ML13354B939

2013 Dresden Initial License Exam, Es 401-1 Sheets

ML13354B939
Person / Time
Site:	Dresden
Issue date:	11/25/2013
From:	Walton R NRC/RGN-III/DRS/OLB
To:	Exelon Generation Co
Walton R
Shared Package
ML11355A021	List: ML13354B939 ML13354B945 ML14015A278 ML14015A355 ML14044A027
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Download: ML13354B939 (10)

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ES-401 BWR Examination Outline Form ES-401-1 Facility: Dresden Station U1/U2 Date of Exam: 10/21/2013 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 4 4 3 3 3 3 20 4 3 7 Emergency &

Abnormal Plant 2 2 1 1 N/A 1 1 N/A 1 7 2 1 3 Evolutions Tier Totals 6 5 4 4 4 4 27 6 4 10 1 3 2 3 3 2 3 2 2 2 2 2 26 3 2 5 2.

Plant 2 2 1 1 1 1 1 1 1 1 1 1 12 2 1 3 Systems Tier Totals 5 3 4 4 3 4 3 3 3 3 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

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

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

G 1 2 3 1 2 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF 295001 Partial or Complete Loss of Forced 0 FORCED CORE FLOW CIRCULATION : Nuclear 3.1 1 S Boiler Instrumentation System Core Flow Circulation / 1 & 4 7 4.6 76 G.2.120 Ability to interpret and execute procedure steps.

Ability to determine and/or interpret the following as 0 they apply to PARTIAL OR COMPLETE LOSS OF 295003 Partial or Complete Loss of AC / 6 3.4 2 1 A.C. POWER : Cause of partial or complete loss of A.C. power G2.1.28 Knowledge of the purpose and function of 295004 Partial or Total Loss of DC Pwr / 6 X 4.1 3 major system components and controls.

Knowledge of the operational implications of the 0 following concepts as they apply to MAIN TURBINE 295005 Main Turbine Generator Trip / 3 4.0 4 1 GENERATOR TRIP : Pressure effects on reactor power Knowledge of the interrelations between SCRAM and the following: Reactor power.

0 4.2 5 295006 SCRAM / 1 S A2.02 Ability to determine and/or interpret the 6 4.4 77 following as they apply to SCRAM: Control Rod Position Knowledge of the reasons for the following responses as they apply to CONTROL ROOM 0 4.1 6 295016 Control Room Abandonment / 7 S ABANDONMENT; Reactor Scram 1 4.7 78 G.2.2.40 Ability to apply Technical Specifications for a system Ability to operate and/or monitor the ollowing as they 0

295018 Partial or Total Loss of CCW / 8 apply to PARTIAL OR COMPLETE LOSS OF 3.3 7 2

COMPONENT COOLING WATER : System Loads Ability to determine and/or interpret the following as 0 they apply to PARTIAL OR COMPLETE LOSS OF 295019 Partial or Total Loss of Inst. Air / 8 3.6 8 2 INSTRUMENT AIR : Status of safety-related instrument air system loads A1.04Ability to operate and/or mojnitor the following 295021 Loss of Shutdown Cooling / 4 x as they apply to a LOSS OF SHUTDOWN COOLING: 3.7 9 Alternate Heat Removal Methods.

Knowledge of the operational implications of the 0

295023 Refueling Acc / 8 following concepts as they apply to REFUELING 3.7 10 3

ACCIDENTS : Inadvertent criticality Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following: RHR/LPCI 0 3.9 11 295024 High Drywell Pressure / 5 S A2.06 Ability to determine and/or interpret the 4 4.1 79 following as they apply to HIGH DRYWELL PRESSURE: Suppression pool temperature

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

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

G 1 2 3 1 2 Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE : High 0 4.1 12 295025 High Reactor Pressure / 3 S Reactor Pressure/ATWS 7 4.3 80 G.2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

Ability to operate and/or monitor the following as they 295026 Suppression Pool High Water 0 apply to SUPPRESSION POOL HIGH WATER 3.9 13 Temp. / 5 3 TEMPERATURE: Temperature Monitoring 295027 High Containment Temperature / 5 Ability to determine and/or interpret the following as 0

295028 High Drywell Temperature / 5 they apply to HIGH DRYWELL TEMPERATURE : 3.6 14 5

Torus/suppression chamber pressure G2.1.28 Knowledge of the purpose and function of 295030 Low Suppression Pool Wtr Lvl / 5 X 4.1 15 major system components and controls.

Knowledge of the operational implications of the 0

295031 Reactor Low Water Level / 2 following concepts as they apply to REACTOR LOW 4.6 16 1

WATER LEVEL : Adequate core cooling Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN and 295037 SCRAM Condition Present following: Reactor water level 4.0 17 0

and Reactor Power Above APRM S 9 EA2.03 Ability to determine and/or interpret the 4.4 81 Downscale or Unknown / 1 following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : SBLC tank level Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE : Biological effects of radioisotope ingestion 2.5 18 0 G2.4.30 Knowledge of events related to system 295038 High Off-site Release Rate / 9 S 1 operation/satus that must be reported to internal organizaitons or ezternal agencies such as the State, 4.1 82 the NRC, or the transmission system operator.rocedure implementation during emergency operations.

Knowledge of the interrelations between PLANT 0

600000 Plant Fire On Site / 8 FIRE ON SITE and the following: Sensors / detectors 2.6 19 1

and valves Knowledge of the reasons for the following responses 700000 Generator Voltage and Electric Grid 0 as they apply to GENERATOR VOLTAGE AND 3.6 20 Disturbances / 6 2 ELECTRIC GRID DISTURBANCES: Actions contained in AOP for voltage and grid disturbances.

3 3 Group Point Total: 20/

K/A Category Totals: 4 4 2 4 / / 7 3 4

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

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

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 S A2.03 Ability to determine and/or interpret the following 3.7 83 as they apply to HIGH REACTOR PRESSURE :

Reactor water level 295008 High Reactor Water Level / 2 0 Knowledge of the interrelations between HIGH 3.8 21 5 REACTOR WATER LEVEL and the following: HPCI 295009 Low Reactor Water Level / 2 0 Knowledge of the operational implications of the 3.3 22 5 following concepts as they apply to LOW REACTOR WATER LEVEL : Natural circulation 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 0 Ability to determine and/or interpret the following as 3.8 23 1 they apply to HIGH DRYWELL TEMPERATURE :

Drywell temperature 295013 High Suppression Pool Temp. / 5 0 Knowledge of the operational implications of the 2.5 24 1 following concepts as they apply to HIGH SUPPRESSION POOL TEMPERATURE : Pool stratification 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 R G2.4.35 Knowledge of local auxiliary operator tasks 3.8 25 during an emergency and the resultant operational effects.

295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 S A2.06 Ability to determine and/or interpret the 3.8 84 following as they apply to INADVERTENT CONTAINMENT ISOLATION : Cause of isolation 295022 Loss of CRD Pumps / 1 G2.1.23 Ability to perform specific system and 4.4 85 integrated plant procedures during all modes of plant operation.

295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment 0 Knowledge of the reasons for the following responses 4.1 26 Ventilation High Radiation / 9 2 as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION : Starting SBGT/FRVS 295035 Secondary Containment High 0 Ability to operate and/or monitor the following as they 3.6 27 Differential Pressure / 5 1 apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment ventilation system

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

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

1 2 3 1 2 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 2 1 1 1 1 1 Group Point Total: 7/

/ / 3 2 1

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

System # / Name K K K K K K A A A A K/A Topic(s)

G IR #

1 2 3 4 5 6 1 2 3 4 Ability to predict and/or monitor changes in parameters associated with operating the 3.7 28 203000 RHR/LPCI: Injection 0 RHR/LPCI: INJECTION MODE (PLANT S SPECIFIC) controls including: Emergency Mode 8 generator loading 4.3 86 G.2.3.11 Ability to control radiation releases.

Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING 1 MODE) ; and (b) based on those predictions, 205000 Shutdown Cooling 2.7 29 1 use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation pump trips Ability to monitor automatic operations of the 0

206000 HPCI HIGH PRESSURE COOLANT INJECTION 4.2 30 4

SYSTEM including: Reactor pressure 207000 Isolation (Emergency) 0 Ability to manually operate and/or monitor in 3.8 31 Condenser 6 the control room: Shell side makeup valves G. 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core 209001 LPCS R 4.0 32 cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

209002 HPCS Knowledge of the physical connections and/or cause-effect relationships between STANDBY LIQUID CONTROL SYSTEM and the 2.5 33 following: Plant Air Systems 0 A2.03 Ability to (a) predict the impacts of the 211000 SLC S following on the STANDBY LIQUID 3

CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of 3.4 87 those abnormal conditions or operations: A.C.

power failures Knowledge of electrical power supplies to the following: Analog trip system logic cabinets 2.7 34 0

212000 RPS S G2.2.42 Ability to recognize system 2

parameters that are entry-level conditions for 4.6 88 Technical Specifications.

Knowledge of the effect that a loss or 0 malfunction of the INTERMEDIATE RANGE 215003 IRM 3.9 35 1 MONITOR (IRM) SYSTEM will have on following: RPS

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

System # / Name K K K K K K A A A A K/A Topic(s)

G IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of SOURCE RANGE MONITOR 0 (SRM) SYSTEM design feature(s) and/or 215004 Source Range Monitor 3.2 36 6 interlocks which provide for the following:

IRM/SRM interlock Knowledge of the operational implications of the following concepts as they apply to 0 AVERAGE POWER RANGE 215005 APRM / LPRM 2.9 37 4 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM : LPRM detector location and core symmetry 217000 RCIC Knowledge of the effect that a loss or 0 malfunction of the following will have on the 218000 ADS 3.9 38 1 AUTOMATIC DEPRESSURIZATION SYSTEM : RHR/LPCI system pressure Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION 2.6 39 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including: Individual system relay status 223002 PCIS/Nuclear Steam 0 A2.08 Ability to (a) predict the impacts of the S

Supply Shutoff 4 following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, 3.1 89 control, or mitigate the consequences of those abnormal conditions or operations:

Surveillance testing 0 Knowledge of electrical power supplies to the 239002 SRVs 4.1 40 6 following: SRV Solenoids.

Ability to monitor automatic operations of the 259002 Reactor Water Level 0 REACTOR WATER LEVEL CONTROL 3.0 41 Control 6 SYSTEM including: Reactor water level setpoint setdown following a reactor scram 0 Ability to manually operate and/or monitor in 261000 SGTS 2.7 42 9 the control room: Ventilation valves/dampers Knowledge of the physical connections and/or cause-effect relationships between A.C. 3.8 43 262001 AC Electrical 0 ELECTRICAL DISTRIBUTION and the R following: Emergency generators Distribution 1 G.2.1.20 Ability to interpret and execute 4.6 44 procedure steps.

Knowledge of the physical connections and/or cause-effect relationships between 2.5 45 UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) and the following: Drywell 0 0 ventilation control 262002 UPS (AC/DC) 9 2 Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY 2.8 46 (A.C./D.C.) : D.C. electrical power

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

System # / Name K K K K K K A A A A K/A Topic(s)

G IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of electrical power supplies to the following: Major D.C. loads 3.1 47 263000 DC Electrical 0 0 Knowledge of the effect that a loss or Distribution 1 2 malfunction of the D.C. ELECTRICAL DISTRIBUTION will have on following: 3.5 48 Components using D.C. control power (i.e.

breakers)

Knowledge of the effect that a loss or malfunction of the EMERGENCY 4.2 49 GENERATORS (DIESEL/JET) will have on 0 0 following: Emergency core cooling systems 264000 EDGs 1 6 Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for the following: 2.6 50 Governor control Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following: Cross over to other 3.0 51 0 1 air systems.

300000 Instrument Air 2 3 Knowledge of the operational implications of 2.9 52 the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Filters Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: Valves 2.7 53 400000 Component Cooling 0 A2.02 Ability to (a) predict the impacts of the S following on the CCWS and (b) based on Water 1 those predictions, use procedures to correct, control, or mitigate the consequences of 3.0 90 those abnormal operation: High/low surge tank level 2 2 Group Point Total: 26/

K/A Category Point Totals: 3 2 3 3 2 3 2 / 2 2 / 5 3 2

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 1 Ability to predict and/or monitor changes in 2.8 54 0 parameters associated with operating the CONTROL ROD DRIVE HYDRAULIC SYSTEM controls including: CRD cooling water flow 201002 RMCS S A2.02 Ability to (a) predict the impacts of the 3.3 91 following on the REACTOR MANUAL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod drift alarm 201003 Control Rod and Drive 0 Knowledge of the operational implications of 2.7 55 Mechanism 6 the following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM :

How control rod worth varies with moderator temperature and voids.

201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 0 Ability to monitor automatic operations of the 3.2 56 4 RECIRCULATION SYSTEM including: Lights and alarms 202002 Recirculation Flow Control 0 Knowledge of RECIRCULATION FLOW 2.9 57 7 CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

Minimum and maximum pump speed setpoints 204000 RWCU 0 Ability to manually operate and/or monitor in 3.2 58 3 the control room: RWCU drain flow regulator 214000 RPIS 215001 Traversing In-core Probe 0 Knowledge of the physical connections and/or 2.5 59 2 cause-effect relationships between TRAVERSING IN-CORE PROBE and the following: Process computer 215002 RBM 0 Knowledge of electrical power supplies to the 2.5 60 1 following: RBM channels 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling 0 Knowledge of the effect that a loss or 3.2 61 Mode 1 malfunction of the following will have on the RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE : AC Electrical Power 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator

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

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 245000 Main Turbine Gen. / Aux. S G2.1.37 Knowledge of procedures, guidelines, 3.0 92 or limitations associated with reactivity management.

256000 Reactor Condensate 259001 Reactor Feedwater 0 Knowledge of the physical connections and/or 2.7 62 6 cause-effect relationships between REACTOR FEEDWATER SYSTEM and the following:

Main turbine generator 268000 Radwaste 0 Knowledge of the effect that a loss or 2.7 63 4 malfunction of the RADWASTE will have on following: Drain sumps 271000 Offgas 0 Ability to (a) predict the impacts of the 3.5 64 3 following on the OFFGAS SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Main steamline high radiation 272000 Radiation Monitoring R 2.2.37 Ability to determine operability and /or 3.6 65 availability of safety related equipment.

286000 Fire Protection S A2.03 Ability to (a) predict the impacts of the 3.0 93 following on the FIRE PROTECTION SYSTEM

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations

A.C. Distribution failure 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals: 2 1 1 1 1 1 1 1 1 1 1 Group Point Total: 12/3

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