ML093280266
| ML093280266 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/18/2009 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-424/09-301, 50-425/09-301, ES-401-2 50-424/09-301, 50-425/09-301 | |
| Download: ML093280266 (14) | |
Text
ES-401. Rev. 9 PWR Examination Outline Form ES-401-2
/JILfLt-'l I Facility: VOGTLE Date of Exam: 2009 I
RO KIA 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 3
3 6
Emergency &
2 1
2 1
2 2
1 9
2 2
4 Abnormal Plant N/A N/A Evolutions Tier Totals 4
5 4
5 5
4 27 5
5 10 1
2 2
2 2
3 3
3 3
2 3
3 28 3
2 5
- 2.
1 1
1 0
1 1
Plant 2
1 1
1 1
1 10 2
1 3
Systems Tier Totals 3
3 3
2 4
4 4
4 3
4 4
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 3
2 2
3 1
2 2
2
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (Le., except for one category in Tier 3 ofthe SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/- 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 ES-401, Attachment 2, for guidance regarding the 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 KIAs 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) KIAs in Tiers 1 and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be relevant to the applicable evolution or system.
- 8.
On the following pages, enter the KIA 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; iffuel 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. LimitSRO selections to KIAs that are linked to 10 CFR 55.43.
ES-401 Rev. 9 PWR Examination Outline Form ES-401-2 jJILllr1 Facility: VOGTLE Date of Exam: 2009 RO KIA 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 3
3 6
Emergency &
2 1
2 1
2 2
1 9
2 2
4 Abnormal Plant N/A N/A Evolutions Tier Totals 4
5 4
5 5
4 27 5
5 10 1
2 2
2 2
3 3
3 3
2 3
3 28 3
2 5
- 2.
1 1
1 0
1 1
Plant 2
1 1
1 1
1 10 2
1 3
Systems Tier Totals 3
3 3
2 4
4 4
4 3
4 4
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 3
2 2
3 1
2 2
2
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (Le., except for one category in Tier 3 ofthe SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-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 ES-401, Attachment 2, for guidance regarding the 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 KIAs 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) KIAs 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.
- 8.
On the following pages, enter the KIA 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; iffuel 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 KIAs that are linked to 1 0 CFR 55.43.
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EA2.06 Reactor Trip - Stabilization - Recovery 4.3 4.5 0 0 0 0 0 0 0
~ 0 0 0 1 1 008AK2.02 Pressurizer Vapor Space Ar.r.irlpnt 3 2.7 2.7 0 ~ 0 0000000 009EG2.4.34 Small Break LOCA I 3 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~
011 EG2.2.37 Large Break 3
3.6 4.6 000 0000 O~
015AG2.4.6 RCP Malfunctions 1 4 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~
022AA1.02 Loss of Rx 3
2.9 ooo~oooo 025AK1.01 Loss of RHR System 14 3.9 4.3
~ 0 0 0 0 0 0 0 0 0 0 027AK3.02 Pressurizer Pressure Control System 2.9 3
oo~oooooo o Malfunction 1 3 029EK2.06 ATWS 11 2.9 3.1 0 ~ 0 0 0 0 0 0 0 0 0 055EK1.01 Station Blackout 1 6 3.3 3.7
~ 0 0 0 0 0 0 0 0 0 0 056AA2.39 Loss of Off-site Power 1 6 3.5 3.6 0 0 0 0 0 0 0 ~ 0 0*0 Page 1 of 2 FORM ES-401-2 TOPIC:
Occurrence of a reactor trip Sensors detectors Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Ability to determine operability and/or availability of safety related equipment Knowledge symptom based EOP mitigation strategies.
CVCS charging low flow alarm, sensor and indicator Loss of RHRS during all modes of operation Verification of alternate transmitter and/or plant computer prior to shifting flow chart transmitters Breakers, relays, and disconnects.
Effect of battery discharge rates on capacity Safety injection pump ammeter and flowmeter 1/28/2009 2:23 PM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 007EA2.06 Reactor Trip - Stabilization - Recovery 4.3 4.5 D D D D D D D ~ D D D 11 008AK2.02 Pressurizer Vapor Space Accident 13 2.7 2.7 D ~ D D D D D D D D D 009EG2.4.34 Small Break LOCA 1 3 4.2 4.1 D D D D D D D D D D ~
011 EG2.2.37 Large Break LOCA 13 3.6 4.6 D D' D D D D D D D D ~
015AG2.4.6 RCP Malfunctions 1 4 3.7 4.7 D D D D D D D D D D ~
022AA1.02 Loss of Rx Coolant Makeup 1 2 3
2.9 DDDDDD~DDDD 025AK1.01 Loss of RHR System 14 3.9 4.3
~ D D D D D D D D D D 027AK3.02 Pressurizer Pressure Control System 2.9 3
D D ~ D D D D D D D D Malfunction 1 3 029EK2.06 ATWS 11 2.9 3.1 D ~ D D D D D D D D D 055EK1.01 Station Blackout 1 6 3.3 3.7
~ D D D D D D D D D D 056AA2.39 Loss of Off-site Power 1 6 3.5 3.6 D D D D D D D ~ D D' D Page 1 of 2 FORM ES-401-2 TOPIC:
Occurrence of a reactor trip Sensors and detectors Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Ability to determine operability and/or availability of safety related equipment Knowledge symptom based EOP mitigation strategies.
CVCS charging low flow alarm, sensor and indicator Loss of RHRS during all modes of operation Verification of alternate transmitter and/or plant computer prior to shifting flow chart transmitters Breakers, relays, and disconnects.
Effect of battery discharge rates on capacity Safety injection pump ammeter and flowmeter 1/28/2009 2:23 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
057AA1.04 Loss of Vital AC Inst. Bus 1 6 058AA2.01 Loss of DC Power 1 6 062AK3.03 Loss of Nuclear Svc Water 1 4 065AA1.03 Loss of Instrument Air 1 8 077AK2.04 Generator Voltage and Electric Grid Disturbances 1 6 WE04EK3.4 LOCA Outside Containment 1 3 WE05EK1.3 Inadequate Heat Transfer - Loss of Secondary Heat Sink 1 4 T1 G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.5 3.6 D D D D D D ~ D D D D 3.7 4.1 D D D D D D D ~ D D D 4
4.2 DD~DDDDDDDD 2.9 3.1 DDDDDD~DDDD 3.0 3.0 D~DDDDDDDDD 3.6 3.8 DD~DDDDDDDD 3.9 4.1
~DDDDDDDDDD Page 2 of 2 FORM ES-401-2 TOPIC:
RWST and VCT valves That a loss of dc power has occurred; verification that sUbstitute power sources have come on line Guidance actions contained in EOP for Loss of nuclear service water Restoration of systems served by instrument air when pressure is regained Controllers, positioners RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink).
1/28/2009 2:23 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
057AA1.04 Loss of Vital AC Ins!. Bus 1 6 058AA2.01 Loss of DC Power 1 6 062AK3.03 Loss of Nuclear Svc Water 14 065AA1.03 Loss of Instrument Air 1 8 077AK2.04 Generator Voltage and Electric Grid Disturbances 1 6 WE04EK3.4 LOCA Outside Containment 1 3 WE05EK1.3 Inadequate Heat Transfer - Loss of Secondary Heat Sink 14 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.5 3.6 D D D D D D ~ D D D D 3.7 4.1 D D D D D D D ~ D D D 4
4.2 DD~DDDDDDDD 2.9 3.1 DDDDDD~DDDD 3.0 3.0 D~DDDDDDDDD 3.6 3.8 DD~DDDDDDDD 3.9 4.1
~DDDDDDDDDD Page 2 of 2 FORM ES-401-2 TOPIC:
RWST and VCT valves That a loss of dc power has occurred; verification that substitute power sources have come on line Guidance actions contained in EOP for Loss of nuclear service water Restoration of systems served by instrument air when pressure is regained Controllers, positioners RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink).
1/28/2009 2:23 PM
ES-401, REV 9 T1 G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 003AK2.05 Dropped Control Rod 1 1 2.5 2.8 D ~ D D D D D D D D Control rod drive power supplies and logic circuits 032AA2.09 Loss of Source Range NI 1 7 2.5 2.9 DDDDDDD~Dnn Effect of improper HV setting 051AA1.04 Loss of Condenser Vacuum 14 2.5 2.5 DDDDDD~DDDD Rod position 068AG2,4.6 Control Room Evac. 1 8 3.7 4.7 DDDDDDDDDD~
Knowledge symptom based EOP mitigation strategies.
076AA2.03 High Reactor Coolant Activity 1 9 2.5 3
DDDDDDD~DDD RCS radioactivity level meter WE03EA1.3 LOCA Cooldown - Depress. 1 4 3.7 4.1 DDDDDD~DDDD Desired operating results during abnormal and emergency situations.
WE06EK3,4 Degraded Core Cooling 14 3.5 3.7 DD~DDDDDDDD RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
WE08EK2.1 RCS Overcooling - PTS 1 4 3,4 3.7 D~DDDDDDDDD Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WE09EK1.2 Natural Circ. 1 4 3.3 3.7
~DDDDDDDDDD Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).
Page 1 of 1 1/28/2009 2:23 PM ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 003AK2.05 Dropped Control Rod 1 1 2.5 2.8 D ~ D D D D D D D D D Control rod drive power supplies and logic circuits 032AA2.09 Loss of Source Range NI 1 7 2.5 2.9 DDDDDDD~DDD Effect of improper HV setting 051AA1.04 Loss of Condenser Vacuum 14 2.5 2.5 DDDDDD~DDDD Rod position 068AG2.4.6 Control Room Evac. 1 8 3.7 4.7 DDDDDDDDDD~
Knowledge symptom based EOP mitigation strategies.
076AA2.03 High Reactor Coolant Activity 1 9 2.5 3
DDDDDDD~DDD RCS radioactivity level meter WE03EA1.3 LOCA Cooldown - Depress. 14 3.7 4.1 DDDDDD~DDDD Desired operating results during abnormal and emergency situations.
WE06EK3.4 Degraded Core Cooling 1 4 3.5 3.7 DD~DDDDDDDD RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
WE08EK2.1 RCS Overcooling - PTS 1 4 3.4 3.7 D~DDDDDDDDD Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WE09EK1.2 Natural Circ. 1 4 3.3 3.7
~DDDDDDDDDD Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).
Page 1 of 1 1/28/2009 2:23 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
003K6.14 Reactor Coolant Pump 004K5.11 Chemical and Volume Control 004K5.15 Chemical and Volume Control 005K2.03 Residual Heat Removal 006A4.11 Emergency Core Cooling 007K1.01 Pressurizer Tank 008A4.02 Component Cooling Water 008K3.03 Component Cooling Water 010K2.04 Pressurizer Pressure Control 010K6.01 Pressurizer Pressure Control 012K3.04 Reactor Protection T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.6 2.9 0 0 0 0 0 ~ 0 0 0 0 0 oooo~oooooo 3.3 3.5 000 0 0000 2.7 2.8 0 ~ 0 0000 00 4.2 4.3 0 0 0 0 0 ooo~o 2.9 3.1
~ 0 0 0 0 0 0 0 0 0
2.5 2.5 0 0 0 0 0 0 0 0 0 ~ 0 4.1 4.2 0 0 ~ 0 0 0 0 0 0 0 0 2.7 2.9 0 ~ 0 0 0 0 0 0 0 0 0 2.7 3.1 0 0 0 0 0 ~ 0 0 0 0 0 3.8 4.1 0 0 ~ 0 0 0 0 0 0 0 0 Page 1 of 3 FORM ES-401-2 TOPIC:
Starting requirements stress, brittle fracture, pressurized thermal shock and control rod reactivity effects as they relate to MTC RCS pressure boundary motor-operated valves Overpressure protection system Containment system Filling and draining operations of the CCWS including the proper venting of the components RCP Indicator for code safety position Pressure detection systems 1/28/2009 2:23 PM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 003K6.14 Reactor Coolant Pump 2.6 2.9 DDDDD~DDDDD Starting requirements 004K5.11 Chemical and Volume Control 3.6 3.9 DDDD~DDDDDD Thermal stress, brittle fracture, pressurized thermal shock 004K5.15 Chemical and Volume Control 3.3 3.5 DDDD~DDDDDD Boron and control rod reactivity effects as they relate to MTC 005K2.03 Residual Heat Removal 2.7 2.B D~DDDDDDDDD RCS pressure boundary motor-operated valves 006A4.11 Emergency Core Cooling 4.2 4.3 DDDDDDDDD~D Overpressure protection system 007K1.01 Pressurizer Relief/Quench Tank 2.9 3.1
~DDDDDDDDDD Containment system 00BA4.02 Component Cooling Water 2.5 2.5 DDDDDDDDD~D Filling and draining operations of the CCWS including the proper venting of the components 00BK3.03 Component Cooling Water 4.1 4.2 DD~DDDDDDDD RCP 010K2.04 Pressurizer Pressure Control 2.7 2.9 D~DDDDDDDDD Indicator for code safety position 010K6.01 Pressurizer Pressure Control 2.7 3.1 DDDDD~DDDDD Pressure detection systems 012K3.04 Reactor Protection 3.B 4.1 DD~DDDDDDDD ESFAS Page 1 of 3 1/2B/2009 2:23 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 013K1.07 Engineered Safety Features Actuation 4.1 4.4
~DDDDDDDDDD AFW System 022A1.02 Containment Cooling 3.6 3.8 DDDDDD~DDDD Containment pressure 026K4.01 Containment Spray 4.2 4.3 DDD~DDDDDDD Source of water for CSS, including recirculation phase after LOCA 039G2.2.25 Main and Reheat Steam 3.2 4.2 DDDDDDDDDD~
Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
059A3.04 Main Feedwater 2.5 2.6 DDDDDDDD~DD Turbine driven feed pump 061A1.01 Auxiliary/Em ergency Feedwater 3.9 4.2 DDDDDD~DDDD S/G level 061G2.1.7 Auxiliary/Emergency Feedwater 4.4 4.7 DDDDDDDDDD~
Ability to'evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
062K4.02 AC Electrical Distribution 2.5 2.7 DDD~DDDDDDD Circuit breaker automatic trips 063A2.01 DC Electrical Distribution 2.5 3.2 DDDDDDD~DDD Grounds 064K6.08 Emergency Diesel Generator 3.2 3.3 DDDDD~DDDDD Fuel oil storage tanks 073K5.01 Process Radiation Monitoring 2.5 3.0 DDDD~DDDDDD Radiation theory, including sources, types, units and effects Page 2 of 3 1/28/2009 2:23 PM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 013K1.07 Engineered Safety Features Actuation 4.1 4.4
~ 0 0 0 0 0 0 0 0 0 0 022A1.02 Containment Cooling 3.6 3.8 DDDDDD~DDDD 026K4.01 Containment Spray 4.2 4.3 DDD~DDDDDDD 039G2.2.25 Main and Reheat Steam 3.2 4.2 DDDDDDDDDD~
059A3.04 Main Feedwater 2.5 2.6 DDDDDDDD~DD 061A1.01 Auxiliary/Emergency Feedwater 3.9 4.2 DDDDDD~DDDD 061G2.1.7 Auxiliary/Emergency Feedwater 4.4 4.7 DDDDDDDDDD~
062K4.02 AC Electrical Distribution 2.5 2.7 DDD~DDDDDDD 063A2.01 DC Electrical Distribution 2.5 3.2 0 0 0 0 0 0 0 ~ 0 0 0 064K6.08 Emergency Diesel Generator 3.2 3.3 0 0 0 0 0 ~ 0 0 0 0 0 073K5.01 Process Radiation Monitoring 2.5 3.0 0 0 0 0 ~ 0 0 0 0 0 0 Page 2 of 3 FORM ES-401-2 TOPIC:
AFW System Containment pressure Source of water for CSS, including recirculation phase after LOCA Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Turbine driven feed pump S/G level Ability to'evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
Circuit breaker automatic trips Grounds Fuel oil storage tanks Radiation theory, including sources, types, units and effects 1/28/2009 2:23 PM
ES-401, REV 9 T2Gl PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:
RO SRO 076A2.01 Service Water 3.S 3.7 DDDDDDD~DDD Loss ofSWS 076A2.02 Service Water 2.7 3.1 DDDDDDD~DDD Service water header pressure 078A3.01 Instrument Air 3.1 3.2 DDDDDDDD~DD Air pressure 078G2.4.31 Instrument Air 4.2 4.1 DDDDDDDDDD~
Knowledge of annunciators alarms, indications or response procedures 103A1.01 Containment 3.7 4.1 DDDDDD~DDDD Containment pressure, temperature and humidity 103A4.03 Containment 2.7 2.7 DDDDDDDDD~D ESF slave relays Page 3 of 3 1/28/2009 2:23 PM ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 076A2.01 Service Water 3.5 3.7 D D D D D D D ~ D D D 076A2.02 Service Water 2.7. 3.1 D D D D D D D ~ D D D 078A3.01 Instrument Air 3.1 3.2 D D D D D D D D ~ D D 078G2.4.31 Instrument Air 4.2 4.1 D D D D D D D D D D ~
1 03A 1.01 Containment 3.7 4.1 D D D D D D ~ D D D D 1 03A4.03 Containm ent 2.7 2.7 D D D D D D D D D ~ D Page 3 of 3 FORM ES-401-2 TOPIC:
Loss of SWS Service water header pressure Air pressure Knowledge of annunciators alarms, indications or response procedures Containment pressure, temperature and humidity ESF slave relays 1/28/2009 2:23 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
001 A4.12 Control Rod Drive 002G2.1.31 Reactor Coolant 01SK2.01 Nuclear Instrumentation 028KS.04 Hydrogen Recombiner and Purge Control 029K1.0S Containment Purge 033A 1.01 Spent Fuel Pool Cooling 03SK6.01 Steam Generator OSSK3.01 Condenser Air Removal 071A2.08 Waste Gas Disposal 086A3.01 Fire Protection T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 2.9 2.9 0 0 0 0 0 0 0 0 0 ~ 0 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~
3.3 3.7 0 ~
2.6 3.2 0 0 0 0 ~ 0 0 0 0 0 0 2.9 3.1
~ 0 0 0 0 0 0 0 0 0 0 2.7 3.3 0 0 0 0 0 0 ~ 0 0 0 0 3.2 3.6 0 0 0 0 0 ~ 0 0 0 0 0 2.S 2.7 0
~oooo 000 2.S 2.8 0 ooooo~o o 2.9 3.3 ooooooo~oo Page 1 of 1 FORM ES-401-2 TOPIC:
Stopping TIG load changes; only make minor adjustments to prevent coil burnout Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
channels, components and interconnections The selective removal of hydrogen Containment air cleanup and recirculation system Spent fuel pool water level MSIVs Main condenser Meteorological changes Starting mechanisms of fire water pumps 1/28/2009 2:23 PM ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 001A4.12 Control Rod Drive 2.9 2.9 DDDDDDDDD~D Stopping T/G load changes; only make minor adjustments to prevent coil burnout 002G2.1.31 Reactor Coolant 4.6 4.3 DDDDDDDDDD~
Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
015K2.01 Nuclear Instrumentation 3.3 3.7 D~DDDDDDDDD NIS channels, components and interconnections 028K5.04 Hydrogen Recombiner and Purge 2.6 3.2 DDDD~DDDDDD The selective removal of hydrogen Control 029K1.05 Containment Purge 2.9 3.1
~DDDDDDDDDD Containment air cleanup and recirculation system 033A1.01 Spent Fuel Pool Cooling 2.7 3.3 DDDDDD~DDDD Spent fuel pool water level 035K6.01 Steam Generator 3.2 3.6 DDDDD~DDDDD MSIVs 055K3.01 Condenser Air Removal 2.5 2.7 DD~DDDDDDDD Main condenser 071A2.08 Waste Gas Disposal 2.5 2.8 DDDDDDD~DDD Meteorological changes 086A3.01 Fire Protection 2.9 3.3 DDDDDDDD~DD Starting mechanisms of fire water pumps Page 1 of 1 1/28/2009 2:23 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.29 Conduct of operations G2.1.30 Conduct of operations G2.1.8 Conduct of operations G2.2.13 Equipment Control G2.2.44 Equipment Control G2.3.11 Radiation Control G2.3.14 Radiation Control G2.4.13 Emergency Procedures/Plans G2.4.34 Emergency Procedures/Plans G2.4.41 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.0 D D D D D D D D D D ~
4.4 4.0 D D D D D D D D D D ~
3.4 4.1 D D D D D D D D D D ~
4.1 4.3 D D D D D D D D D D ~
4.2 4.4 D D D D D D D D D D ~
3.8 4.3 D D D D D D D D D D ~
3.4 3.8 D D D D D D D D D D ~
4.0 4.6 D D D D D D D D D D ~
4.2 4.1 D D D D D D D DOD ~
2.9 4.6 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
Ability to locate and operate components, including local controls.
Ability to coordinate personnel activities outside the control room.
Knowledge of tagging and clearance procedures.
Ability to interpret control room indications to verify the
. status and operation of a system, and understand how operator actions and directives affect plant and system conditions Ability to control radiation releases.
Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of crew roles and responsibilities during EOP usage.
Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Knowledge of the emergency action level thresholds and classifications.
1/28/2009 2:23 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.29 Conduct of operations G2.1.30 Conduct of operations G2.1.8 Conduct of operations G2.2.13 Equipment Control G2.2.44 Equipment Control G2.3.11 Radiation Control G2.3.14 Radiation Control G2.4.13 Emergency Procedures/Plans G2.4.34 Emergency Procedures/Plans G2.4.41 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.0 D D D D D D D D D D ~
4.4 4.0 D D D D D D D D D D ~
3.4 4.1 D D D D D D D D D D ~
4.1 4.3 D D D D D D D D D D ~
4.2 4.4 D D D D D D D D D D ~
3.8 4.3 DDDDDDDDDD~
3.4 3.8 DDDDDDDDDD~
4.0 4.6 DDDDDDDDDD~
4.2 4.1 DDDDDDDDDD~
2.9 4.6 DDDDDDDDDD~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
Ability to locate and operate components, including local controls.
Ability to coordinate personnel activities outside the control room.
Knowledge of tagging and clearance procedures.
Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Ability to control radiation releases.
Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of crew roles and responsibilities during EOP usage.
Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Knowledge of the emergency action level thresholds and classifications.
1/28/2009 2:23 PM
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 022AA2.02 Loss of Rx Coolant Makeup 1 2 3.2 3.7 D D D D D D D ~ D D D 027 AG2.1.32 Pressurizer Pressure Control System Malfunction 1 3 3.8 4.0 DDDDDDDDDD~
029EG2.2.22 ATWS/1 4.0 4.7 DDDDDDDDDD~
058AA2.03 Loss of DC Power 1 6 3.5 3.9 DDDDDDD~DDD 062AA2.02 Loss of Nuclear Svc Water 1 4 2.9 3.6 DDDDDDD~DDD we11 EG2.4.2 Loss of Emergency Coolant Recirc. 14 4.5 4.6 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Charging pump problems Ability to explain and apply all system limits and precautions.
Knowledge of limiting conditions for operations and safety limits.
DC loads lost; impact on ability to operate and monitor plant systems The cause of possible SWS loss Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
1/28/2009 2:23 PM ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 022AA2.02 Loss of Rx Coolant Makeup 1 2 3.2 3.7 D D D D D D D ~ D D D 027AG2.1.32 Pressurizer Pressure Control System 3.8 4.0 DDDDDDDDDD~
Malfunction 1 3 029EG2.2.22 ATWS/1 4.0 4.7 DDDDDDDDDD~
058AA2.03 Loss of DC Power 1 6 3.5 3.9 DDDDDDD~DDD 062AA2.02 Loss of Nuclear Svc Water 14 2.9 3.6 DDDDDDD~DDD we11 EG2.4.2 Loss of Emergency Coolant Recirc. 1 4 4.5 4.6 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Charging pump problems Ability to explain and apply ali system limits and precautions.
Knowledge of limiting conditions for operations and safety limits.
DC loads lost; impact on ability to operate and monitor plant systems The cause of possible SWS loss Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
1/28/2009 2:23 PM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 003AG2.4.35 Dropped Control Rod 1 1 3.8 4.0 D D D D D D D D D D ~
028AA2.08 Pressurizer Level Malfunction 1 2 3.1 3.5 D D D D D D D ~ D D D 069AG2.4.8 Loss of CTMT Integrity 1 5 3.8 4.5 D D D D D D D D D D ~
WE03EA2.2 LOCA Cooldown - Depress. 1 4 3.5 4.1 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects PZR level as a function of power level Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Adherence to appropriate procedures and operation within the limitations in the facility's license and.
amendments.
1/28/2009 2:23 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
003AG2.4.35 Dropped Control Rod 1 1 028AA2.08 Pressurizer Level Malfunction 1 2 069AG2.4.8 Loss of CTMT Integrity 1 5 WE03EA2.2 LOCA Cooldown - Depress. 1 4 SRO T1 G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.8 4.0 D D D D D D D D D D ~
3.1 3.5 D D D D D D D ~ D D D 3.8 4.5 D D D D D D D D D D ~
3.5 4.1 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects PZR level as a function of power level Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
1/28/2009 2:23 PM
ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:
RO SRO 008A2.07 Component Cooling Water 2.S 2.8 DDDDDDD~DDD Consequences of high or low CCW flow rate and tempera-ture; the flow rate at which the CCW standby pump will start 012G2.4.20 Reactor Protection 3.8 4.3 DDDDDDDDDD~
Knowledge of operational implications of EOP warnings, cautions and notes.
013A2.04 Engineered Safety Features Actuation 3.6 4.2 DDDDDDD~DDD Loss of instrument bus OS9G2.4.3 Main Feedwater 3.7 3.9 D D D D D D D D D D ~
Ability to identify post-accident instrumentation.
061A2.02 Auxiliary/Emergency Feedwater 3.2 3.6 D D D D D D D ~ D D D Loss of air to steam supply valve Page 1 of 1 1/28/2009 2:23 PM ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 008A2.07 Component Cooling Water 2.5 2.8 DDDDDDD~DDD Consequences of high or low CCW flow rate and tempera-ture; the flow rate at which the CCW standby pump will start 012G2.4.20 Reactor Protection 3.8 4.3 DDDDDDDDDD~
Knowledge of operational implications of EOP warnings, cautions and notes.
013A2.04 Engineered Safety Features Actuation 3.6 4.2 DDDDDDD~DDD Loss of instrument bus 059G2.4.3 Main Feedwater 3.7 3.9 D D D D D D D D D D ~
Ability to identify post-accident instrumentation.
~~------------------
061 A2.02 Auxiliary/Emergency Feedwater 3.2 3.6 D D D D D D D ~ D D D Loss of air to steam supply valve Page 1 of 1 1/28/2009 2:23 PM
ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 055G2.4.11 Condenser Air Removal 4.0 4.2 0 0 0 0 0 0 0 0 0 0 ~
Knowledge of abnormal condition procedures.
068A2.02 Liquid Radwaste 2.7 2.8 DOD 0 0 0 0 ~ DOD Lack of tank recirculation prior to release 071A2.03 Waste Gas Disposal 2.7 3.3 0 0 0 0 0 0 0 ~ 0 0 0 Rupture disk failures Page 1 of 1 1/28/2009 2:23 PM ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 055G2.4.11 Condenser Air Rem oval 4.0 4.2 D D D D D D D D D D ~
Knowledge of abnormal condition procedures.
068A2.02 Liquid Radwaste 2.7 2.8 D D D D D D D ~ D D D Lack of tank recirculation prior to release 071A2.03 Waste Gas Disposal 2.7 3.3 D D D D D D D ~ D D D Rupture disk failures Page 1 of 1 1/28/2009 2:23 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.15 Conduct of operations G2.2.22 Equipment Control G2.2.38 Equipment Control G2.3.4 Radiation Control G2.3.5 Radiation Control G2.4.20 Emergency Procedures/Plans G2.4.47 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.7 3.4 D D D D D D D D D D ~
4.0 4.7 D D D D D D D D D D ~
3.6 4.5 D D D D D D D D D D ~
3.2 3.7 D D D D D D D D D D ~
2.9 2.9 D D D D D D [] D D D ~
4.3 DDDDDDDDDD~
4.2 4.2 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
Knowledge of limiting conditions for operations and safety limits.
Knowledge of conditions and limitations in the facility license.
Knowledge of radiation exposure limits under normal and emergency conditions Ability to use radiation monitoring systems Knowledge of operational implications of EOP warnings, cautions and notes.
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
1/28/2009 2:23 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.15 Conduct of operations G2.2.22 Equipment Control G2.2.38 Equipment Control G2.3.4 Radiation Control G2.3.5 Radiation Control G2.4.20 Emergency Procedures/Plans G2.4.47 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.7 3.4 0 0 0 0 0 0 0 0 0 0 ~
4.0 4.7 0 0 0 0 0 0 0 0 0 0 ~
3.6 4.5 0 0 0 0 0 0 0 0 0 0 ~
3.2 3.7 DOD 0 0 0 0 0 0 0 ~
2.9 2.9 0 0 0 0 DOD 0 0 0 ~
3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~
4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
Knowledge of limiting conditions for operations and safety limits.
Knowledge of conditions and limitations in the facility license.
Knowledge of radiation exposure limits under normal and emergency conditions Ability to use radiation monitoring systems Knowledge of operational implications of EOP warnings, cautions and notes.
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
1/28/2009 2:23 PM