ML050470028
| ML050470028 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/01/2005 |
| From: | Desilets M Entergy Nuclear Vermont Yankee |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| ES-401, ES-401-1 | |
| Download: ML050470028 (16) | |
Text
ES-401 BWR Examination Outline. Rev 1.
Form ES-401-1
~~
Facility: Vermont Yankee Date of Exam: January 31,2005 I
I RO WA Category Points 11 SRO-Only Points 4
3 7
1 2
3 5
5 10
- 3. Generic Knowledge and 1
2 3
4 10 EE 3
2 2
3 2
2 Abilities Categories Vote:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
7.*
- 8.
- 9.
Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA category shall not be less than two).
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 *l 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.
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,, for guidance regarding the elimination of inappropriate WA statements.
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.
Absent a plant-specific priority, only those WAS 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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WS categories.
The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.
On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
For Tier 3, select topics form Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43 X = selected for RO section S = selected for SRO section Rev 1 : Changed numbering so the last 25 questions will be SRO only, corrected tier 2 K&A counts, re-sampled 2 K&As (see Rev 1 of K&A rejection sheet), changed 29501 3 to an RO question and 295035 to SRO question.
BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier llGroup 1 (RO I SRO)
Form ES-401-1 ES-401 KIA Topic(s)
EIAPE # I Name / Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 Knowledge of the interrelations between Partial or Complete Loss of Forced Core Flow Circulation and the following:
(CFR: 41.7 145.8)
AK2.04 Reactorlturbine pressure regulating system: Plant-Specific 3.30 3.30 3.30 2.4.50 and operate controls identified in the alarm response manual (CFR 45.3) 3.30 Ability to verify system alarm setpoints 3.30 3.30 2
3 Ability to operate and I or monitor the following as they apply to Partial or Complete Loss of AC (CFR: 41.7 145.6)
AA1.01 A.C. electrical distribution system 3.70 3.80 3.70 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC Power I 6 Knowledge of the reasons for the following responses as they apply to Partial or Total Loss of DC Power:
(CFR: 41.5 / 45.6)
AK3.01 Load shedding: Plant-Specific 2.60 3.10 2.60 4
~~
Knowledge of the interrelations between Main Turbine Generator Trip and the following:
(CFR: 41.7 145.8)
AK2.08 A.C. electrical distribution 3.20 3.30 3.20 5
295005 Main Turbine Generator Trip I 3 295006 SCRAM I 1
Knowledge of the reasons for the following responses as they apply to SCRAM):
(CFR: 41.5 145.6)
AK3.01 Reactor water level response 3.80 3.90 3.80 6
~~
Ability to operate and / or monitor the following as they apply to Control Room Abandonment:
(CFR: 41.7 145.6)
AA1.05 D.C. electrical distribution 2.80 2.90 Knowledge of the operational applications of the following concepts as they apply to the Partial or Total Loss of CCW:
(CFR: 41.8 to 41.10)
AKl.01 Effects on componentkystem operations 3.50 3.60 2.80 3.50 7
29501 6 Control Room Abandonment 17 8
29501 8 Partial or Total Loss of CCW 1 8 3.50 Ability to determine and interpret the following as they apply to Partial or Total Loss of CCW:
(CFR: 41.10143.5145.13)
AA2.03 Cause for partial or complete loss 3.20 3.50
11 ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 11Group 1 (RO I SRO)
Form ES-401-1 WA Topic(s)
G I X
2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls (CFR 41.10, 43.2, 45.6) 4.00 4.00 4.00 9
3.80 77 S
2.1.32 Ability to explain and apply system limits and precautions (CFR 41.lo, 43.2,45.12) 3.40 3.80 Knowledge of the interrelations between Loss of Shutdown Cooling and the following:
(CFR: 41.7 145.8)
AK2.02 Reactor water cleanup 3.20 3.30 3.20 10 3.30 78 Ability to determine and interpret the following as they apply to Loss of Shutdown Cooling:
(CFR: 41.10 143.5 145.13)
AA2.06 Reactor pressure 3.20 3.30 Ability to determine and interpret the following as they apply to Refueling Acc Cooling Mode:
(CFR: 41.10 143.5 145.13)
AA2.04 Occurrence of fuel handling accident 3.40 4.10 3.40 11
~~
Knowledge of the reasons for the following responses as they apply to High Drywell Pressure:
(CFR: 41.5 I 45.6)
EK3.08 Containment spray: Plant-specific 3.70 4.10 3.70 12 3.80 13 Knowledge of the interrelations between High Reactor Pressure and the following:
(CFR: 41.7 I45.8)
EK2.06 HPCI: Plant-specific 3.80 3.80 Ability to determine and interpret the following as they apply to High Reactor Pressure:
(CFR: 41.10143.5145.13)
EA2.01 Reactor pressure 4.30 4.30 4.30 79 Knowledge of the operational applications of the following concepts as they apply to the Suppression Pool High Water Temp:
(CFR: 41.8 to 41.1 0)
EK1.01 Pump NPSH 3.00 3.40 3.00 2.80 14 inoperable alarms (CFR 41.lo, 43.5, 45.13) 295027 High Containment Temperature 15
I1 ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 11Group 1 (RO I SRO)
Form ES-401-1 WA Topic@)
G I E/APE # I Name I Safety Function Knowledge of the reasons for the following responses as they apply to High Drywell Temperature:
(CFR: 41.5 145.6)
EK3.03 Drywell spray operation: Mark-l&ll 3.60 3.90 3.60 15 Knowledge of the operational applications of the following concepts as they apply to the Low Suppression Pool Water Level:
(CFR: 41.8 to 41.10)
EK1.03 Heat capacity 3.80 4.10 3.80 16 2.70 -
3.30 17 -
81 295031 Reactor Low Water Level 12 which require the notification of plant personnel Knowledge of the interrelations between SCRAM Condition Present and Power Above APRM Downscale or Unknown and the following:
(CFR: 41.7 / 45.8)
EK2.04 SBLC system 4.40 4.50 4.40 18 19 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 295038 High Off-site Release Rate I 9 ll 3.40 X
2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material (CFR 41.10, 43.5, 45.12) 3.40 3.70 2.80 3.50 Knowledge of the reasons for the following responses as they apply to Plant Fire On Site:
(CFR: 41.5 / 45.6)
AK3.04 Actions contained in the abnormal procedure for plant fire on site 2.80 3.40 Ability to determine and interpret the following as they apply to Plant Fire On Site:
(CFR: 41.10143.5145.13)
AA2.12 zone 3.10 3.50 Location of vital equipment within fire 11 KIA Category Totals:
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier l/Group 2 (RO / SRO)
WA Topic@)
IR E/APE # / Name / Safety Function 295002 Loss of Main Condenser Vac / 3 Knowledge of the interrelations between Loss of Main Condenser Vac and the following:
(CFR: 41.7 / 45.8)
AK2.11 Seal steam: Plant-Specific 2.60 2.70 2.60 11 295008 High Reactor Water Level / 2 11 295009 Low Reactor Water Level I 2 Knowledge of the reasons for the following responses as they apply to High Drywell Pressure:
(CFR: 41.5 / 45.6)
AK3.02 Increased drywell cooling 3.40 3.40 3.40 22 295010 High Drywell Pressure / 5 29501 1 High Containment Temp / 5 3.60 83 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies (CFR 43.5, 45.1 1) 2.20 3.60 Suppressed, no Mark 111 containment at VY Ability to operate and / or monitor the following as they apply to High Drywell Temperature:
(CFR: 41.7 / 45.6)
AA1.01 Drywell ventilation system 3.50 3.60 3.50 23 Knowledge of the reasons for the following responses as they apply to High Suppression Pool Temp:
(CFR: 41.5 / 45.6)
AK3.01 Suppression pool cooling operation 3.60 3.80 3.60 24 Ability to determine and interpret the following as they apply to High Suppression Pool Temp:
(CFR: 41.10/43.5/45.13)
AA2.02 Localized heatingktratification 3.20 3.50 3.20 25 11 295014 Inadvertent Reactivity Addition / 1 2.1.06 Ability to supervise and assume a management role during plant transients and upset conditions (CFR 43.5, 45.12, 45.13) 2.10 4.30 4.30 84 11 295015 Incomplete SCRAM / 1 11 295017 High Off-site Release Rate / 9 11 295020 Inadvertent Cont. Isolation I5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl I 5
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier l/Group 2 (RO / SRO)
G 11 E/APE # / Name / Safety Function WA Topic@)
IR Knowledge of the reasons for the following responses as they apply to High Secondary Containment Area Temperature:
(CFR: 41.5 / 45.6)
EK3.01 Emergency/normal depressurization 3.50 3.50 3.80 295032 High Secondary Containment Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 11 500000 High CTMT Hydrogen Conc. / 5 v
WA Category Point Totals Knowledge of the operational applications of the following concepts as they apply to the Secondary Containment Ventilation High Radiation:
(CFR: 41.8 to 41.10)
EK1.02 Radiation releases 4.10 4.40 4.10 Ability to determine and interpret the following as they apply to Secondary Containment High Sump/Area Water Level:
(CFR: 41.10/43.5/45.13)
EA2.02 Water level in the affected area 3.10 3.10 3.10 Group Point Total:
27 85
ES-401 WA Topic(s)
BWR Examination Outline Form ES-401-1 IR Plant Systems -Tier ZGroup 1 (RO / SRO)
Knowledge of the physical connections and/or cause-effect relationships between SLC and the following:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.07 Jet pump differential pressure indication: Plant-Specific 2.60 2.60 2.60 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormaVemergency operations (CFR 43.5, 45.12) 3.00 4.00 2.4.07 Knowledge of event based EOP mitigation strategies (CFR 41.lo, 43.5, 45.13) 3.10 3.80 RPS Ability to manually operate and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.12 Close/open SCRAM instrument volume vent and/or drain valves 3.90 3.90 3.00 3.80 3.90 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm (CFR 43.5, 45.3, 45.12) 3.30 3.60 3.30 Ability to (a) predict the impacts of the following on the HPCl and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.15 BWR-2, 3, 4 3.40 3.50 Loss of control oil pressure:
3.40 2.4.06 Knowledge symptom based EOP mitigation strategies.
(CFR: 41.10/43.5/45.13) 3.1 4.0 Suppressed, system does not exist at VY 4.0 LPCS Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.02 Valve power 2.50 2.70 2.50 Suppressed, system does not exist at VY 29 30 86 31 32 87 33
BWR Examination Outline Form ES-401-1 Plant Systems -Tier UGroup 1 (RO / SRO)
ES-401 System # / Name 215003 IRM WA Topic(s)
Knowledge of the physical connections and/or cause-effect relationships between IRM and the following:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.02 Reactor manual control 3.60 3.60 3.60 34 Knowledge of the physical connections and/or cause-effect relationships between Source Range Monitor and the following:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.06 Reactor vessel 2.80 2.80 2.80 35 21 5004 Source Range Monitor
~~~
21 5005 APRM / LPRM 3.50 3.40 2.60 36
~
88 37 Knowledge of the effect that a loss or malfunction of the APRM / LPRM will have on the following:
(CFR: 41.7 / 45.4)
K3.06 IRM: Plant-Specific 3.50 3.60 Ability to (a) predict the impacts of the following on the APRM / LPRM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.06 Recirculation flow channels upscale 3.40 3.50 Knowledge of the operational implications of the following concepts as they apply to the RCIC:
(CFR: 41.5 / 45.3)
K5.01 Indications of pump cavitation 2.60 2.60 217000 RCIC 3.70 3.40 38 39 Ability to monitor automatic operations of the (SYSTEM) including:
(CFR: 41.7 / 45.7)
A3.03 System pressure 3.70 3.60 Ability to (a) predict the impacts of the following on the ADS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.03 valves: Plant-Specific Loss of air supply to ADS 3.40 3.60 21 8000 ADS Knowledge of the operational implications of the following concepts as they apply to the ADS:
(CFR: 41.5 / 45.3)
K5.01 ADS logic operation 3.80 3.80 3.80
BWR Examination Outline Form ES-401-1 Plant Systems -Tier UGroup 1 (RO / SRO)
ES-401 System # / Name WA Topic(s) 223002 PCIS/Nuclear Steam Supply Shutoff 2.70 3.00 41 42 Ability to (a) predict the impacts of the following on the PCIWNuclear Steam Supply Shutoff and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 I45.6)
A2.07 Various process instrumentation failures 2.70 2.90 Knowledge of the effect that a loss or malfunction of the following will have on the PCIS/Nuclear Steam Supply Shutoff:
(CFR: 41.7 / 45.7)
K6.02 D.C. electrical distribution 3.00 3.20 239002 SRVs Ability to (a) predict the impacts of the following on the SRVs and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.01 Stuck open vacuum breakers 3.00 3.30 3.30 89 SRVs Ability to manually operate and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.06 Reactor water level 3.90 4.10 3.90 43 259002 Reactor Water Level Control Ability to (a) predict the impacts of the following on the Reactor Water Level Control and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.01 steam flow inputs 3.30 3.40 Loss of any number of main 3.30 3.00 44 261 000 SGTS Ability to monitor automatic operations of the SGTS including:
(CFR: 41.7 / 45.7)
A3.03 Valve operation 3.00 2.90 45 Knowledge of the physical connections and/or cause-effect relationships between AC Electrical Distribution and the following:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.04 Uninterruptible power supply 3.10 3.40 3.10 262001 AC Electrical 3istribution
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier UGroup 1 (RO / SRO)
IR -
2.50 WA Topic(s)
System # / Name 262002 UPS (AC/DC)
Ability to predict and/or monitor changes in parameters associated with operating the UPS (ACIDC) controls including:
(CFR: 41.5 145.5)
Al.02 Motor generator outputs 2.50 2.90 Knowledge of the physical connections and/or cause-effect relationships between UPS (ACIDC) and the following:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.06 Unit computer: Plant-Specific 2.60 2.70 2.60 48 263000 DC Electrical Distribution DC Electrical Distribution Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.01 Major D.C. loads 3.10 3.40 3.10 49 Knowledge of the operational implications of the following concepts as they apply to the DC Electrical Distribution:
(CFR: 41.5 / 45.3)
K5.01 Hydrogen generation during battery charging 2.60 2.90 2.60 50 Ability to (a) predict the impacts of the following on the EDGs and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.10 LOCA 3.90 4.20 4.20 90 264000 EDGs 3.40 3.10 51 Knowledge of the operational implications of the following concepts as they apply to the EDGs:
(CFR: 41.5 / 45.3)
K5.06 Load sequencing 3.40 3.50 Knowledge of the physical connections and/or cause-effect relationships between Instrument Air and the following:
(CFR: 41.2 to 41.9 I 45.7 to 45.8)
K1.05 Main Steam Isolation valve air 3.10 3.20 52 300000 Instrument Air 400000 Component Cooling Water 2.90 Knowledge of the effect that a loss or malfunction of the Component Cooling Water will have on the following:
(CFR: 41.7 / 45.4)
K3.01 Loads cooled by CCWS 2.90 3.30 Group Point Total:
.</A Category Point Totals
ES-401 201001 CRD Hydraulic 201 002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RClS 201006 RWM 202001 Recirculation 11 202002 Recirculation Flow Control 215002 RBM BWR Examination Outline Plant Systems -Tier 2/Group 2 (RO / SRO)
Form ES-401-1 I IR WA Topic(s)
Ability to (a) predict the impacts of the following on the RMCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.03 Select block 2.90 2.80 2.80 Ability to (a) predict the impacts of the following on the Control Rod and Drive Mechanism and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.05 Reactor Scram 4.10 4.10 4.10 Suppressed, system does not exist at Suppressed, system does not exist at Recirculation Ability to manually operate and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.12 Core flow 3.90 3.80 3.80 Ability to monitor automatic operations of the RWCU including:
(CFR: 41.7 / 45.7)
A3.01 System pressure downstream of the pressure regulating valve: LP-RWCU 3.30 3.30 3.30 Ability to (a) predict the impacts of the following on the Traversing In-core Probe and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
(CFR: 41.5 / 45.6)
A2.07 Failure to retract during accident conditions: Mark-l&ll (Not-BWR1) 3.40 3.70 3.70 91 54
BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO / SRO)
Form ES-401-1 ES-401 System # / Name WA Topic@)
Knowledge of the operational implications of the following concepts as they apply to the Nuclear Boiler Inst.:
(CFR: 41.5 / 45.3)
K5.13 Reference leg flashing:
Design-Specific 3.50
. 3.60 3.50 57 3.80 3.60 3.50 58 59 93 Knowledge of RHWLPCI: Torus/Pool Cooling Mode design feature(s) and or interlock(s) which provide for the following:
(CFR: 41.7)
K4.03 Unintentional reduction in vessel injection flow during accident conditions: Plant-Specific 3.80 3.80 AI. Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES controls including:
(CFR: 41.5 / 45.5)
A.102 Drywell Pressure 3.60 3.70 2.2.17 Knowledge of the process for managing maintenance activities during power operations (CFR 43.5, 45.13) 2.30 3.50 219000 RHWLPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.
11 226001 RHWLPCI: CTMT Spray ll Mode 230000 RHWLPCI: Torus/Pool II Spray Mode Ability to monitor automatic operations of the Fuel Pool CoolinglCleanup including:
(CFR: 41.7 / 45.7)
A3.02 Pump trip(s) 2.60 2.60 2.60 2.90 60 233000 Fuel Pool CoolinglCleanup Knowledge of the effect that a loss or malfunction of the Fuel Handling Equipment will have on the following:
(CFR: 41.7 / 45.4)
K3.01 Reactor manual control system: Plant-Specific 2.90 3.30 61 234000 Fuel Handling Equipment Knowledge of the effect that a loss or malfunction of the following will have on the Main and Reheat Steam:
(CFR: 41.7 / 45.7)
K6.04 Relief valve operability:
Plant-Specific 3.40 3.50 3.40 62 239001 Main and Reheat Steam 1
L 239003 MSlV Leakage Control Suppressed, system does not exist at VY 241 000 Reactorflurbine Pressure Regulator
ES-401 System # / Name 245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate 259001 Reactor Feedwater 11 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 11 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel lnternals WA Category Point Totals BWR Examination Outline Plant Systems -Tier 2/Group 2 (RO I SRO)
Form ES-401-1 WA Topic(s)
IR Knowledge of the effect that a loss or malfunction of the Main Turbine Gen.
/ Aux. will have on the following:
(CFR: 41.7 / 45.4)
K3.07 Reactor protection system 3.60 3.70 3.60 Knowledge of Fire Protection design feature(s) and or interlock@) which provide for the following:
(CFR: 41.7)
K4.06 Fire suppression capability that does not rely on the displacement of oxygen (Halon):
Plant-SDecific 3.40 3.40 3.40 Knowledge of Reactor Vessel 3.30 lnternals design feature(s) and or interlock(s) which provide for the following:
(CFR: 41.7)
K4.05 Natural circulation 3.30 3.50 Group Point Total:
63 64 65 1 2/3 -
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Date of Exam Facility:
Category 1
66 Topic F
IR 3.8 KIA #
2.1.
2.1.8 Ability to coordinate personnel activities outside the control room (CFR 45.5, 45.12, 45.13) 2.1.1 9 Ability to use plant computer to obtain and evaluate parametric information on system or component status (CFR 45.12)
Ability to explain and apply system limits and precautions (CFR 41.1 0, 43.2, 45.1 2)
Knowledge of facility requirements for controlling vital / controlled access (CFR 41.10, 43.5, 45.9,45.10) 3.0 3.4 67 68
- 1.
Conduct of Operations 2.1.32 2.1.13 2.1.4 95 Knowledge of shift staffing requirements (CFR 41.1 0, 43.2)
Subtotal 2.2.13 Knowledge of tagging and clearance procedures (CFR 41.1 0, 45.1 3) 69 3.6 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation (CFR 45.12 3.5 70
- 2.
Equipment Control 2.2.
2.2.
3.2 2.2.7 Knowledge of the process for conducting tests for experiments not described in the safety analysis report (CFR 43.3, 45.1 3) 2.2.20 Knowledge of the process for managing troubleshooting activities (CFR 43.5, 45.1 3) 97 Subtotal
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 WA #
2.3.1 1
2.3.1 Facility
Topic Ability to control radiation releases (CFR 45.9, 45.1
- 0) 2.70 3.20 Knowledge of 10 CFR 20 and related facility radiation control requirements (CFR 41.12, 43.4, 45.9, 45.10) 2.60 3.00 Category
- 3.
Radiation Control
- 4.
Emergency Procedures I Plan 2.3 1
2.3 I
2.3.2 Knowledge of facility ALARA program (CFR 41.12,43.4, 45.9, 45.10) 2.50 2.90 Subtotal 2.4.1 2.4.1 7
2.4.29 2.4.
2.4.5 2.4.32 Subtotal Knowledge of EOP entry conditions and immediate action steps (CFR 41.1 0, 43.5, 45.13) 4.30 4.60 Knowledge of EOP terms and definitions (CFR 41.10, 45.13) 3.10 3.80 Knowledge of the emergency plan (CFR 43.5, 45.1
- 1) 2.60 4.00 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions (CFR 41.10,43.5, 45.13) 2.90 3.60 Knowledge of operator response to loss of all annunciators (CFR 41.lo, 43.5, 45.13) 3.30 3.50 Tier 3 Point Total
ES-401 Record of Rejected WAS, Rev 1 Form ES-401-4 Reason for Rejection Tier I Group Randomly Selected KIA 314 2.4.1 8 Not referenced to 1 OCRF55.43 for SRO
< 2.5 IR for RO
< 2.5 IR for RO 312 2.2.5 314 2.4.42 313 2.3.5
< 2.5 IR for RO 312 2.2.20
< 2.5 IR for RO 312 2.2.1 9
< 2.5 IR for RO
< 2.5 IR for RO 2.2.31 No Mark Ill containment 111 295021 AK2.06 No head spray system 211 211000 K1.10 No connection or cause effect relationship between SLC and HPCl 211 215005 K3.04 No RClS system
< 2.5 IR for RO for all K2 K&As 245000 K2 264000 K5.03 211 262002 K1.01
< 2.5 IR for RO No relationship between UPS and feedwater level control 211 262002 K1.09 No relationship between UPS and drywell ventilation control 262002 K1.13 No relationship between UPS and recirculation pump speed control 211 211 211 211 No relationship between UPS and main steam line radiation monitors 262002 K1.14 262002 K1.15 262002 K1.16 No relationship between UPS and stack gas monitors No relationship between UPS and MSlVs
~
211 262002 K1.17 No relationship between UPS and scram solenoid valves 211 262002 K1.20 No relationship between UPS and plant communications equipment 211 262002 Al.01
< 2.5 IR for RO 211 300000 K1.01
< 2.5 IR for RO 211 264000 2.4.46 System oversampled. Third K&A selected 295036 Al.02 Random change of K&A to insure RO Tier 1 has 2 A2 K&As 1 I2 211 205000 A2.12 Random selection and change of K&A for RO Tier 2 to insure 2 G K&As 211 206000 2.4.46 Oversampled. Verification of alarms tested throughout simulator scenarios.
223001 A1.O1 fi Oversampled for drywell temperature and ventilation.
Note: Rev 1 consists of the last 2 rejected K&As.