ML12284A310

2012 Dresden Nuclear Power Station Initial License Examination ES-401-1, ES-401-3 Rev 1

ML12284A310
Person / Time
Site:	Dresden
Issue date:	09/26/2012
From:	David Reeser Operations Branch III
To:	Nelson J Exelon Generation Co
Shared Package
ML11354A121	List: ML12132A315 ML12132A316 ML12132A317 ML12132A318 ML12132A319 ML12132A320 ML12132A321 ML12132A322 ML12132A323 ML12132A324 ML12132A325 ML12132A327 ML12132A328 ML12284A310 ML12284A317 ML12284A326 ML12284A332 ML12284A336 ML12284A338 ML12284A342 ML12284A366 ML12284A373 ML12284A378 ML12291A685 ML12291A688
References
Download: ML12284A310 (10)

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ES-401BWR Examination OutlineFORM ES-401-1Facility Name: Dresden Date of Exam: 8/6/2012 K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G *TotalTotal 1 3 3 3 4 4 3 20 7 2 2 1 1 1 1 1 7 3Tier Totals 5 4 4 5 5 4 27 10 1 3 2 3 3 2 3 2 2 2 2 2 26 5 2 1 1 1 1 2 1 1 1 1 1 1 12 0 2 3Tier Totals 4 3 4 4 4 4 3 3 3 3 3 38 8 1 2 3 4 1 2 2 2Note: 1.Note: 2.Note: 3.Note: 4.Note: 5.Note: 6.Note: 7.*Note: 8.Note: 9.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.ES-401, Page 16 of 33 4 3N/AN/AFor 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.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.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.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.

3The 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.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 Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.3. Generic Knowledge and Abilities Categories 1 2 2 3 4 3 A2 2 6 3 1 4 2 10 G*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.RO K/A Category Points 7Ensure 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).TierGroupSRO-Only Points2. Plant Systems1. Emergency & Abnormal Plant Evolutions 1 4 4 2 ES-401 2Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#52295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0

6Nuclear boiler instrumentation3.2 1 53295003 Partial or Complete Loss of AC / 6 0

3Battery status: Plant-Specific3.2 1 44295004 Partial or Total Loss of DC Pwr / 6 0

1Battery charger3.1 1 39295005 Main Turbine Generator Trip / 3 0

1Pressure effects on reactor power4.0 1 55295006 SCRAM / 1 01.23Ability to perform specific system and integrated plant procedures during all modes of plant operation.4.3 1 50295016 Control Room Abandonment / 7 0 4A.C. electrical distribution3.1 1 58295018 Partial or Total Loss of CCW / 8 0

1Component temperatures3.3 1 45295019 Partial or Total Loss of Inst. Air / 8 0

2Standby air compressor operation3.5 1 56295021 Loss of Shutdown Cooling / 4 02.39Knowledge of less than or equal to one hour Technical Specification action statements for systems.3.9 1 51295023 Refueling Acc / 8 0 3Airborne contamination levels3.3 1 43295024 High Drywell Pressure / 5 1

8Ventilation3.3 1 48295025 High Reactor Pressure / 3 0

7ARI/RPT/ATWS: Plant-Specific4.1 1 54295026 Suppression Pool High Water Temp. / 5 04.49Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.4.6 1295027 High Containment Temperature / 5Dresden does not have a Mark III containment 0 42295028 High Drywell Temperature / 5 0 3Reactor water level indication 3.6 1 57295030 Low Suppression Pool Wtr Lvl / 5 0

5HPCI3.5 1 47295031 Reactor Low Water Level / 2 0

4Steam cooling4.0 1 41295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 0

3Boron effects on reactor power (SBLC)4.2 1 49295038 High Off-site Release Rate / 9 0

1Stack-gas monitoring system: Plant-Specific3.9 1 40600000 Plant Fire On Site / 8 0

2Fire Fighting2.9 1 46700000 Generator Voltage and Electric Grid Disturbances / 6 0

2Actions contained in abnormal operating procedure for voltage and grid disturbances3.6 1K/A Category Totals:

3 3 3 4 4 3 20ES-401, Page 17 of 33Group Point Total:

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

Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#295002 Loss of Main Condenser Vac / 3 0295007 High Reactor Pressure / 3 0295008 High Reactor Water Level / 2 0 62295009 Low Reactor Water Level / 2 0 4Reactor water cleanup2.7 1295010 High Drywell Pressure / 5 0295011 High Containment Temp / 5Dresden does not have a Mark III containment 0295012 High Drywell Temperature / 5 0295013 High Suppression Pool Temp. / 5 0295014 Inadvertent Reactivity Addition / 1 0 59295015 Incomplete SCRAM / 1 0

4Reactor pressure: Plant-Specific3.8 1 60295017 High Off-site Release Rate / 9 1

2Standby gas treatment/FRVS3.4 1 63295020 Inadvertent Cont. Isolation / 5 & 7 0

4Reactor pressure 3.9 1 61295022 Loss of CRD Pumps / 1 0

2CRDM high temperature2.9 1295029 High Suppression Pool Wtr Lvl / 5 0 64295032 High Secondary Containment Area Temperature / 5 01.19Ability to use plant computers to evaluate system or component status.3.9 1295033 High Secondary Containment Area Radiation Levels / 9 0 65295034 Secondary Containment Ventilation High Radiation / 9 0

1Personnel protection3.8 1295035 Secondary Containment High Differential Pressure / 5 0295036 Secondary Containment High Sump/Area Water Level / 5 0500000 High CTMT Hydrogen Conc. / 5 0K/A Category Totals:

2 1 1 1 1 1 7ES-401, Page 18 of 33Group Point Total:

ES-401 4Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 1 (RO)Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)IR#20203000 RHR/LPCI: Injection Mode 0 5Manual initiation controls 4.3 1 13205000 Shutdown Cooling 0

8Heat exchanger temperatures 3.1 1 4206000 HPCI 0

1System valves: BWR-2, 3, 4 3.2 1 1207000 Isolation (Emergency)

Condenser 1 1Primary containment isolation system: BWR-2, 3 3.4 1 21209001 LPCS 02.38Knowledge of conditions and limitations in the facility license.3.6 1209002 HPCSSystem not utilized at Dresden 0 7211000 SLC 0 6Core plate differential pressure indication 2.6 1 2212000 RPS 0

4A.C. electrical distribution 3.4 1 9215003 IRM 0

3Changing detector position 3.0 1 25 14215004 Source Range Monitor 0

4 0 5Detectors; SCRAM, rod block, and period alarm trip setpoints 2.9; 3.6 2 15215005 APRM / LPRM 0 3Inoperative trip (all causes) 3.6 1217000 RCICSystem not utilized at Dresden 0 3218000 ADS 0

1ADS logic 3.1 1 26 8223002 PCIS/Nuclear Steam Supply Shutoff 2 8 0 8Containment nitrogen inerting system; Manual defeating of selected isolations during specified emergency conditions 2.7; 3.3 2 16239002 SRVs 0

2Leaky SRV 3.1 1 18259002 Reactor Water Level Control 0

6Reactor water level setpoint setdown following a reactor scram: Plant-Specific 3.0 1 17261000 SGTS 0 3Valve operation 3.0 1 11262001 AC Electrical Distribution 0

1D.C. power 3.1 1 6262002 UPS (AC/DC) 0 5Rod worth minimizer: Plant-Specific 2.9 1 24 19263000 DC Electrical Distribution 0

1 0 2A.C. electrical distribution; Battery voltage indicator: Plant-Specific 3.3; 3.2 2 23 10264000 EDGs 0

7 0 5Local operation and control; Paralleling A.C. power sources 3.3; 3.4 2 5300000 Instrument Air 0 2Systems having pneumatic valves and controls 3.3 1 12 22400000 Component Cooling Water 0

5 01.32Motors ; Ability to explain and apply system limits and precautions.

2.8; 3.8 2 0K/A Category Totals:

3 2 3 3 2 3 2 2 2 2 2 26ES-401, Page 19 of 33Group Point Total:

ES-401-1 5Form ES-401-1ES-401BWR Examination OutlineForm ES-401-1Plant Systems - Tier 2/Group 2 (RO)Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)IR#31201001 CRD Hydraulic 0 8Solenoid operated valves 2.5 1201002 RMCS 0 27201003 Control Rod and Drive Mechanism 0

3RPIS 3.1 1201004 RSCSSystem not utilized at Dresden 0201005 RCISSystem not utilized at Dresden 0201006 RWM 0 38202001 Recirculation 0

2Jet pump operation: BWR-3, 4, 5, 6 3.1 1202002 Recirculation Flow Control 0204000 RWCU 0 30214000 RPIS 0

1Reed switch locations 3.0 1215001 Traversing In-core Probe 0 36215002 RBM 0

3Trip bypasses: BWR-3, 4, 5 2.8 1216000 Nuclear Boiler Inst.

0 28219000 RHR/LPCI: Torus/Pool Cooling Mode 0

1Valves 2.5 1 34223001 Primary CTMT and Aux.

0 9Vacuum breaker malfunction 3.4 1226001 RHR/LPCI: CTMT Spray Mode 0 32230000 RHR/LPCI: Torus/Pool Spray Mode 0

5Suppression pool 3.3 1233000 Fuel Pool Cooling/Cleanup 0234000 Fuel Handling Equipment 0239001 Main and Reheat Steam 0239003 MSIV Leakage Control 0241000 Reactor/Turbine Pressure Regulator 0 33245000 Main Turbine Gen. / Aux.

0 8Generator output voltage/reactive load 2.5 1256000 Reactor Condensate 0 37259001 Reactor Feedwater 04.31Knowledge of annunciator alarms, indications, or response procedures.

4.2 1268000 Radwaste 0271000 Offgas 0272000 Radiation Monitoring 0 29286000 Fire Protection 0

2Personnel protection 3.2 1 35288000 Plant Ventilation 0

1Isolation/initiation signals 3.8 1290001 Secondary CTMT 0290003 Control Room HVAC 0290002 Reactor Vessel Internals 0 0K/A Category Totals:

1 1 1 1 2 1 1 1 1 1 1 12ES-401, Page 20 of 33Group Point Total:

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

Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0295003 Partial or Complete Loss of AC / 6 0295004 Partial or Total Loss of DC Pwr / 6 079295005 Main Turbine Generator Trip / 302.

25Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.4.2 176295006 SCRAM / 1 0 6Cause of reactor SCRAM3.8 1295016 Control Room Abandonment / 7 077295018 Partial or Total Loss of CCW / 8 0

2Cooling water temperature3.2 181295019 Partial or Total Loss of Inst. Air / 804.

08Knowledge of how abnormal operating procedures are used in conjunction with EOPs.4.5 1295021 Loss of Shutdown Cooling / 4 0295023 Refueling Acc / 8 0295024 High Drywell Pressure / 5 0295025 High Reactor Pressure / 3 0295026 Suppression Pool High Water Temp.

/ 5 0295027 High Containment Temperature / 5Dresden does not have a Mark III containment 078295028 High Drywell Temperature / 5 0

1Drywell temperature4.1 182295030 Low Suppression Pool Wtr Lvl / 502.

22Knowledge of limiting conditions for operations and safety limits.4.7 1295031 Reactor Low Water Level / 2 080295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 104.35Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.4.0 1295038 High Off-site Release Rate / 9 0600000 Plant Fire On Site / 8 0700000 Generator Voltage and Electric Grid Disturbances / 6 0K/A Category Totals:

0 0 0 0 3 4 7ES-401, Page 17 of 33Group Point Total:

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

Q#E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 GK/A Topic(s)

IR#295002 Loss of Main Condenser Vac / 3 0295007 High Reactor Pressure / 3 0295008 High Reactor Water Level / 2 0295009 Low Reactor Water Level / 2 0 85295010 High Drywell Pressure / 5 04.11Knowledge of abnormal condition procedures.4.2 1295011 High Containment Temp / 5Dresden does not have a Mark III containment 0295012 High Drywell Temperature / 5 0 83295013 High Suppression Pool Temp. / 5 0 1Suppression pool temperature4.0 1295014 Inadvertent Reactivity Addition / 1 0295015 Incomplete SCRAM / 1 0295017 High Off-site Release Rate / 9 0295020 Inadvertent Cont. Isolation / 5 & 7 0295022 Loss of CRD Pumps / 1 0295029 High Suppression Pool Wtr Lvl / 5 0295032 High Secondary Containment Area Temperature / 5 0295033 High Secondary Containment Area Radiation Levels / 9 0295034 Secondary Containment Ventilation High Radiation / 9 0295035 Secondary Containment High Differential Pressure / 5 0 84295036 Secondary Containment High Sump/Area Water Level / 5 04.18Knowledge of the specific bases for EOPs.4.0 1500000 High CTMT Hydrogen Conc. / 5 0K/A Category Totals:

0 0 0 0 1 2 3ES-401, Page 18 of 33Group Point Total:

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

Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)

IR#203000 RHR/LPCI: Injection 087205000 Shutdown Cooling Mode 0 1Recirculation loop high temperature: Plant-Specific3.3 1206000 HPCI 0207000 Isolation (Emergency)

Condenser 089209001 LPCS02.40Ability to apply Technical Specifications for a system.4.7 1209002 HPCSSystem not utilized at Dresden 086211000 SLC 0

4Inadequate system flow3.4 1212000 RPS 0215003 IRM 0215004 Source Range Monitor 0215005 APRM / LPRM 0217000 RCICSystem not utilized at Dresden 0218000 ADS 0223002 PCIS/Nuclear Steam Supply Shutoff 0239002 SRVs 0259002 Reactor Water Level Control 088261000 SGTS02.44Ability 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.4.4 190262001 AC Electrical Distribution04.05Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.4.3 1262002 UPS (AC/DC) 0263000 DC Electrical Distribution 0264000 EDGs 0300000 Instrument Air 0400000 Component Cooling Water 0 0K/A Category Totals:

0 0 0 0 0 0 0 2 0 0 3 5ES-401, Page 19 of 33Group Point Total:

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

Q#System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 GK/A Topic(s)

IR#201001 CRD Hydraulic 0201002 RMCS 0201003 Control Rod and Drive Mechanism 0201004 RSCSSystem not utilized at Dresden 0201005 RCISSystem not utilized at Dresden 0201006 RWM 0202001 Recirculation 0202002 Recirculation Flow Control 091204000 RWCU 0 3Flow control valve failure2.9 1214000 RPIS 0215001 Traversing In-core Probe 0215002 RBM 0216000 Nuclear Boiler Inst.

0219000 RHR/LPCI: Torus/Pool Cooling Mode 0223001 Primary CTMT and Aux.

0226001 RHR/LPCI: CTMT Spray Mode 0230000 RHR/LPCI: Torus/Pool Spray Mode 093233000 Fuel Pool Cooling/Cleanup 0

9A.C. electrical power failures2.9 1234000 Fuel Handling Equipment 0239001 Main and Reheat Steam 0239003 MSIV Leakage Control 092241000 Reactor/Turbine Pressure Regulator 01.07Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.4.7 1245000 Main Turbine Gen. / Aux.

0256000 Reactor Condensate 0259001 Reactor Feedwater 0268000 Radwaste 0271000 Offgas 0272000 Radiation Monitoring 0286000 Fire Protection 0288000 Plant Ventilation 0290001 Secondary CTMT 0290003 Control Room HVAC 0290002 Reactor Vessel Internals 0 0K/A Category Totals:

0 0 0 0 0 0 0 2 0 0 1 3ES-401, Page 20 of 33Group Point Total:

ES-401Generic Knowledge and Abilities Outline (Tier 3)Form ES-401-3Facility Name:Dresden Date of Exam:8/6/2012 Q#IR#IR#672.1.20Ability to interpret and execute procedure steps.4.6 1 662.1.25Ability to interpret reference materials, such as graphs, curves, tables, etc.3.9 1 752.1.26Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).3.4 12.1.2.1.942.1.42Knowledge of new and spent fuel movement procedures.3.4 1Subtotal 3 1 682.2.03Knowledge of the design, procedural, and operational differences between units.3.8 1 692.2.20Knowledge of the process for managing troubleshooting activities.2.6 12.2.

2.2.1002.2.23Ability to track Technical Specification limiting conditions for operations.4.6 1 952.2.37Ability to determine operability and/or availability of safety related equipment.4.6 1Subtotal 2 2 712.3.04Knowledge of radiation exposure limits under normal or emergency conditions.3.2 1 702.3.14Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.3.4 12.3.2.3.962.3.05Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.2.9 1 992.3.06Ability to approve release permits.3.8 1Subtotal 2 2 732.4.23Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.3.4 1 742.4.28Knowledge of procedures relating to a security event.3.2 1 722.4.32Knowledge of operator response to loss of all annunciators.3.6 12.4.982.4.40Knowledge of SRO responsibilities in emergency plan implementation.4.5 1 972.4.41Knowledge of the emergency action level thresholds and classifications.4.6 1Subtotal 3 2 10 7 ROSRO-OnlyCategoryTopic1. Conduct of OperationsK/A #ES-401, Page 26 of 33Tier 3 Point Total3. Radiation Control4. Emergency Procedures

/ Plan2. Equipment Control