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)

Text

ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Dresden Date of Exam: 8/6/2012 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

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

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

Plant 2 1 1 1 1 2 1 1 1 1 1 1 12 0 2 1 3 Systems Tier Totals 4 3 4 4 4 4 3 3 3 3 3 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 2 2 3 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).

Note: 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.

Note: 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 Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

Note: 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.

Note: 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.

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

Note: 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.

Note: 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.

Note: 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, Page 16 of 33

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)

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

1 2 3 1 2 295001 Partial or Complete Loss of Forced 0 52 Nuclear boiler instrumentation 3.2 1 Core Flow Circulation / 1 & 4 6 0

53 295003 Partial or Complete Loss of AC / 6 Battery status: Plant-Specific 3.2 1 3

0 44 295004 Partial or Total Loss of DC Pwr / 6 Battery charger 3.1 1 1

0 39 295005 Main Turbine Generator Trip / 3 Pressure effects on reactor power 4.0 1 1

01. Ability to perform specific system and integrated plant 55 295006 SCRAM / 1 4.3 1 23 procedures during all modes of plant operation.

0 50 295016 Control Room Abandonment / 7 A.C. electrical distribution 3.1 1 4

0 58 295018 Partial or Total Loss of CCW / 8 Component temperatures 3.3 1 1

0 45 295019 Partial or Total Loss of Inst. Air / 8 Standby air compressor operation 3.5 1 2

02. Knowledge of less than or equal to one hour Technical 56 295021 Loss of Shutdown Cooling / 4 3.9 1 39 Specification action statements for systems.

0 51 295023 Refueling Acc / 8 Airborne contamination levels 3.3 1 3

1 43 295024 High Drywell Pressure / 5 Ventilation 3.3 1 8

0 48 295025 High Reactor Pressure / 3 ARI/RPT/ATWS: Plant-Specific 4.1 1 7

Ability to perform without reference to procedures those actions 295026 Suppression Pool High Water 04.

54 that require immediate operation of system components and 4.6 1 Temp. / 5 49 controls.

295027 High Containment Temperature / 5 Dresden does not have a Mark III containment 0 0

42 295028 High Drywell Temperature / 5 Reactor water level indication 3.6 1 3

0 57 295030 Low Suppression Pool Wtr Lvl / 5 HPCI 3.5 1 5

0 47 295031 Reactor Low Water Level / 2 Steam cooling 4.0 1 4

295037 SCRAM Condition Present and 0

41 Reactor Power Above APRM Downscale or Boron effects on reactor power (SBLC) 4.2 1 3

Unknown / 1 0

49 295038 High Off-site Release Rate / 9 Stack-gas monitoring system: Plant-Specific 3.9 1 1

0 40 600000 Plant Fire On Site / 8 Fire Fighting 2.9 1 2

700000 Generator Voltage and Electric Grid 0 Actions contained in abnormal operating procedure for voltage 46 3.6 1 Disturbances / 6 2 and grid disturbances K/A Category Totals: 3 3 3 4 4 3 Group Point Total: 20 ES-401, Page 17 of 33

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)

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

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 0 295007 High Reactor Pressure / 3 0 295008 High Reactor Water Level / 2 0 0

62 295009 Low Reactor Water Level / 2 Reactor water cleanup 2.7 1 4

295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 Dresden does not have a Mark III containment 0 295012 High Drywell Temperature / 5 0 295013 High Suppression Pool Temp. / 5 0 295014 Inadvertent Reactivity Addition / 1 0 0

59 295015 Incomplete SCRAM / 1 Reactor pressure: Plant-Specific 3.8 1 4

1 60 295017 High Off-site Release Rate / 9 Standby gas treatment/FRVS 3.4 1 2

0 63 295020 Inadvertent Cont. Isolation / 5 & 7 Reactor pressure 3.9 1 4

0 61 295022 Loss of CRD Pumps / 1 CRDM high temperature 2.9 1 2

295029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 01. Ability to use plant computers to evaluate system or component 64 3.9 1 Temperature / 5 19 status.

295033 High Secondary Containment Area 0

Radiation Levels / 9 295034 Secondary Containment Ventilation 0 65 Personnel protection 3.8 1 High Radiation / 9 1 295035 Secondary Containment High 0

Differential Pressure / 5 295036 Secondary Containment High 0

Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 2 1 1 1 1 1 Group Point Total: 7 ES-401, Page 18 of 33

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

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

1 2 3 4 5 6 1 2 3 4 0

20 203000 RHR/LPCI: Injection Mode Manual initiation controls 4.3 1 5

0 13 205000 Shutdown Cooling Heat exchanger temperatures 3.1 1 8

0 4 206000 HPCI System valves: BWR-2, 3, 4 3.2 1 1

207000 Isolation (Emergency) 1 1 Primary containment isolation system: BWR-2, 3 3.4 1 Condenser 1

02. Knowledge of conditions and limitations in the facility 21 209001 LPCS 3.6 1 38 license.

209002 HPCS System not utilized at Dresden 0 0

7 211000 SLC Core plate differential pressure indication 2.6 1 6

0 2 212000 RPS A.C. electrical distribution 3.4 1 4

0 9 215003 IRM Changing detector position 3.0 1 3

25 0 0 Detectors; SCRAM, rod block, and period alarm trip 2.9; 215004 Source Range Monitor 2 14 4 5 setpoints 3.6 0

15 215005 APRM / LPRM Inoperative trip (all causes) 3.6 1 3

217000 RCIC System not utilized at Dresden 0 0

3 218000 ADS ADS logic 3.1 1 1

26 223002 PCIS/Nuclear Steam Supply 2 0 Containment nitrogen inerting system; Manual defeating of 2.7; 2

8 Shutoff 8 8 selected isolations during specified emergency conditions 3.3 0

16 239002 SRVs Leaky SRV 3.1 1 2

0 Reactor water level setpoint setdown following a reactor 18 259002 Reactor Water Level Control 3.0 1 6 scram: Plant-Specific 0

17 261000 SGTS Valve operation 3.0 1 3

0 11 262001 AC Electrical Distribution D.C. power 3.1 1 1

0 6 262002 UPS (AC/DC) Rod worth minimizer: Plant-Specific 2.9 1 5

24 0 0 A.C. electrical distribution; Battery voltage indicator: Plant- 3.3; 263000 DC Electrical Distribution 2 19 1 2 Specific 3.2 23 0 0 Local operation and control; Paralleling A.C. power 3.3; 264000 EDGs 2 10 7 5 sources 3.4 0

5 300000 Instrument Air Systems having pneumatic valves and controls 3.3 1 2

12 0 01. Motors ; Ability to explain and apply system limits and 2.8; 400000 Component Cooling Water 2 22 5 32 precautions. 3.8 0

K/A Category Totals: 3 2 3 3 2 3 2 2 2 2 2 Group Point Total: 26 ES-401, Page 19 of 33

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

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

1 2 3 4 5 6 1 2 3 4 0

31 201001 CRD Hydraulic 8 Solenoid operated valves 2.5 1 201002 RMCS 0 0

27 201003 Control Rod and Drive Mechanism 3 RPIS 3.1 1 201004 RSCS System not utilized at Dresden 0 201005 RCIS System not utilized at Dresden 0 201006 RWM 0 0

38 202001 Recirculation 2 Jet pump operation: BWR-3, 4, 5, 6 3.1 1 202002 Recirculation Flow Control 0 204000 RWCU 0 0

30 214000 RPIS 1 Reed switch locations 3.0 1 215001 Traversing In-core Probe 0 0

36 215002 RBM 3 Trip bypasses: BWR-3, 4, 5 2.8 1 216000 Nuclear Boiler Inst. 0 0

28 219000 RHR/LPCI: Torus/Pool Cooling Mode 1 Valves 2.5 1 0

34 223001 Primary CTMT and Aux. 9 Vacuum breaker malfunction 3.4 1 226001 RHR/LPCI: CTMT Spray Mode 0 0

32 230000 RHR/LPCI: Torus/Pool Spray Mode 5 Suppression pool 3.3 1 233000 Fuel Pool Cooling/Cleanup 0 234000 Fuel Handling Equipment 0 239001 Main and Reheat Steam 0 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0 0

33 245000 Main Turbine Gen. / Aux. 8 Generator output voltage/reactive load 2.5 1 256000 Reactor Condensate 0

04. Knowledge of annunciator alarms, indications, or response 37 259001 Reactor Feedwater 4.2 1 31 procedures.

268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 0

29 286000 Fire Protection 2 Personnel protection 3.2 1 0

35 288000 Plant Ventilation 1 Isolation/initiation signals 3.8 1 290001 Secondary CTMT 0 290003 Control Room HVAC 0 290002 Reactor Vessel Internals 0 0

K/A Category Totals: 1 1 1 1 2 1 1 1 1 1 1 Group Point Total: 12 ES-401, Page 20 of 33

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 (SRO)

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

1 2 3 1 2 295001 Partial or Complete Loss of Forced 0

Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC / 6 0 295004 Partial or Total Loss of DC Pwr / 6 0

02. Knowledge of the bases in Technical Specifications for 79 295005 Main Turbine Generator Trip / 3 4.2 1 25 limiting conditions for operations and safety limits.

0 76 295006 SCRAM / 1 Cause of reactor SCRAM 3.8 1 6

295016 Control Room Abandonment / 7 0 0

77 295018 Partial or Total Loss of CCW / 8 Cooling water temperature 3.2 1 2

04. Knowledge of how abnormal operating procedures are 81 295019 Partial or Total Loss of Inst. Air / 8 4.5 1 08 used in conjunction with EOPs.

295021 Loss of Shutdown Cooling / 4 0 295023 Refueling Acc / 8 0 295024 High Drywell Pressure / 5 0 295025 High Reactor Pressure / 3 0 295026 Suppression Pool High Water Temp.

0

/5 295027 High Containment Temperature / 5 Dresden does not have a Mark III containment 0 0

78 295028 High Drywell Temperature / 5 Drywell temperature 4.1 1 1

02. Knowledge of limiting conditions for operations and 82 295030 Low Suppression Pool Wtr Lvl / 5 4.7 1 22 safety limits.

295031 Reactor Low Water Level / 2 0 295037 SCRAM Condition Present

04. Knowledge of local auxiliary operator tasks during an 80 and Reactor Power Above APRM 4.0 1 35 emergency and the resultant operational effects.

Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 0 600000 Plant Fire On Site / 8 0 700000 Generator Voltage and Electric Grid 0

Disturbances / 6 K/A Category Totals: 0 0 0 0 3 4 Group Point Total: 7 ES-401, Page 17 of 33

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 (SRO)

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

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 0 295007 High Reactor Pressure / 3 0 295008 High Reactor Water Level / 2 0 295009 Low Reactor Water Level / 2 0 04.

85 295010 High Drywell Pressure / 5 Knowledge of abnormal condition procedures. 4.2 1 11 295011 High Containment Temp / 5 Dresden does not have a Mark III containment 0 295012 High Drywell Temperature / 5 0 0

83 295013 High Suppression Pool Temp. / 5 Suppression pool temperature 4.0 1 1

295014 Inadvertent Reactivity Addition / 1 0 295015 Incomplete SCRAM / 1 0 295017 High Off-site Release Rate / 9 0 295020 Inadvertent Cont. Isolation / 5 & 7 0 295022 Loss of CRD Pumps / 1 0 295029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 0

Temperature / 5 295033 High Secondary Containment Area 0

Radiation Levels / 9 295034 Secondary Containment Ventilation 0

High Radiation / 9 295035 Secondary Containment High 0

Differential Pressure / 5 295036 Secondary Containment High 04.

84 Knowledge of the specific bases for EOPs. 4.0 1 Sump/Area Water Level / 5 18 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 0 0 0 0 1 2 Group Point Total: 3 ES-401, Page 18 of 33

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

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

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection 0 0

87 205000 Shutdown Cooling Mode Recirculation loop high temperature: Plant-Specific 3.3 1 1

206000 HPCI 0 207000 Isolation (Emergency) 0 Condenser 02.

89 209001 LPCS Ability to apply Technical Specifications for a system. 4.7 1 40 209002 HPCS System not utilized at Dresden 0 0

86 211000 SLC Inadequate system flow 3.4 1 4

212000 RPS 0 215003 IRM 0 215004 Source Range Monitor 0 215005 APRM / LPRM 0 217000 RCIC System not utilized at Dresden 0 218000 ADS 0 223002 PCIS/Nuclear Steam Supply 0

Shutoff 239002 SRVs 0 259002 Reactor Water Level Control 0 Ability to interpret control room indications to verify the

02. status and operation of a system, and understand how 88 261000 SGTS 4.4 1 44 operator actions and directives affect plant and system conditions.

04. Knowledge of the organization of the operating procedures 90 262001 AC Electrical Distribution 4.3 1 05 network for normal, abnormal, and emergency evolutions.

262002 UPS (AC/DC) 0 263000 DC Electrical Distribution 0 264000 EDGs 0 300000 Instrument Air 0 400000 Component Cooling Water 0 0

K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 3 Group Point Total: 5 ES-401, Page 19 of 33

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

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

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 0 201002 RMCS 0 201003 Control Rod and Drive Mechanism 0 201004 RSCS System not utilized at Dresden 0 201005 RCIS System not utilized at Dresden 0 201006 RWM 0 202001 Recirculation 0 202002 Recirculation Flow Control 0 0

91 204000 RWCU 3 Flow control valve failure 2.9 1 214000 RPIS 0 215001 Traversing In-core Probe 0 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling Mode 0 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode 0 0

93 233000 Fuel Pool Cooling/Cleanup 9 A.C. electrical power failures 2.9 1 234000 Fuel Handling Equipment 0 239001 Main and Reheat Steam 0 239003 MSIV Leakage Control 0 Ability to evaluate plant performance and make operational 01.

92 241000 Reactor/Turbine Pressure Regulator judgments based on operating characteristics, reactor 4.7 1 07 behavior, and instrument interpretation.

245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 286000 Fire Protection 0 288000 Plant Ventilation 0 290001 Secondary CTMT 0 290003 Control Room HVAC 0 290002 Reactor Vessel Internals 0 0

K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 20 of 33

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Dresden Date of Exam:8/6/2012 RO SRO-Only Category K/A # Topic Q# IR # IR #

67 2.1. 20 Ability to interpret and execute procedure steps. 4.6 1 66 2.1. 25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9 1 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high 75

1. 2.1. 26 temperature, high pressure, caustic, chlorine, oxygen and hydrogen). 3.4 1 Conduct of 2.1.

Operations 2.1.

94 2.1. 42 Knowledge of new and spent fuel movement procedures. 3.4 1 Subtotal 3 1 68 2.2. 03 Knowledge of the design, procedural, and operational differences between units. 3.8 1 69 2.2. 20 Knowledge of the process for managing troubleshooting activities. 2.6 1

2. 2.2.

Equipment 2.2.

Control 100 2.2. 23 Ability to track Technical Specification limiting conditions for operations. 4.6 1 95 2.2. 37 Ability to determine operability and/or availability of safety related equipment. 4.6 1 Subtotal 2 2 71 2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2 1 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 70 2.3. 14 or emergency conditions or activities. 3.4 1

3. 2.3.

Radiation 2.3.

Control Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 96 2.3. 05 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 99 2.3. 06 Ability to approve release permits. 3.8 1 Subtotal 2 2 Knowledge of the bases for prioritizing emergency procedure implementation during 73 2.4. 23 emergency operations. 3.4 1 74 2.4. 28 Knowledge of procedures relating to a security event. 3.2 1 72 4. 2.4. 32 Knowledge of operator response to loss of all annunciators. 3.6 1 Emergency Procedures 2.4.

/ Plan 98 2.4. 40 Knowledge of SRO responsibilities in emergency plan implementation. 4.5 1 97 2.4. 41 Knowledge of the emergency action level thresholds and classifications. 4.6 1 Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33