ML12132A328

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2012 Dresden Nuclear Power Station Initial License Examination Outline ES-401-1, ES-401-3
ML12132A328
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 04/05/2012
From: David Reeser
Operations Branch III
To: Nelson J
Exelon Generation Co
Shared Package
ML11354A121 List:
References
Download: ML12132A328 (10)


Text

ES-401 BWR Examination Outline FORM ES-401-1 Facility 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

Total Total 1

3 3

3 4

4 3

20 7

2 2

1 1

1 1

1 7

3 Tier 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 3

Tier Totals 4

3 4

4 4

4 3

3 3

3 3

38 8

1 2

3 4

1 2

2 2

Note: 1.

Note: 2.

Note: 3.

Note: 4.

Note: 5.

Note: 6.

Note: 7.*

Note: 8.

Note: 9.

Tier Group SRO-Only Points

2.

Plant Systems

1.

Emergency &

Abnormal Plant Evolutions 1

4 4

G*

RO K/A Category Points 7

10 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).

3 2

4 3

A2 2

3 1

4 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.

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.

6 3

N/A N/A 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.

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.

3. Generic Knowledge and Abilities Categories 1

2 2

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.

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

3 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.

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)

Q#

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 52 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0

6 Nuclear boiler instrumentation 3.2 1

53 295003 Partial or Complete Loss of AC / 6 0

3 Battery status: Plant-Specific 3.2 1

44 295004 Partial or Total Loss of DC Pwr / 6 0

1 Battery charger 3.1 1

39 295005 Main Turbine Generator Trip / 3 0

1 Pressure effects on reactor power 4.0 1

55 295006 SCRAM / 1 02.

04 Ability to explain the variations in control board layouts, systems, instrumentation, and procedural actions between units at a facility.

3.6 1

50 295016 Control Room Abandonment / 7 0

3 RPIS 3.0 1

58 295018 Partial or Total Loss of CCW / 8 0

1 Component temperatures 3.3 1

45 295019 Partial or Total Loss of Inst. Air / 8 0

2 Standby air compressor operation 3.5 1

56 295021 Loss of Shutdown Cooling / 4 04.

47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

4.2 1

51 295023 Refueling Acc / 8 0

3 Airborne contamination levels 3.3 1

43 295024 High Drywell Pressure / 5 1

8 Ventilation 3.3 1

48 295025 High Reactor Pressure / 3 0

7 ARI/RPT/ATWS: Plant-Specific 4.1 1

54 295026 Suppression Pool High Water Temp. / 5 04.

49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

4.6 1

295027 High Containment Temperature / 5 0

42 295028 High Drywell Temperature / 5 0

3 Reactor water level indication 3.6 1

57 295030 Low Suppression Pool Wtr Lvl / 5 0

3 HPCS: Plant-Specific 3.4 1

47 295031 Reactor Low Water Level / 2 0

4 Steam cooling 4.0 1

41 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 0

3 Boron effects on reactor power (SBLC) 4.2 1

49 295038 High Off-site Release Rate / 9 0

1 Stack-gas monitoring system: Plant-Specific 3.9 1

40 600000 Plant Fire On Site / 8 0

2 Fire Fighting 2.9 1

46 700000 Generator Voltage and Electric Grid Disturbances / 6 0

2 Actions contained in abnormal operating procedure for voltage and grid disturbances 3.6 1

K/A Category Totals:

3 3

3 4

4 3

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

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)

Q#

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295002 Loss of Main Condenser Vac / 3 0

295007 High Reactor Pressure / 3 0

295008 High Reactor Water Level / 2 0

62 295009 Low Reactor Water Level / 2 0

4 Reactor water cleanup 2.7 1

295010 High Drywell Pressure / 5 0

295011 High Containment Temp / 5 0

295012 High Drywell Temperature / 5 0

295013 High Suppression Pool Temp. / 5 0

295014 Inadvertent Reactivity Addition / 1 0

59 295015 Incomplete SCRAM / 1 0

4 Reactor pressure: Plant-Specific 3.8 1

60 295017 High Off-site Release Rate / 9 1

2 Standby gas treatment/FRVS 3.4 1

63 295020 Inadvertent Cont. Isolation / 5 & 7 0

4 Reactor pressure 3.9 1

61 295022 Loss of CRD Pumps / 1 0

2 CRDM high temperature 2.9 1

295029 High Suppression Pool Wtr Lvl / 5 0

64 295032 High Secondary Containment Area Temperature / 5 01.

19 Ability to use plant computers to evaluate system or component status.

3.9 1

295033 High Secondary Containment Area Radiation Levels / 9 0

65 295034 Secondary Containment Ventilation High Radiation / 9 0

1 Personnel protection 3.8 1

295035 Secondary Containment High Differential Pressure / 5 0

295036 Secondary Containment High Sump/Area Water Level / 5 0

500000 High CTMT Hydrogen Conc. / 5 0

K/A Category Totals:

2 1

1 1

1 1

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

ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant 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 G

K/A Topic(s)

IR 20 203000 RHR/LPCI: Injection Mode 0

5 Manual initiation controls 4.3 1

13 205000 Shutdown Cooling 0

3 Recirculation loop temperatures 3.3 1

4 206000 HPCI 0

1 System valves: BWR-2, 3, 4 3.2 1

1 207000 Isolation (Emergency)

Condenser 1

0 Plant air systems: BWR-2, 3 3.0 1

21 209001 LPCS 04.

11 Knowledge of abnormal condition procedures.

4.0 1

209002 HPCS 0

7 211000 SLC 0

6 Core plate differential pressure indication 2.6 1

2 212000 RPS 0

4 A.C. electrical distribution 3.4 1

9 215003 IRM 0

3 Changing detector position 3.0 1

25 14 215004 Source Range Monitor 0

4 0

5 Detectors; SCRAM, rod block, and period alarm trip setpoints 2.9; 3.6 2

15 215005 APRM / LPRM 0

1 Power supply degraded 2.7 1

217000 RCIC 0

3 218000 ADS 0

1 ADS logic 3.1 1

26 8

223002 PCIS/Nuclear Steam Supply Shutoff 2

8 0

2 Containment nitrogen inerting system; Testability 2.7; 2.7 2

16 239002 SRVs 0

2 Leaky SRV 3.1 1

18 259002 Reactor Water Level Control 0

1 Runout flow control: Plant-Specific 3.0 1

17 261000 SGTS 0

3 Valve operation 3.0 1

11 262001 AC Electrical Distribution 0

1 D.C. power 3.1 1

6 262002 UPS (AC/DC) 0 5

Rod worth minimizer: Plant-Specific 2.9 1

24 19 263000 DC Electrical Distribution 0

1 0

2 A.C. electrical distribution; Battery voltage indicator: Plant-Specific 3.3; 3.2 2

23 10 264000 EDGs 0

7 0

5 Local operation and control; Paralleling A.C. power sources 3.3; 3.4 2

5 300000 Instrument Air 0

2 Systems having pneumatic valves and controls 3.3 1

12 22 400000 Component Cooling Water 0

5 01.

32 Motors ; Ability to explain and apply system limits and precautions.

2.8; 3.8 2

0 K/A Category Totals:

3 2

3 3

2 3

2 2

2 2

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

ES-401-1 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant 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 G

K/A Topic(s)

IR 31 201001 CRD Hydraulic 0

8 Solenoid operated valves 2.5 1

201002 RMCS 0

27 201003 Control Rod and Drive Mechanism 0

3 RPIS 3.1 1

201004 RSCS 0

201005 RCIS 0

201006 RWM 0

38 202001 Recirculation 0

2 Jet pump operation: BWR-3, 4, 5, 6 3.1 1

202002 Recirculation Flow Control 0

204000 RWCU 0

30 214000 RPIS 0

1 Reed switch locations 3.0 1

215001 Traversing In-core Probe 0

36 215002 RBM 0

1 IRM/RBM recorder/switch: BWR-3, 4, 5 2.8 1

216000 Nuclear Boiler Inst.

0 28 219000 RHR/LPCI: Torus/Pool Cooling Mode 0

1 Valves 2.5 1

34 223001 Primary CTMT and Aux.

1 0

High drywell temperature 3.6 1

226001 RHR/LPCI: CTMT Spray Mode 0

32 230000 RHR/LPCI: Torus/Pool Spray Mode 0

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

33 245000 Main Turbine Gen. / Aux.

0 8

Generator output voltage/reactive load 2.5 1

256000 Reactor Condensate 0

37 259001 Reactor Feedwater 04.

31 Knowledge of annunciator alarms, indications, or response procedures.

4.2 1

268000 Radwaste 0

271000 Offgas 0

272000 Radiation Monitoring 0

29 286000 Fire Protection 0

2 Personnel protection 3.2 1

35 288000 Plant Ventilation 0

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

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)

Q#

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0

295003 Partial or Complete Loss of AC / 6 0

295004 Partial or Total Loss of DC Pwr / 6 0

79 295005 Main Turbine Generator Trip / 3 02.

39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

4.5 1

295006 SCRAM / 1 0

295016 Control Room Abandonment / 7 0

77 295018 Partial or Total Loss of CCW / 8 0

2 Cooling water temperature 3.2 1

81 295019 Partial or Total Loss of Inst. Air / 8 04.

08 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

4.5 1

82 295021 Loss of Shutdown Cooling / 4 04.

09 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

4.2 1

76 295023 Refueling Acc / 8 0

5 Entry conditions of emergency plan 4.6 1

295024 High Drywell Pressure / 5 0

295025 High Reactor Pressure / 3 0

295026 Suppression Pool High Water Temp.

/ 5 0

295027 High Containment Temperature / 5 0

78 295028 High Drywell Temperature / 5 0

1 Drywell temperature 4.1 1

295030 Low Suppression Pool Wtr Lvl / 5 0

295031 Reactor Low Water Level / 2 0

80 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 04.

35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

4.0 1

295038 High Off-site Release Rate / 9 0

600000 Plant Fire On Site / 8 0

700000 Generator Voltage and Electric Grid Disturbances / 6 0

K/A Category Totals:

0 0

0 0

3 4

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

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)

Q#

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295002 Loss of Main Condenser Vac / 3 0

295007 High Reactor Pressure / 3 0

85 295008 High Reactor Water Level / 2 04.

41 Knowledge of the emergency action level thresholds and classifications.

4.6 1

295009 Low Reactor Water Level / 2 0

295010 High Drywell Pressure / 5 0

295011 High Containment Temp / 5 0

295012 High Drywell Temperature / 5 0

83 295013 High Suppression Pool Temp. / 5 0

1 Suppression pool temperature 4.0 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 Temperature / 5 0

295033 High Secondary Containment Area Radiation Levels / 9 0

295034 Secondary Containment Ventilation High Radiation / 9 0

295035 Secondary Containment High Differential Pressure / 5 0

84 295036 Secondary Containment High Sump/Area Water Level / 5 04.

18 Knowledge of the specific bases for EOPs.

4.0 1

500000 High CTMT Hydrogen Conc. / 5 0

K/A Category Totals:

0 0

0 0

1 2

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

ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant 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 G

K/A Topic(s)

IR 203000 RHR/LPCI: Injection 0

87 205000 Shutdown Cooling Mode 0

1 Recirculation loop high temperature: Plant-Specific 3.3 1

206000 HPCI 0

207000 Isolation (Emergency)

Condenser 0

89 209001 LPCS 02.

40 Ability to apply Technical Specifications for a system.

4.7 1

209002 HPCS 0

86 211000 SLC 0

4 Inadequate system flow 3.4 1

212000 RPS 0

215003 IRM 0

215004 Source Range Monitor 0

215005 APRM / LPRM 0

217000 RCIC 0

218000 ADS 0

223002 PCIS/Nuclear Steam Supply Shutoff 0

239002 SRVs 0

259002 Reactor Water Level Control 0

88 261000 SGTS 02.

44 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 diti 4.4 1

90 262001 AC Electrical Distribution 04.

05 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

4.3 1

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 5

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

ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant 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 G

K/A Topic(s)

IR 201001 CRD Hydraulic 0

201002 RMCS 0

201003 Control Rod and Drive Mechanism 0

201004 RSCS 0

201005 RCIS 0

201006 RWM 0

202001 Recirculation 0

202002 Recirculation Flow Control 0

91 204000 RWCU 0

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

93 233000 Fuel Pool Cooling/Cleanup 0

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

92 241000 Reactor/Turbine Pressure Regulator 01.

07 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor b h i

d i t

t i t t ti 4.7 1

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 3

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

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility Name:Dresden Date of Exam:8/6/2012 Q#

IR IR 67 2.1. 06 Ability to manage the control room crew during plant transients.

3.8 1

66 2.1. 25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 1

75 2.1. 26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

3.4 1

2.1.

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.

2.2.

100 2.2. 23 Ability to track Technical Specification limiting conditions for operations.

4.6 1

95 2.2. 42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

4.6 1

Subtotal 2

2 71 2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions.

3.2 1

70 2.3. 14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.4 1

2.3.

2.3.

96 2.3. 05 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 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 73 2.4. 23 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

3.4 1

74 2.4. 28 Knowledge of procedures relating to a security event.

3.2 1

72 2.4. 32 Knowledge of operator response to loss of all annunciators.

3.6 1

2.4.

98 2.4. 40 Knowledge of SRO responsibilities in emergency plan implementation.

4.5 1

97 2.4. 50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

4.0 1

Subtotal 3

2 10 7

ES-401, Page 26 of 33 Tier 3 Point Total

3.

Radiation Control

4.

Emergency Procedures

/ Plan

2.

Equipment Control RO SRO-Only Category Topic

1.

Conduct of Operations K/A #