.04 Emergency Core Cooling System (ECCS)
Knowledge of bus power supplies to the following: (CFR:
41.7)
ESFAS-operated valves SYS007 A1.01 Pressurizer Relief Tank/Quench Tank System (PRTS)
T/G 2 I 1 RO 3.6 T/G 2 I 1 RO 3.6 T/G 2 I 1 RO 2.9 Ability to predict and/or monitor changes in parameters Maintaining quench tank water level within limits (to prevent exceeding design limits) associated with operating the PRTS controls including: (CFR: 41.5/45.5)
Page 1 of 11 SRO 3.9 SRO 3.8 SRO 3.1
ES 401, Rev 9 Question 8
1808 9
1809 10 1810 11 1811 12 1812 13 1813 i~
2009 RO NRC ~ lke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS008 A2.03 Component Cooling Water System (CCWS)
Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunc-tions or operations: (CFR: 41.5/43.5/45.3/45.13)
High/low CCW temperature SYS010 K6.04 Pressurizer Pressure Control System (PZR PCS)
Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: (CFR: 41.7 / 45.7)
PRT.....
SYS012 K6.03 Reactor Protection System (RPS)
T/G 211 RO 3.0 T/G 211 RO 2.9 T/G 211 RO 3.1 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: (CFR: 41.7 /45/7)
Trip logic circuits................................................
SYS013 A4.03 Engineered Safety Features Actuation System (ESFAS)
Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)
ESFAS initiation SYS013 K1.01 Engineered Safety Features Actuation System (ESFAS)
T/G 211 RO 4.5 T/G 2 11 RO 4.2 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)
Initiation signals for ESF circuit logic...............................
SYS022 A2.03 Containment Cooling System (CCS)
T/G 211 RO 2.6 Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; 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)
Fan motor thermal overload/high-speed operation.....................
Page 2 of 11 SRO 3.2 SRO 3.2 SRO 3.5 SRO 4.7 SRO 4.4 SRO 3.0 ES 401, Rev 9 Question 8
1808 9
1809 10 1810 11 1811 12 1812 13 1813 2009 RO NRC f\\
"ke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS008 A2.03 Component Cooling Water System (CCWS)
Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunc-tions or operations: (CFR: 41.5 /43.5 /45.3 /45.13)
High/low CCW temperature SYS010 KG.04 Pressurizer Pressure Control System (PZR PCS)
T/G 211 RO 3.0 T/G 2 I 1 RO 2.9 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: (CFR: 41.7 /45.7)
PRT...........................................................
SYS012 KG.03 Reactor Protection System (RPS)
T/G 2 11 RO 3.1 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: (CFR: 41.7 / 45/7)
Trip logic circuits................................................
SYS013 A4.03 Engineered Safety Features Actuation System (ESFAS)
T/G 2 I 1 RO 4.5 Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)
ESFAS initiation.................................................
SYS013 K1.01 Engineered Safety Features Actuation System (ESFAS)
T/G 2 I 1 RO 4.2 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8)
Initiation signals for ESF circuit logic...............................
SYS022 A2.03 Containment Cooling System (CCS)
T/G 2 I 1 RO 2.G Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; 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)
Fan motor thermal overload/high-speed operation.....................
Page 2 of 11 SRO 3.2 SRO 3.2 SRO 3.5 SRO 4.7 SRO 4.4 SRO 3.0
ES 401, Rev 9 Question 14 1814 15 1815 16 1816 17 1817 18 1818 19 1819 20 1820
(\\
2009 RO NRC R.
ike Examination Combined PWR Written Examination Outline KIA Number KIA Description SYS025 K502 KIA System Ice Condenser System Knowledge of operational implications of the following concepts as they apply to the ice condenser system:
(CFR: 41.5/45.7)
Heat transfer.............
SYS026 A2.0S Containment Spray System (CSS)
Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 211 RO 2.6*
SRO 2.S*
T/G 211 RO 3.2 SRO 3.7 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; 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)
Safe securing of containment spray when it can be done)...
SYS026 2.2.12 Containment Spray System (CSS)
T/G 211 RO 3.7 SRO 4.1 SYS026 GENERIC Knowledge of surveillance procedures. (CFR: 41.10/45.13)
SYS039 K3.04 Main and Reheat Steam System (MRSS)
T/G 211 RO 2.5*
SRO 2.6*
Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: (CFR: 41.7 145.6)
SYS059 K3.02 Main Feedwater (MFW) System Knowledge of the effect that a loss or malfunction of the MFW will have on the following: (CFR: 41.7 1 45.6)
SYS059 K3.03 Main Feedwater (MFW) System MFW pumps T/G 2 11 RO 3.6 AFWsystem T/G 2 11 RO 3.5 Knowledge of the effect that a loss or malfunction of the MFW will have on the following: (CFR: 41.7 145.6)
S/GS...........................................................
SYS061 K1.01 Auxiliary I Emergency Feedwater (AFW) System Knowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: (CFR: 41.2 to 41.9/45.7 to 45.8)
S/G system...
Page 3 of 11 T/G 2 11 RO 4.1 SRO 3.7 SRO 3.7.
SRO 4.1 ES 401, Rev 9 Question 14 1814 15 1815 16 1816 17 1817 18 1818 19 1819 20 1820 KIA Number KIA Description SYS025 K502 2009 RO NRC R
.ke Examination Combined PWR Written Examination Outline KIA System Ice Condenser System Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2 I 1 RO 2.6*
SRO 2.8*
Knowledge of operational implications of the following concepts as they apply to the ice condenser system:
(CFR: 41.5/45.7)
Heat transfer....................................................
SYS026 A2.08 Containment Spray System (CSS)
T/G 2 I 1 RO 3.2 SRO 3.7 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; 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)
Safe securing of containment spray when it can be done)...............
SYS026 2.2.12 Containment Spray System (CSS)
T/G 2 I 1 RO 3.7 SRO 4.1 SYS026 GENERIC Knowledge of surveillance procedures. (CFR: 41.10/45.13)
SYS039 K3.04 Main and Reheat Steam System (MRSS)
T/G 2 I 1 RO 2.5*
SRO 2.6*
Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: (CFR: 41.7/45.6)
SYS059 K3.02 Main Feedwater (MFW) System Knowledge of the effect that a loss or malfunction of the M FW will have on the following: (CFR: 41.7 /45.6)
SYS059 K3.03 Main Feedwater (MFW) System Knowledge of the effect that a loss or malfunction of the M FW will have on the following: (CFR: 41.7 /45.6)
MFW pumps T/G 2 I 1 RO 3.6 AFW system T/G 2 I 1 RO 3.5 S/GS...........................................................
SYS061 K1.01 Auxiliary I Emergency Feedwater (AFW) System T/G 2 I 1 RO 4.1 Knowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8)
S/G system.....................................................
SRO 4.1
ES 401, Rev 9 Question 21 1821 22 1822 23 1823 24 1824 25 1825 26 1826 27 1827 r~
2009 RO NRC R ike Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS062 K4.10 AC Electrical Distribution System Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: (CFR:
41.7)
Uninterruptable ac power sources T/G 2 11 RO 3.1 SRO 3.5 SYS063 K2.01 DC Electrical Distribution System T/G 2/1 RO 2.9*
SRO 3.1*
Knowledge of bus power supplies to the following: (CFR:
41.7)
Major DC loads SYS064 A3.01 Emergency Diesel Generator (ED/G) System T/G 2 11 RO 4.1 Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7 /45.5)
Automatic start of compressor and ED/G............................
SYS064 K6.08 Emergency Diesel Generator (ED/G) System T/G 2 11 RO 3.2 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7/
45.7)
Fuel oil storage tanks...
SYS073 A4.03 Process Radiation Monitoring (PRM) System T/G 2 11 RO 3.1 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /45.5 to 45.8)
SYS076 K4.06 Service Water System (SWS)
Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41/7)
SYS078 A3.01 Instrument Air System (lAS)
Ability to monitor automatic operation of the lAS, including: (CFR: 41.7/45.5)
Check source for operability demonstration..........................
T/G 211 RO 2.8 Service water train separation......................................
T/G 2 11 RO 3.1 Air pressure.....................................................
Page 4 of 11 SRO 4.0 SRO 3.3 SRO 3.2 SRO 3.2 SRO 3.2 ES 401, Rev 9 Question 21 1821 22 1822 23 1823 24 1824 25 1825 26 1826 27 1827 2009 RO NRC f\\
"ke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS062 K4.10 AC Electrical Distribution System Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: (CFR:
41.7)
Uninterruptable ac power sources T/G 2/ 1 RO 3.1 SRO 3.5 SYS063 K2.01 DC Electrical Distribution System T/G 2/1 RO 2.9*
SRO 3.1*
Knowledge of bus power supplies to the following: (CFR:
41.7)
Major DC loads SYS064 A3.01 Emergency Diesel Generator (ED/G) System T/G 2/ 1 RO 4.1 Ability to monitor automatic operation of the ED/G system, including: (CFR: 41.7/45.5)
Automatic start of compressor and ED/G............................
SYS064 K6.08 Emergency Diesel Generator (ED/G) System T/G 2/ 1 RO 3.2 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: (CFR: 41.7/
45.7)
Fuel oil storage tanks.............................................
SYS073 A4.03 Process Radiation Monitoring (PRM) System T/G 2 / 1 RO 3.1 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /45.5 to 45.8)
SYS076 K4.06 Service Water System (SWS)
Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following: (CFR: 41/7)
SYS078 A3.01 Instrument Air System (lAS)
Ability to monitor automatic operation of the lAS, including: (CFR: 41.7/45.5)
Check source for operability demonstration..........................
T/G 2/ 1 RO 2.8 Service water train separation......................................
T/G 2/ 1 RO 3.1 Air pressure.....................................................
Page 4 of 11 SRO 4.0 SRO 3.3 SRO 3.2 SRO 3.2 SRO 3.2
ES 401, Rev 9 Question 28 1828 29 1829 30 1830 31 1831 32 1832 33 1833 34 1834 2009 RO NRC ~.ke Examination Combined PWR Written Examination Outline KIA Number KIA Description SYS103 A4.03 KIA System Containment System Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)
SYS002 K3.03 Reactor Coolant System (RCS)
Knowledge of the effect that a loss or malfunction of the RCS will have on the following: (CFR: 41.7)
ESF slave relays Containment SYS014 A1.02 Rod Position Indication System (RPIS)
Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 211 RO 2.7*
SRO 2.7*
T/G 212 RO 4.2 SRO 4.6 T/G 212 RO 3.2 SRO 3.6 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including: (CFR: 41.5/45.5)
Control rod position indication on control room panels................
SYS017 K6.01 In-Core Temperature Monitor (ITM) System Knowledge of the effect of a loss or malfunction of the following ITM system components: (CFR: 41.7 / 45.7)
Sensors and detectors SYS029 A2.03 Containment Purge System (CPS)
T/G 2/2 RO 2.7 SRO 3.0 T/G 2/2 RO 2.7 SRO 3.1 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge 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)
Startup operations and the associated required valve lineups.............
SYS034 A3.03 Fuel Handling Equipment System (FHES)
T/G 212 RO 2.9 Ability to monitor automatic operation of the Fuel Handling System, including: (CFR: 41.7/45.5)
High flux at shutdown.............................................
SRO 3.3 SYS045 K4.13 Main Turbine Generator (MT/G) System T/G 212 RO 2.6*
SRO 2.8*
Knowledge of MT/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Overs peed protection.............................................
Page 5 of 11 ES 401, Rev 9 Question 28 1828 29 1829 30 1830 31 1831 32 1832 33 1833 34 1834 2009 RO NRC f\\
.ke Examination Combined PWR Written Examination Outline KiA Number KiA Description SYS103 A4.03 KiA System Containment System Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)
SYS002 K3.03 Reactor Coolant System (RCS)
Knowledge of the effect that a loss or malfunction of the RCS will have on the following: (CFR: 41.7)
ESF slave relays Containment SYS014 A1.02 Rod Position Indication System (RPIS)
Form ES-401-2/3 Tier/Group Importance RO/SRO T/G 2/1 RO 2.7*
SRO 2.7*
T/G 2/2 RO 4.2 SRO 4.S T/G 2/2 RO 3.2 SRO 3.S Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including: (CFR: 41.5 /45.5)
Control rod position indication on control room panels................
SYS017 KS.01 In-Core Temperature Monitor (ITM) System Knowledge of the effect of a loss or malfunction of the following ITM system components: (CFR: 41.7 /45.7)
Sensors and detectors SYS029 A2.03 Containment Purge System (CPS)
T/G 2 /2 RO 2.7 SRO 3.0 T/G 2 /2 RO 2.7 SRO 3.1 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge 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)
Startup operations and the associated required valve lineups.............
SYS034 A3.03 Fuel Handling Equipment System (FHES)
T/G 2/2 RO 2.9 Ability to monitor automatic operation of the Fuel Handling System, including: (CFR: 41.7/45.5)
High flux at shutdown.............................................
SRO 3.3 SYS045 K4.13 Main Turbine Generator (MTlG) System T/G 2/2 RO 2.S*
SRO 2.8*
Knowledge of MT/G system design feature(s) and/or interlock(s) which provide for the following: (CFR: 41.7)
Overspeed protection.............................................
Page50f 11
ES401, Rev 9 Que!?tion 35 1835 36 1836 37 1837 38 1838 39 1839 40 1840 41 1841 2009 RO NRC R~e Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO SYS055 K1.06 Condenser Air Removal System (CARS)
T/G 2 12 RO 2.6 SRO 2.6 Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8)
SYS068 2.4.50 Liquid Radwaste System (LRS)
SYS068 GENERIC PRM system T/G 212 RO 4.2 SRO 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10/43.5/45.3)
SYS071 A4.14 Waste Gas Disposal System (WGDS)
T/G 2 12 RO 2.8 SRO 3.0 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 /45.5 to 45.8)
SYS075 K2.03 Circulating Water System Knowledge of bus power supplies to the following: (CFR:
41.7)
EPE007 2.4.2 Reactor Trip EPE007 GENERIC WDGS status alarms T/G 2/2 RO 2.6*
SRO 2.7*
Emergency/essential SWS pumps...................................
T/G 1 1 1 RO 4.5 SRO 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.'7 /45.7 /45.8)
APE008 AK1.01 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck 0 T/G 1 11 RO 3.2 SRO 3.7 Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: (CFR 41.8/41.10/45.3)
Thermodynamics and flow characteristics of open or leaking valves APE015/017 AK2.08 Reactor Coolant Pump (RCP) Malfunctions Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: (CFR 41.7 / 45.7)
CCWS.....................
Page 6 of 11 T/G 1 11 RO 2.6 SRO 2.6 ES 401, Rev 9 Question 35 1835 36 1836 37 1837 38 1838 39 1839 40 1840 41 1841 2009 RO NRC f\\.
,ke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KJA Number KJA Description KJA System Tier/Group Importance RO/SRO SYS055 K1.06 Condenser Air Removal System (CARS)
T/G 2/2 RO 2.6 SRO 2.6 Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: (CFR: 41.2 to 41.9 /45.7 to 45.8)
SYS06S 2.4.50 Liquid Radwaste System (LRS)
SYS068 GENERIC PRM system T/G 2/2 RO 4.2 SRO 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10/43.5/45.3)
SYS071 A4.14 Waste Gas Disposal System (WGDS)
T/G 2/2 RO 2.S SRO 3.0 Ability to manually operate and/or monitor in the control room: (CFR: 41.7/45.5 to 45.8)
SYS075 K2.03 Circulating Water System Knowledge of bus power supplies to the following: (CFR:
41.7)
EPE007 2.4.2 Reactor Trip EPE007 GENERIC WDGS status alarms T/G 2/2 RO 2.6*
SRO 2.7*
Emergency/essential SWS pumps...................................
T/G 1 / 1 RO 4.5 SRO 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.7 / 45.7 / 45.8)
APEOOS AK1.01 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck 0 T/G 1 / 1 RO 3.2 SRO 3.7 Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: (CFR 41.8 /41.10/45.3)
Thermodynamics and flow characteristics of open or leaking valves APE015/017 AK2.0S Reactor Coolant Pump (RCP) Malfunctions T/G 1/1 RO 2.6 SRO 2.6 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: (CFR 41.7 / 45.7)
CCWS.........................................................
Page 6 of 11
ES 401, Rev 9 Question 42 1842 43 1843 44 1844 45 1845 46 1846 47 1847 48 1848
!~
2009 RO NRC R.
-iike Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System TierlGroup Importance RO/SRO APE022 AK1.02 Loss of Reactor Coolant Makeup T/G 1 / 1 RO 2.7 SRO 3.1 Knowledge of the operational implications of the following concepts* as they apply to Loss of Reactor Coolant Makeup: (CFR 41.8/41.10/45.3)
Relationship of charging flow to pressure differential between charging and RCS.................................
APE026 AA2.04 Loss of Component Cooling Water (CCW)
Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR:
43.5 145.13)
The normal values and upper limits for the temperatures of the components cooled by CCW...
APE027 AK3.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 /1 RO 2.8 SRO 3.3 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.5,41.10/45.6/45.13)
Why, if PZR level is lost and then restored, that pressure recovers much more slowly............
EPE029 2.4.2 Anticipated Transient Without Scram (ATWS)
T/G 1 / 1 RO 4.5 SRO 4.6 EPE029 GENERIC Knowledge of system set pOints, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.7 145.7 1 45.8)
EPE038 EA1.10 Steam Generator Tube Rupture (SGTR)
T/G 1/1 RO 3.7*
SRO 3.7 Ability to operate and monitor the following as they apply to a SGTR: (CFR 41.7 145.5/45.6)
APE040 AK1.01 Steam Line Rupture Knowledge of the operational implications of the following concepts as they apply to Steam Line Rupture: (CFR 41.8/41.10/45.3)
APE054 AA2.08 Loss of Main Feedwater (MFW)
Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): (CFR: 43.51 45.13)
Control room radiation monitoring indicators and alarms...............
T/G 1 / 1 RO 4.1 SRO 4.4 Consequences of PTS T/G 1 / 1 RO 2.9 SRO 3.3*
Steam flow-feed trend recorder....................................
Page 7 of 11 ES 401, Rev 9 Question 42 1842 43 1843 44 1844 45 1845 46 1846 47 1847 48 1848 2009 RO NRC f...
"ke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KiA Number KiA Description KiA System Tier/Group Importance RO/SRO APE022 AK1.02 Loss of Reactor Coolant Makeup T/G 1/1 RO 2.7 SRO 3.1 Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: (CFR 41.8 1 41.10/45.3)
Relationship of charging flow to pressure differential between charging and RCS.................................
APE026 AA2.04 Loss of Component Cooling Water (CCW)
Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: (CFR:
43.5/45.13)
The normal values and upper limits for the temperatures of the components cooled by CCW.................................
APE027 AK3.04 Pressurizer Pressure Control System (PZR PCS) Malfunction T/G 1 I 1 RO 2.8 SRO 3.3 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: (CFR 41.5,41.10/45.6/45.13)
Why, if PZR level is lost and then restored, that pressure recovers much more slowly................................
EPE029 2.4.2 Anticipated Transient Without Scram (ATWS)
T/G 1 11 RO 4.5 SRO 4.6 EPE029 GENERIC Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.7/45.7/45.8)
EPE038 EA1.10 Steam Generator Tube Rupture (SGTR)
T/G 1 11 RO 3.7*
SRO 3.7 Ability to operate and monitor the following as they apply to a SGTR: (CFR 41.7/45.5/45.6)
APE040 AK1.01 Steam Line Rupture Knowledge of the operational implications of the following concepts as they apply to Steam Line Rupture: (CFR 41.8/41.10/45.3)
APE054 AA2.08 Loss of Main Feedwater (MFW)
Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW): (CFR: 43.51 45.13)
Control room radiation monitoring indicators and alarms...............
T/G 1 I 1 RO 4.1 SRO 4.4 Consequences of PTS T/G 1 I 1 RO 2.9 SRO 3.3*
Steam flow-feed trend recorder....................................
Page 7 of 11
ES 401, Rev 9 Question 49 1849 50 1850 51 1851 52 1852 53 1853 54 1854 2009 RO NRC nke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO EPE055 EK3.02 Loss of Offsite and Onsite Power (Station Blackout)
T/G 1 11 RO 4.3 SRO 4.6 Knowledge of the reasons for the following responses as the apply to the Station Blackout: (CFR 41.5 141.10 1 45.6/45.13)
APE056 AA2.37 Loss of Offsite Power Ability to determine and interpret the following as they apply to the Loss of Offsite Power: (CFR: 43.5 1 45.13)
Actions contained in EOP for loss of offsite and onsite power T/G 1/1 RO 3.7*
SRO 3.8 ED/G indicators for the following: voltage, frequency, load, load-status, and closure of bus tie breakers......................
APE057 AA1.06 Loss of Vital AC Electrical Instrument Bus T/G 1 11 RO 3.5 SRO 35 Ability to operate and 1 or monitor the following as they apply to the Loss of Vital AC Instrument Bus: (CFR 41.7 1 45.5/45.6)
APE058 AK3.02 Loss of DC Power Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: (CFR 41.5,41.10 1 45.6/45.1)
APE062 AA1.05 Loss of Nuclear Service Water Ability to operate and 1 or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): (CFR 41.7/45.5/45.6)
WE04 EK2.2 LOCA Outside Containment Knowledge of the interrelations between the (LOCA Outside Containment) and the following:
(CFR:41.7/45.7)
Manual control of components for which automatic control is lost.......
T/G 1 11 RO 4.0 SRO 4.2 Actions contained in EOP for loss of dc power.......................
T/G 1 11 RO 3.1 SRO 3.1 The CCWS surge tank, including level control and level alarms, and radiation alarm...............................................
T/G 1 11 RO 3.8 SRO 4.0 Facility*s 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.
Page 8 of 11 ES401, Rev 9 Question 49 1849 50 1850 51 1851 52 1852 53 1853 54 1854 2009 RO NRC f...
~ke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description KIA System Tier/Group Importance RO/SRO EPE055 EK3.02 Loss of Offsite and Onsite Power (Station Blackout)
T/G 1 11 RO 4.3 SRO 4.6 Knowledge of the reasons for the following responses as the apply to the Station Blackout: (CFR 41.5 /41.10 /
45.6/45.13)
APE056 AA2.37 Loss of Offsite Power Ability to determine and interpret the following as they apply to the Loss of Offsite Power: (CFR: 43.5/45.13)
Actions contained in EOP for loss of offsite and on site power T/G 111 RO 3.7*
SRO 3.8 ED/G indicators for the following: voltage, frequency, load, load-status, and closure of bus tie breakers......................
APE057 AA1.06 Loss of Vital AC Electrical Instrument Bus T/G 1 11 RO 3.5 SRO 35 Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: (CFR 41.7 /
45.5/45.6)
APE058 AK3.02 Loss of DC Power Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: (CFR 41.5,41.10/
45.6/45.1)
APE062 AA1.05 Loss of Nuclear Service Water Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water (SWS): (CFR 41.7/45.5/45.6)
WE04 EK2.2 LOCA Outside Containment Knowledge of the interrelations between the (LOCA Outside Containment) and the following:
(CFR: 41.7/45.7)
Manual control of components for which automatic control is lost.......
T/G 1 11 RO 4.0 SRO 4.2 Actions contained in EOP for loss of dc power.......................
T/G 1 I 1 RO 3.1 SRO 3.1 The CCWS surge tank, including level control and level alarms, and radiation alarm...............................................
T/G 1 11 RO 3.8 SRO 4.0 Facility*s 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.
Page 8 of 11
ES 401, Rev 9 Question 55 1855 56 1856 57 1857 58 1858 59 1859 60 1860 61 1861 2009 RO NRC f
-ike Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA Number KIA Description WEOS EK2.1 KIA System Loss of Secondary Heat Sink Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:
(CFR: 41.7 145.7)
Tier/Group Importance RO/SRO T/G 1/1 RO 3.7 SRO 3.9 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
WE11 2.4.8 Loss of Emergency Coolant Recirculation T/G 1 11 RO 3.8 SRO 4.S WE11 GENERIC APE003 AK1.07 Dropped Control Rod Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: (CFR 41.8/41.10/45.3)
APEOOS AK2.02 Inoperable/Stuck Control Rod Knowledge of the interrelations between the Inoperable 1 Stuck Control Rod and the following: (CFR 41.7 145.7)
APE024 AK1.04 Emergency Boration Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8/41.10/45.3)
Knowledge of how abnormal operating procedures are used in conjunction with EOPs. (CFR: 41.10/43.5/45.13)
T/G 1 12 RO 3.1 SRO 3.9 Effect of dropped rod on insertion limits and SDM T/G 1 12 RO 2.S SRO 2.6 Breakers, relays, disconnects, and control room switches T/G 1 12 RO 2.8 SRO 3.6 Low temperature limits for born concentration....................
APE061 AA2.04 Area Radiation Monitoring (ARM) System Alarms T/G 1 12 RO 3.1 SRO 3.S Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: (CFR: 43.5/45.13)
APE067 AK3.02 Plant Fire On Site Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: (CFR 41.5,41.101 45.6/45.13)
Whether an alarm channel is functioning properly.....................
T/G 1 12 RO 2.S SRO 3.3 Steps called out in the site fire protection plan, FPS manual, and fire zone manual.......................................
Page 9 of 11 ES 401, Rev 9 Question 55 1855 56 1856 57 1857 58 1858 59 1859 60 1860 61 1861 2009 RO NRC f ike Examination Combined PWR Written Examination Outline Form ES-401-2/3 KJA Number KJA Description WE05 EK2.1 KJA System Loss of Secondary Heat Sink Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:
(CFR: 41.7 /45.7)
Tier/Group Importance RO/SRO T/G 1 I 1 RO 3.7 SRO 3.9 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
WE11 2.4.8 Loss of Emergency Coolant Recirculation T/G 1 I 1 RO 3.8 SRO 4.5 WE11 GENERIC APE003 AK1.07 Dropped Control Rod Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: (CFR 41.8/41.10/45.3)
APE005 AK2.02 Inoperable/Stuck Control Rod Knowledge of the interrelations between the Inoperable /
Stuck Control Rod and the following: (CFR 41.7 / 45.7)
APE024 AK1.04 Emergency Boration Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: (CFR 41.8/41.10/45.3)
Knowledge of how abnormal operating procedures are used in conjunction with EOPs. (CFR: 41.10/43.5/45.13)
T/G 1 12 RO 3.1 SRO 3.9 Effect of dropped rod on insertion limits and SDM T/G 1 12 RO 2.5 SRO 2.6 Breakers, relays, disconnects, and control room switches T/G 1 12 RO 2.8 SRO 3.6 Low temperature limits for born concentration....................
APE061 AA2.04 Area Radiation Monitoring (ARM) System Alarms T/G 1 12 RO 3.1 SRO 3.5 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: (CFR: 43.5/45.13)
APE067 AK3.02 Plant Fire On Site Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: (CFR 41.5,41.10 /
45.6 /45.13)
Whether an alarm channel is functioning properly.....................
T/G 1 12 RO 2.5 SRO 3.3 Steps called out in the site fire protection plan, FPS manual, and fire zone manual.......................................
Page 9 of 11
ES 401, Rev 9 Question 62 1862 63 1863 64 1864 65 1865 66 1866 67 1867 68 1868 KIA Number KIA Description APE068 2.1.28 APE068 GENERIC WE03 EK3.2 2009 RO NRC h.
.ke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System Tier/Group Importance RO/SRO Control Room Evacuation T/G 1/2 RO 4.1 SRO 4.1 Knowledge of the purpose and function of major system components and controls. (CFR: 41.7)
LOCA Cooldown and Depressurization T/G 1 12 RO 3.4 SRO 3.S Knowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization)
(CFR: 41.5 /41.10, 45.6 /45.13)
Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).
WEOS EA1.1 Natural Circulation Operations T/G 1 12 RO 3.5 SRO 3.5 Ability to operate and / or monitor the following as they apply to the (Natural Circulation Operations)
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
(CFR: 41.7 / 45.5 /45.6)
WE13 2.2.37 WE13 GENERIC GEN2.1 2.1.28 Conduct of Operations GEN2.1 2.1.30 Conduct of Operations GEN2.1 2.1.31 Conduct of Operations Steam Generator Overpressure T/G 1 12 RO 3.6 SRO 4.6 Ability to determine operability and/or availability of safety related equipment.
(CFR: 41.7/43.5/45.12)
GENERIC - Conduct of Operations T/G 3 I 0 RO 4.1 SRO 4.1 Knowledge of the purpose and function of major system components and controls. (CFR: 41.7)
GENERIC - Conduct of Operations T/G 3 10 RO 4.4 SRO 4.0 Ability to locate and operate components, including local controls. (CFR: 41.7 /
45.7)
GENERIC - Conduct of Operations T/G 3/0 RO 4.6 SRO 4.3 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. (CFR: 41.10 /
45.12)
Page 10 of 11 ES 401, Rev 9 Question 62 1862 63 1863 64 1864 65 1865 66 1866 67 1867 68 1868 KJA Number KJA Description APE068 2.1.28 APE068 GENERIC WE03 EK3.2 2009 RO NRC ~.ke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KJA System Tier/Group Importance RO/SRO Control Room Evacuation T/G 1 12 RO 4.1 SRO 4.1 Knowledge of the purpose and function of major system components and controls. (CFR: 41.7)
LOCA Cool down and Depressurization T/G 1 12 RO 3.4 SRO 3.S Knowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization)
(CFR: 41.5/41.10,45.6/45.13)
Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).
WEOS EA1.1 Natural Circulation Operations T/G 1 12 RO 3.5 SRO 3.5 Ability to operate and / or monitor the following as they apply to the (Natural Circulation Operations)
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
(CFR: 41.7 /45.5/45.6)
WE13 2.2.37 WE13 GENERIC GEN2.1 2.1.28 Conduct of Operations GEN2.1 2.1.30 Conduct of Operations GEN2.1 2.1.31 Conduct of Operations Steam Generator Overpressure T/G 1 12 RO 3.6 SRO 4.6 Ability to determine operability and/or availability of safety related equipment.
(CFR: 41.7/43.5/45.12)
GENERIC - Conduct of Operations T/G 3 I 0 RO 4.1 SRO 4.1 Knowledge of the purpose and function of major system components and controls. (CFR: 41.7)
GENERIC - Conduct of Operations T/G 3 I 0 RO 4.4 SRO 4.0 Ability to locate and operate components, including local controls. (CFR: 41.7 /
45.7)
GENERIC - Conduct of Operations T/G 3 I 0 RO 4.6 SRO 4.3 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. (CFR: 41.10/
45.12)
Page 10 of 11
ES 401, Rev 9 Question 69 1869 70 1870 71 1871 72 1872 73 1873 74 1874 75 1875 KIA Number KIA Description GEN2.2 2.2.21 Equipment Control GEN2.2 2.2.35 Equipment Control GEN2.3 2.3.12 Radiation Control GEN2.3 2.3.14 Radiation Control GEN2.3 2.3.7 Radiation Control GEN2.4 2.4.16 2009 RO NRC f\\
Jke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System GENERIC - Equipment Control GENERIC - Equipment Control GENERIC - Radiation Control GENERIC - Radiation Control GENERIC - Radiation Control Tier/Group Importance RO/SRO T/G 3/0 RO 2.9 SRO 4.1 Knowledge of pre-and post-maintenance operability requirements. (CFR:
41.10 / 43.2)
T/G 3/0 RO 3.6 SRO 4.5 Ability to determine Technical Specification Mode of Operation. (CFR: 41.7/
41.10/43.2/45.13)
T/G 3/0 RO 3.2 SRO 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12/45.9/
45.10)
T/G 3/0 RO 3.4 SRO 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12/43.4 / 45.10)
T/G 3/0 RO 3.5 SRO 3.6 Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12/45.10)
GENERIC - Emergency Procedures I Plan T/G 3/0 RO 3.5 SRO 4.4 Emergency Procedures / Plan Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. (CFR:
41.10/43.5/45.13)
GEN2.4 2.4.46 GENERIC - Emergency Procedures I Plan T/G 3/0 RO 4.2 SRO 4.2 Emergency Procedures / Plan Ability to verify that the alarms are consistent with the plant conditions. (CFR:
41.10/43.5/45.3/45.12)
Page 11 of 11 ES 401, Rev 9 Question 69 1869 70 1870 71 1871 72 1872 73 1873 74 1874 75 1875 KIA Number KIA Description GEN2.2 2.2.21 Equipment Control GEN2.2 2.2.35 Equipment Control GEN2.3 2.3.12 Radiation Control GEN2.3 2.3.14 Radiation Control GEN2.3 2.3.7 Radiation Control GEN2.4 2.4.16 2009 RO NRC K
",ke Examination Combined PWR Written Examination Outline Form ES-401-2/3 KIA System GENERIC - Equipment Control GENERIC - Equipment Control GENERIC - Radiation Control GENERIC - Radiation Control GENERIC - Radiation Control Tier/Group Importance RO/SRO T/G 3/0 RO 2.9 SRO 4.1 Knowledge of pre-and post-maintenance operability requirements. (CFR:
41.10/43.2)
T/G 3/0 RO 3.6 SRO 4.5 Ability to determine Technical Specification Mode of Operation. (CFR: 41.71 41.10/43.2/45.13)
T/G 3/0 RO 3.2 SRO 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 145.91 45.10)
T/G 3/0 RO 3.4 SRO 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 143.4 1 45.10)
T/G 3/0 RO 3.5 SRO 3.6 Ability to comply with radiation work permit requirements during normal orabnormal conditions. (CFR: 41.12 145.10)
GENERIC - Emergency Procedures I Plan T/G 3/0 RO 3.5 SRO 4.4 Emergency Procedures 1 Plan Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. (CFR:
41.10/43.5/45.13)
GEN2.4 2.4.46 GENERIC - Emergency Procedures I Plan T/G 3/0 RO 4.2 SRO 4.2 Emergency Procedures 1 Plan Ability to verify that the alarms are consistent with the plant conditions. (CFR:
41.10/43.5 145.3/45.12)
Page 11 of 11