ML092881117
| ML092881117 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/15/2009 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-327/09-302, 50-328/09-302 | |
| Download: ML092881117 (14) | |
Text
DRAFT ES-401. Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Sequoyat..
Date of Exam: 2009 Retake Exam 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 2
2 1
1 9
2 2
4 Abnormal Plant N/A N/A Evolutions Tier Totals 4
5 5
5 4
4 27 5
5 10 1
2 2
4 3
2 2
2 3
2 3
3 28 3
2 5
- 2.
Plant 2
0 1
1 1
1 1
1 1
1 1
1 10 2
1 3
Systems Tier Totals 2
3 5
4 3
3 3
4 3
4 4
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
2 3
3 1
2 2
2
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than 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 fro.:n 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 relevanHo 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 10 CFR 55.43.
I DRAFT DRAFT ES-401 1 Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Sequoy~
Date of Exam: 2009 Retake Exam 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 2
2 1
1 9
2 2
4 Abnormal Plant N/A N/A Evolutions Tier Totals 4
5 5
5 4
4 27 5
5 10 1
2 2
4 3
2 2
2 3
2 3
3 28 3
2 5
- 2.
Plant 2
0 1
1 1
1 1
1 1
1 1
1 10 2
1 3
Systems Tier Totals 2
3 5
4 3
3 3
4 3
4 4
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
2 3
3 1
2 2
2
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than 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 outiine; 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 fro';' 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 10 CFR 55.43.
i DRAFT
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 KS A1 A2 A3 A4 G RO SRO 007EK2.03 Reactor Trip - Stabilization - Recovery 3~5 3.S 0 ~ 0 0 0 0 0 0 0 0 0 11 009EK1.02 Small Break LOCA I 3 3.5 4.2
~ 0 0 0 0 0 0 0 0 0 0 011EK2.02 Large Break LOCA I 3 2.6 2.7 0 ~ 0 0 0 0 0 0 0 0 0 015AK2.10 RCP Malfunctions I 4 2.8 2.8 0 ~ 0 0 0 0 0 0 0 0 0 022AG2.1.31 Loss of Rx Coolant Makeup I 2 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~
026AA2.02 Loss of Component Cooling Water I 8 2.9 3.6 0 0 0 0 0 0 0 ~ 0 0 0 029EG2.2.22 ATWS 11 4.0 4.7 0 0 0 0 0 0 0 0 0 0 ~
038EA1.13 Steam Gen. Tube Rupture 13 3.7 3.6 0 0 0 0 0 0 ~ 0 0 0 0 040AA 1.09 Steam Line Rupture - Excessive Heat 3.4 3.4 0 0 0 0 0 0 ~ 0 0 0 0 Transfer 14 054AK1.02 Loss of Main Feedwater 14 3.6 4.2
~ 0 0 0 0 0 0 0 0 0 0 FORM ES-401-2 TOPIC:
Reactor trip status panel Use of steam tables Pumps RCP indicators and controls Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
The cause of possible CCW loss Knowledge of limiting conditions for operations and safety limits.
Steam flow indicators Setpoints of main steam safety and PORVs Effects of feedwater introduction on dry S/G 055EK3.02 Station Blackout 16 4.3 4.6 0 0 ~ 0 0 0 0 0 0 0 0 Actions contained in EOP for loss of offsite and onsite power Page 1 of2 2111/2009 12:16 PM ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 007EK2.03 Reactor Trip - Stabilization - Recovery 3.S 3.6 0 ~ 0 0 0 0 0 0 0 0 0 11 009EK1.02 Small Break LOCA/3 3.S 4.2
~ 0 0 0 0 0 DOD 0 0 011EK2.02 Large Break LOCA 13 2.6 2.7 0 ~ 0 0 0 0 0 0 0 0 0 01SAK2.10 RCP Malfunctions I 4 2.8 2.8 0 ~ 0 D DOD D D D 0 022AG2.1.31 Loss of Rx Coolant Makeup I 2 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~
026AA2.02 Loss of Component Cooling Water 18 2.9 3.6 0 DOD DOD ~ 0 0 0 029EG2.2.22 ATWS 11 4.0 4.7 0 DOD 0 0 DOD D ~
038EA1.13 Steam Gen. Tube Rupture 13 3.7 3.6 D DODD 0 ~ 0 DOD 040AA1.09 Steam Line Rupture - Excessive Heat Transfer 14 3.4 3.4 DDDDDD~DDDD OS4AK1.02 Loss of Main Feedwater I 4 3.6 4.2
~DDDDDDDDDD OSSEK3.02 Station Blackout I 6 4.3 4.6 DD~DDDDDDDD Page 1 of 2 FORM ES-401-2 TOPIC:
Reactor trip status panel Use of steam tables Pumps RCP indicators and controls Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
The cause of possible CCW loss Knowledge of limiting conditions for operations and safety limits.
Steam flow indicators Setpoints of main steam safety and PORVs Effects of feedwater introduction on dry S/G Actions contained in EOP for loss of offsite and onsite power 2111/2009 12:16 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
056AA1.11 Loss of Off-site Power /6 057AK3.01 Loss of Vital AC Inst. Bus / 6 05SAK1.01 Loss of DC Power / 6 062AK3.01 Loss of Nuclear Svc Water /4 065AA2.05 Loss of Instrument Air /S 077AG2.2.39 Generator Voltage and Electric Grid Disturbances / 6 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G AO SAO 3.7 3.7 D D D D D D ~ D D D D 4.1 4.4 D D ~ D D D D D D D D 2.S 3.1
~ D D D D D D D D D D 3.2 3.5 D D ~ D D D D D D D D 3.4 4.1 D D D D D D D ~ D D D 3.9 4.5 D D D D D D D D D D ~
WE11 EA2.1 Loss of Emergency Coolant Aecirc. / 4 3.4 4.2 D D D D D D D ~ D D D Page 2 of 2 FORM ES-401-2 TOPIC:
HPI system Actions contained in EOP for loss of vital ac electrical instrument bus BatterY charger equipment and instrumentation The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers When to commence plant shutdown if instrument air pressure is decreasing Knowledge of less than one hour technical specification action statements tor systems.
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
2111/2009 12:16 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
056AA1.11 Loss of Oft-site Power / 6 057AK3.01 Loss of Vital AC Inst. Bus 1 6 058AK1.01 Loss of DC Power /6 062AK3.01 Loss of Nuclear Svc Water 14 065AA2.05 Loss of Instrument Air 1 8 077AG2.2.39 Generator Voltage and Electric Grid Disturbances / 6 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.7 3.7 D D D D D D ~ D D D D 4.1 4.4 D D ~ D D D D D D D D 2.8 3.1
~ D D D D D D D D D D 3.2 3.5 D D ~ D D D D D D D D 3.4 4.1 D D D D D D D ~ D D D 3.9 4.5 D D D D D D D D D D ~
WE11 EA2.1 Loss of Emergency Coolant Recirc. / 4 3.4 4.2 D D D D D D D ~ D D D Page 2 of 2 FORM ES-401-2 TOPIC:
HPI system Actions contained in EOP for loss of vital ac electrical instrument bus BatterY charger equipment and instrumentation The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers When to commence plant shutdown if instrument air pressure is decreasing Knowledge of less than one hour technical specification action statements for systems.
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
2111/2009 12:16 PM
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO 003AK3.06 Dropped Control Rod 11 2.7 3
D D ~ D D D DOD D 0 Reset of demand position counter to zero 032AK1.01 Loss of Source Range NI/7 2.S 3.1
~ D D D D D D D DOD Effects of voltage changes on performance 059AK2.02 Accidental Liquid RadWaste Rei. I 9 2.7 2.7 D ~ D D D D D D D D D Radioactive-gas monitors 068AG2.1.27 Control Room Evac. I 8 3.9 4
DDDDDDDDDD~
Knowledge of system purpose and or function.
076AA1.04 High Reactor Coolant Activity I 9 3.2 3.4 DDDDDD~DDDD Failed fuel-monitoring equipment WE03EK3.4 LOCA Cooldown - Depress. 1 4 3.5 3.9 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.
WE07EA2.1 Saturated Core Cooling Core Cooling 3.2 4.0 DDDDDDD~DDD Facility conditions and selection of appropriate 14 procedures during abnormal and emergency operations.
WE10EK2.1 Natural Circ. With Seam Void! 4 3.3 3.5 D~DDDDDDDDD Components and functions of control and safety systems, including instrumentation, Signals, interlocks, failure modes and automatic and manual features.
WE16EA1.3 High Containment Radiation 1 9 2.9 3.3 DDDDDD~DDDD Desired operating results during abnormal and emergency situations.
Page 1 of 1 2111/2009 12:16 PM ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 003AK3.06 Dropped Control Rod 1 1 2.7 3
0 0 ~ 0 0 0 0 0 0 0 0 032AK1.01 Loss of Source Range NI 1 7 2.5 3.1
~ 0 0 0 0 0 0 0 0 0 0 059AK2.02 Accidental Liquid RadWaste ReI. 1 9 2.7 2.7 0 ~ 0 0 0 0 0 0 0 0 0 068AG2.1.27 Control Room Evac. 18 3.9 4
DDDDDDDDDD~
076AA 1.04 High Reactor Coolant Activity 19 3.2 3.4 0 0 0 0 0 0 ~ 0 0 0 0 WE03EK3.4 LOCA Cooldown - Depress. 14 3.5 3.9 0 0 ~ 0 0 0 0 0 0 0 0 WE07EA2.1 Saturated Core Cooling Core Cooling 3.2 4.0 0 0 0 0 DOD ~ 0 0 0 14 WE10EK2.1 Natural Circ. With Seam Void! 4 3.3 3.5 0 ~ 0 0 0 0 0 0 0 0 0 WE16EA 1.3 High Containment Radiation 1 9 2.9 3.3 DOD 0 0 0 ~ 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:
Reset of demand position counter to zero Effects of voltage changes on performance Radioactive-gas monitors Knowledge of system purpose and or function.
Failed fuel-monitoring equipment 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.
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
Desired operating results during abnormal and emergency situations.
2I11/200912:16PM
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 003A3.03 Reactor Coolant Pump 3.2 3.1 0 0 0 0 0 0 0 0 ~ 0 0 0D4A1.12 Chemical and Volume Control 2.B 3.2 0 0 0 0 0 0 ~ 0 0 0 0 004A2.25 Chemical and Volume Control 3.B 4.3 0 0 0 0 0 0 0 ~ 0 0 0 005K1.13 Residual Heat Removal 3.3 3.5
~ 0 0 0 0 0 0 0 0 0 0 006K5.06 Emergency Core Cooling 3.5 3.9 0 0 0 0 ~ 0 0 0 0 0 0 007A2.01 Pressurizer Relief/Quench Tank 3.9 4.2 0 0 0 0 0 0 0 ~ 0 0 0 007A4.09 Pressurizer Relief/Quench Tank 2.5 2.7 0 0 0 0 0 DOD 0 ~ 0 OOBK3.01 Component Cooling Water 3.4 3.5 0 0 ~ 0 0 0 0 0 0 0 0 010G2.4.30 Pressurizer Pressure Control 2.7 4.1 0 0 DO 0 DOD 0 0 ~
012K6.09 Reactor Protection 3.6 3.7 0 0 0 0 0 ~ 0 0 0 0 0 013K5.02 Engineered Safety Features Actuation 2.9 3.3 0 0 0 0 ~ 0 0 0 0 0 0 Page 1 of3 FORM ES-401-2 TOPIC:
Seal DIP Rate of boron concentration reduction in RCS as a function of letdown flow while deborating demineralizer is in service Uncontrolled boration or dilution SIS Relationship between ECCS flow and RCS pressure Stuck-open PORV or code safety Relationships between PZR level and changing levels of the PRT and bleed holdup tank Loads cooled by CCWS Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
CEAC Safety system logic and reliability 2/11/2009 12:16 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 003A3.03 Reactor Coolant Pump 3.2 3.1 D D D D D D D D ~ D D Seal DIP 004A 1.12 Chemical and Volume Control 2.8 3.2 DDDDDD~DDDD Rate of boron concentration reduction in RCS as a function of letdown flow while deborating demineralizer is in service 004A2.25 Chemical and Volume Control 3.8 4.3 DDDDDDD~DDD Uncontrolled boration or dilution
~-
005K1.13 Residual Heat Removal 3.3 3.5 li'lDDDDDDDDDD SIS 006K5.06 Emergency Core Cooling 3.5 3.9 DDDD~DDDDDD Relationship between ECCS flow and RCS pressure 007A2.01 Pressurizer Relief/Quench Tank 3.9 4.2 DDDDDDD~DDD Stuck-open PORV or code safety 007A4.09 Pressurizer Relief/Quench Tank 2.5 2.7 DDDDDDDDD~D Relationships between PZR level and changing levels of the PRT and bleed holdup tank 008K3.01 Component Cooling Water 3.4 3.5 DD~DDDDDDDD Loads cooled by CCWS 010G2.4.30 Pressurizer Pressure Control 2.7 4.1 DDDDDDDDDD~
Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
012K6.09 Reactor Protection 3.6 3.7 DDDDD~DDDDD CEAC 013K5.02 Engineered Safety Features Actuation 2.9 3.3 DDDD~DDDDDD Safety system logic and reliability Page 1 of 3 2111/2009 12:16 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
022K3.02 Containment Cooling 025A4.02 Ice Condenser 025G2.2.42 Ice Condenser 026K2.01 Containment Spray 026K3.01 Containment Spray 039A1.03 Main and Reheat Steam 059K4.02 Main Feedwater 061A3.03 Auxiliary/Emergency Feedwater 061K6.02 Auxiliary/Emergency Feedwater 062K2.01 AC Electrical Distribution 063A4.02 DC Electrical Distribution T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 3.0 3.3 D D ~ D D D D D D D D 2.7 2.5 D D D D D D D D D ~ D 3.9 4.6 D D D D D D D D D D ~
3.4 3.6 D ~ D D D D D D D D D 3.9 4.1 D D ~ D D D D D D D D 2.6 2.7 D D D D D D ~ D D D D 3.3 3.5 D D D ~ D D D D D D D 3.9 3.9 D D D D D D D D ~ D D 2.6 2.7 D D D D D ~ D D D D D 3.3 3.4 D ~ D D D D D D D D D 2.8 2.9 D D D D D D D D D ~ D Page 2 of3 FORM ES-401-2 TOPIC:
Containment instrumentation readings Containment vent fans Ability to recognize system parameters that are entry-level conditions for Technical Specifications Containment spray pumps CCS Primary system temperature indications and required values, during main steam system warm-up Automatic turbine/reactor trip runback AFW S/G level control on automatic start Pumps Major system loads Battery voltage indicator 2111/2009 12:16 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 022K3.02 Containment Cooling 3.0 3.3 DD~DDDDDDDD Containment instrumentation readings 025A4.02 Ice Condenser 2.7 2.5 DDDDDDDDD~D Containment vent fans 025G2.2.42 Ice Condenser 3.9 4.6 DDDDDDDDDD~
Ability to recognize system parameters that are entry-level conditions for Technical Specifications 026K2.01 Containment Spray 3.4 3.6 D~DDDDDDDDD Containment spray pumps 026K3.01 Containment Spray 3.9 4.1 DD~DDDDDDDD CCS 039A1.03 Main and Reheat Steam 2.6 2.7 DDDDDD~DDDD Primary system temperature indications and required values, during main steam system warm-up 059K4.02 Main Feedwater 3.3 3.5 DDD~DDDDDDD Automatic turbine/reactor trip run back 061A3.03 Auxiliary/Emergency Feedwater 3.9 3.9 DDDDDDDD~DD AFW S/G level control on automatic start 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 DDDDD~DDDDD Pumps 062K2.01 AC Electrical Distribution 3.3 3.4 D~DDDDDDDDD Major system loads 063A4.02 DC Electrical Distribution 2.8 2.9 DDDDDDDDD~D Battery voltage indicator Page 2 of 3 2111/2009 12:16 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
064K4.03 Emergency Diesel Generator 073A2.0l Process Radiation Monitoring 076K3.02 Service Water 076K4.Q3 Service Water T2G1 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.5 3.0 0 0 0 ~ 0 0 0 0 0 0 0 2.5 2.9 0 0 0 0 0 0 0 ~ 0 0 0 2.5 2.8 0 0 ~ 0 0 0 0 0 0 0 0 2.9 3.4 0 0 0 ~ 0 0 0 0 0 0 0 FORM ES-401-2 TOPIC:
Governor valve operation Erratic or failed power supply Secondary closed cooling water Automatic opening features associated with SWS isolation valves to CCW heat exchanges 078G2.2.38 Instrument Air 103Kl.03 Containment 3.6 4.5 0 DOD 0 0 0 0 0 0 ~
Knowledge of conditions and limitations in the facility license.
3.1 3.5
~ 0 0 0 0 0 0 0 0 0 0 Shield building vent system Page 3 of 3 2111/2009 12:16 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
064K4.03 Emergency Diesel Generator 073A2.01 Process Radiation Monitoring 076K3.02 Service Water 076K4.03 Service Water T2G1 PWR EXAMINATION OUTLINE fR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 3.0 0 0 0 ~ 0 0 0 0 0 0 0 2.5 2.9 0 0 0 0 0 0 0 ~ 0 0 0 2.5 2.8 0 0 ~ 0 0 0 0 0 0 0 0 2.9 3.4 0 0 0 ~ 0 0 0 0 0 0 0 FORM ES-401-2 TOPIC:
Govemor valve operation Erratic or failed power supply Secondary closed cooling water Automatic opening features associated with SWS isolation valves to CCW heat exchanges
~~---------- -
~.----
~~~~~~~~~~~~~~~~~~~-- -----------------------
078G2.2.38 Instrument Air 3.6 4.5
[J 0 0 0 0 0 0 0 0 0 ~
Knowledge of conditions and limitations in the facility license.
103K1.03 Containment 3.1 3.5
~ 0 0 0 0 0 0 0 0 0 0 Shield building vent system Page 3 of 3 2111/2009 12:16 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 011A1.03 Pressurizer Level Control 2.8 3.2 DDDDDD~DDDD VCT level 015K2.01 Nuclear Instrumentation 3.3 3.7 D~DDDDDDDDD NIS channels, components and interconnections 028K3.01 Hydrogen Recombiner and Purge 3.3 Control 4.0 DD~DDDDDDDD Hydrogen concentration in containment 029G2.1.31 Containment Purge 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.
033K4.01 Spent Fuel Pool Cooling 2.9 3.2 DDD~DDDDDDD Maintenance of spent fuel level 034K6.02 Fuel Handling Equipment 2.6 3.3 DDDDD~DDDDD Radiation monitoring systems 041K5.05 Steam DumpiTurbine Bypass Control 2.6 3.2 DDDD~DDDDDD Basis for RCS design pressure limits 071A2.02 Waste Gas Disposal 3.3 3.6 DDDDDDD~DDD Use of waste gas release monitors, radiation, gas flow rate and totalizer 079A4.01 Station Air 2.7 2.7 DDDDDDDDD~D Cross-tie valves with lAS 086A3.03 Fire Protection 2.9 3.3 DDDDDDDD~DD Actuation of fire detectors Page 1 of 1 2I11/200912:16PM ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 011A1.03 Pressurizer Level Control 2.8 3.2 DDDDDD~DDDD VCT level 015K2.01 Nuclear Instrumentation 3.3 3.7 D~DDDDDDDDD NIS channels, components and interconnections 028K3.01 Hydrogen Recombiner and Purge 3.3 4.0 DD~DDDDDDDD Hydrogen concentration in containment Control 029G2.1.31 Containment Purge 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.
033K4.01 Spent Fuel Pool Cooling 2.9 3.2 DDD~DDDDDDD Maintenance of spent fuel level 034K6.02 Fuel Handling Equipment 2.6 3.3 DDDDD~DDDDD Radiation monitoring systems 041K5.05 Steam DumpfTurbine Bypass Control 2.6 3.2 DDDD~DDDDDD Basis for RCS design pressure limits 071A2.02 Waste Gas Disposal 3.3 3.6 DDDDDDD~DDD Use of waste gas release monitors, radiation, gas flow rate and totalizer 079A4.01 Station Air 2.7 2.7 DDDDDDDDD~D Cross-tie valves with lAS 086A3.03 Fire Protection 2.9 3.3 DDDDDDDD~DD Actuation of fire detectors Page 1 of 1 2111/2009 12:16 PM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO G2.1.41 Conduct of operations 2.8 3.7 DDDDDDDDDD~
Knowledge of the refueling processes G2.1.42 Conduct of operations 2.5 3.4 DDDDDDDDDD~
Knowledge of new and spent fuel movement procedures G2.2.23 Equipment Control 3.1 4.6 DDDDDDDDDD~
Ability to track Technical Specification limiting conditions for operations.
G2.2.44 Equipment Control 4.2 4.4 DDDDDDDDDD~
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 G2.3.11 Radiation Control 3.8 4.3 DDDDDDDDDD~
Ability to control radiation releases.
G2.3.5 Radiation Control 2.9 2.9 DDDDDDDDDD~
Ability to use radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 DDDDDDDDDD~
Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.11 Emergency Procedures/Plans 4.0 4.2 DDDDDDDDDD~
Knowledge of abnormal condition procedures.
G2.4.16 Emergency Procedures/Plans 3.5 4.4 DDDDDDDDDD~
Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
G2.4.37 Emergency Procedures/Plans 3.0 4.1 DDDDDDDDDD~
Knowledge of the lines of authority during implamentation of an emergency plan.
Page 1 of 1 2111/2009 12:16 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.41 Conduct of operations G2.1.42 Conduct of operations G2.2.23 Equipment Control G2.2.44 Equipment Control G2.3.11 Radiation Control G2.3.5 Radiation Control G2.3.7 Radiation Control G2.4.11 Emergency Procedures/Plans G2.4.16 Emergency Procedures/Plans G2.4.37 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 3.7 0 0 0 0 0 0 0 0 0 0 ~
2.5 3.4 0 0 0 0 0 0 DOD 0 ~
3.1 4.6 0 0 0 0 0 0 0 0 0 0 ~
4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~
3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~
2.9 2.9 DOD 0 0 0 0 0 0 0 ~
3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~
4.0 4.2 0 0 0 DOD 0 D D 0 ~
3.5 4.4 0 0 0 0 0 0 0 0 0 0 ~
3.0 4.1 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of the refueling processes Knowledge of new and spent fuel movement procedures Ability to track Technical Specification limiting conditions for operations.
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.
Ability to use radiation monitoring systems Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of abnormal condition procedures.
Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
Knowledge of the lines of authority during implamentation of an emergency plan.
2I11/200912:16PM
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 009EA2.11 Small Break LOCA I 3 3.8 4.1 0 0 0 0 0 0 0 ~ 0 0 0 015AA2.11 RCP Malfunctions / 4 3.4 3.8 0 0 0 0 0 0 0 ~ 0 0 0 038EG2.4.20 Steam Gen. Tube Rupture 1 3 3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~
040AA2.02 Steam Line Rupture - Excessive Heat 4.6 4.7 0 0 0 0 0 0 0 ~ 0 0 0 Transfer 14 057AG2.2.44 Loss Inst. Bus 16 4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~
062AG2.1.7 Loss of Nuclear Svc Water I 4 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Containment temperature, pressure, and humidity When to jog RCPs during ICC Knowledge of operational implications of EOP warnings, cautions and notes.
Conditions requiring a reactor trip 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 evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
2111/200912:16PM 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 009EA2.11 Small Break LOCA 1 3 3.8 4.1 D D D D D D D ~ D D D 015AA2.11 RCP Malfunctions / 4 3.4 3.8 D D D D D D D ~ D D D 038EG2.4.20 Steam Gen. Tube Rupture 1 3 3.8 4.3 D D D D D D DOD D ~
040AA2.02 Steam Line Rupture - Excessive Heat 4.6 4.7 D D D D D D D ~ D D D Transfer /4 057 AG2.2.44 Loss of Vital AC Ins!. Bus / 6 4.2 4.4 D D D D D D D D D D ~
062AG2.1.7 Loss of Nuclear Svc Water /4 4.4 4.7 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Containment temperature, pressure, and humidity When to jog RCPs during ICC Knowledge of operational implications of EOP warnings, cautions and notes.
Conditions requiring a reactor trip 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 evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
2111/200912:16PM
ES-401, REV 9 SRO 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 060AA2.05 Accidental Gaseous Radwaste ReI. /9 3.7 4.2 0 0 0 0 0 0 0 ~ 0 0 0 That the automatic safety actions have occurred as a result of a high ARM system signal 061AG2.4.46 ARM System Alarms /7 WE13EA2.1 Steam Generator Over-pressure / 4 we15EG2.4.30 Containment Flooding /5
.------------------,-~---:-:---,------:----------
4.2 4.2 0 DOD D D D D D D ~
Ability to verify that the alarms are consistent with the plant conditions.
2.9 3.4 D D DOD D D ~ 0 D 0 2.7 4.1 D D D D D D D D D D ~
Page 1 of 1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
2111/2009 12:16 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 060AA2.05 Accidental Gaseous Radwaste ReI. / 9 3.7 4.2 D D D D D D D ~ D D D FORM ES-401-2 TOPIC:
That the automatic safety actions have occurred as a result of a high ARM system signal
~------------------------------------
061AG2.4.46 ARM System Alarms / 7 4.2 4.2 D D D D D D D D D D ~
WE13EA2.1 Steam Generator Over-pressure / 4 2.9 3.4 D D D D D D D ~ D D D we15EG2A.30 Containment Flooding / 5 2.7 4.1 D D D D D D D D D D ~
Page 1 of 1 Ability to verify that the alarms are consistent with the plant conditions.
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
2111/2009 12:16 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
004G2.2.44 Chemical and Volume Control 00SA2.04 Residual Heat Removal 012A2.0S Reactor Protection OS9A2.06 Main Feedwater 064G2.4.8 Emergency Diesel Generator SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~
2.9 2.9 0 0 0 0 0 0 0 ~ 0 0 0 3.1 3.2 0 0 0 0 0 0 0 ~ DOD 2.7 2.9 0 0 0 0 0 0 0 ~ 0 0 0 3.8 4.S 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
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 RHR valve malfunction Faulty or erratic operation of detectors and function generators Loss of steam flow to MFW system Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
2111/2009 12:16 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
004G2.2.44 Chemical and Volume Control 00SA2.04 Residual Heat Removal 012A2.0S Reactor Protection OS9A2.06 Main Feedwater 064G2.4.8 Emergency Diesel Generator SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A 1 A2 A3 A4 G RO SRO 4.2 4.4 D D D D D D D D D D ~
2.9 2.9 D D D D D D D ~ D D D 3.1 3.2 D D D D D D D ~ 0 D D 2.7 2.9 D D D D D [J D ~ D D D 3.8 4.S D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
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 RHR valve malfunction Faulty or erratic operation of detectors and function generators Loss of steam flow to MFW system Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
2I11/200912:16PM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
028G2.1.23 Hydrogen Recombiner and Purge Control 068A2.04 Liquid Radwaste 071A2.03 Waste Gas Disposal SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~
3.3 3.3 0 0 0 0 0 0 0 ~ 0 0 0 2.7 3.3 0 0 0 0 0 0 0 ~ DOD Page 1 of 1 FORM ES-401-2 TOPIC:
Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Failure of automatic isolation Rupture disk failures 2111/2009 12:16 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
028G2.1.23 Hydrogen Recombiner and Purge Control 068A2.04 Liquid Radwaste 071A2.03 Waste Gas Disposal SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~
3.3 3.3 0 0 0 0 0 0 0 ~ 0 0 0 2.7 3.3 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:
Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Failure of automatic isolation Rupture disk failures 2111/2009 12:16 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.9 Conduct of operations G2.2.12 Equipment Control G2.2.17 Equipment Control G2.3.11 Radiation Control G2.3.14 Radiation Control G2.4.16 Emergency Procedures/Plans G2.4.38 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G RO SRO 2.9 4.5 0 0 0 0 0 0 0 0 0 0 ~
3.7 4.1 0 0 0 0 0 0 0 0 0 0 ~
2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~
3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~
3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~
3.5 4.4 0 0 0 0 0 0 0 0 0 0 ~
2.4 4.4 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Ability to direct personnel activities inside the control room.
Knowledge of surveillance procedures.
Knowledge of the process for managing maintenance activities during power operations.
Ability to control radiation releases Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.
2I11/200912:16PM ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.9 Conduct of operations G2.2.12 Equipment Control G2.2.17 Equipm ent Control SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 4.5 0 0 0 0 0 0 0 0 0 0 Ii'J 3.7 4.1 0 0 0 0 0 0 0 0 0 0 Ii'J 2.6 3.8 0 0 0 0 0 0 0 0 0 0 Ii'J FORM ES-401-2 TOPIC:
Ability to direct personnel activities inside the control room.
Knowledge of surveillance procedures.
Knowledge of the process for managing maintenance activities during power operations.
G2.3.11 G2.3.14 G2.4.16 G2.4.38 Radiation Control Radiation Control Emergency Procedures/Plans 3.8 4.3 0 0 0 0 0 0 0 0 0 0 Ii'J Ability to control radiation releases 3.4 3.8 0 0 0 0 0 0 0 0 0 0 Ii'J 3.5 4.4 0 0 0 0 0 0 0 0 0 0 Ii'J Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.
. -~--~~------~~~~~-=~=-~~-=~=-~~-=~=---~~~~--~--~~~~~~~--------
Emergency Procedures/Plans 2.4 4.4 0 0 0 0 0 0 0 0 0 0 Ii'J Ability to take actions called for in the facility emergency Page 1 of 1 plan, including supporting or acting as emergency coordinator.
2111/2009 12:16 PM