ML11363A124

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2011 Dresden Nuclear Power Station Initial License Examination Outline Form Es 401-1 Rev 1 and Form Es 401-3 Rev 1
ML11363A124
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 03/29/2011
From:
NRC/RGN-III
To:
Exelon Generation Co
Shared Package
ML11104A075 List:
References
Download: ML11363A124 (10)


Text

ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Dresden Date of Exam: 3/7/11 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 4 3 3 3 4 3 20 4 3 7 Emergency &

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

Plant 2 1 1 1 1 1 1 1 1 1 2 1 12 0 2 1 3 Systems Tier Totals 4 3 3 4 3 4 3 3 3 5 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 2 3 2 2 1 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 17 of 34

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 17 Reactor power 3.8 1 Core Flow Circulation / 1 & 4 6 0

54 295003 Partial or Complete Loss of AC / 6 Electrical bus divisional separation 3.1 1 4

0 7 295004 Partial or Total Loss of DC Pwr / 6 Reactor SCRAM: Plant-Specific 3.1 1 3

Ability to perform without reference to procedures those actions 04.

21 295005 Main Turbine Generator Trip / 3 that require immediate operation of system components and 4.6 1 49 controls.

0 25 295006 SCRAM / 1 Reactor water level control system 3.8 1 2

0 59 295016 Control Room Abandonment / 7 Isolation/emergency condenser(s): Plant-Specific 4.0 1 9

02.

24 295018 Partial or Total Loss of CCW / 8 Knowledge of surveillance procedures. 3.7 1 12 01.

46 295019 Partial or Total Loss of Inst. Air / 8 Ability to interpret and execute procedure steps. 4.6 1 20 0

31 295021 Loss of Shutdown Cooling / 4 Alternate heat removal methods 3.7 1 4

0 41 295023 Refueling Acc / 8 Interlocks associated with fuel handling equipment 3.4 1 2

0 61 295024 High Drywell Pressure / 5 Emergency generators 3.7 1 6

0 29 295025 High Reactor Pressure / 3 Pressure effects on reactor power 3.9 1 1

295026 Suppression Pool High Water 0 64 Suppression pool level 3.8 1 Temp. / 5 2 295027 High Containment Temperature / 5 Not Applicable To Dresden 0 0

19 295028 High Drywell Temperature / 5 Reactor water level measurement 3.5 1 1

0 27 295030 Low Suppression Pool Wtr Lvl / 5 Emergency depressurization 3.8 1 1

0 1 295031 Reactor Low Water Level / 2 Reactor water level 4.6 1 1

295037 SCRAM Condition Present and 1

67 Reactor Power Above APRM Downscale or Alternate boron injection methods: Plant-Specific 3.4 1 3

Unknown / 1 0

33 295038 High Off-site Release Rate / 9 Protection of the general public 4.2 1 2

0 49 600000 Plant Fire On Site / 8 Need for pressurizing control room (recirculating mode) 2.5 1 6

700000 Generator Voltage and Electric Grid 0 30 Operating point on the generator capability curve 3.5 1 Disturbances / 6 1 K/A Category Totals: 4 3 3 3 4 3 Group Point Total: 20

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 0

13 295002 Loss of Main Condenser Vac / 3 Condenser circulating water system 3.1 1 8

295007 High Reactor Pressure / 3 0 0

44 295008 High Reactor Water Level / 2 Reactor water level control: Plant-Specific 3.7 1 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 0

48 295013 High Suppression Pool Temp. / 5 Suppression pool cooling operation 3.6 1 1

0 55 295014 Inadvertent Reactivity Addition / 1 Abnormal reactivity additions. 3.8 1 6

0 47 295015 Incomplete SCRAM / 1 Rod worth minimizer: Plant-Specific 2.5 1 5

295017 High Off-site Release Rate / 9 0 295020 Inadvertent Cont. Isolation / 5 & 7 0 295022 Loss of CRD Pumps / 1 0

01. Ability to use plant computers to evaluate system or component 73 295029 High Suppression Pool Wtr Lvl / 5 3.9 1 19 status.

295032 High Secondary Containment Area 0

Temperature / 5 295033 High Secondary Containment Area 0 8 Area radiation levels 3.8 1 Radiation Levels / 9 1 295034 Secondary Containment Ventilation 0

High Radiation / 9 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: 1 1 1 2 1 1 Group Point Total: 7 ES-401, Page 19 of 34

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 0 3.5; 34, 74 203000 RHR/LPCI: Injection Mode Core cooling methods; Pumps 2 2 1 4.3 0

56 205000 Shutdown Cooling SDC/RHR pump flow 3.3 1 2

0 0 Resetting turbine trips: BWR-2, 3, 4; Condensate storage 4.2; 50, 5 206000 HPCI 2 3 3 tank level: BWR-2, 3, 4 3.5 207000 Isolation (Emergency) 04. Knowledge of annunciator alarms, indications, or response 14 4.2 1 Condenser 31 procedures.

0 53 209001 LPCS Initiation logic 2.9 1 3

209002 HPCS Not Applicable To Dresden 0 0

28 211000 SLC Tank heater operation 2.7 1 7

0 52 212000 RPS RPS motor-generator set failure 3.7 1 1

0 40 215003 IRM RPS 3.9 1 1

0 18 215004 Source Range Monitor RPS status 3.6 1 3

0 35 215005 APRM / LPRM Inoperative trip (all causes) 3.6 1 3

217000 RCIC Not Applicable To Dresden 0 0

36 218000 ADS RHR/LPCI: Plant-Specific 4.0 1 1

223002 PCIS/Nuclear Steam Supply 0 Manual defeating of selected isolations during specified 42 3.3 1 Shutoff 8 emergency conditions 0

62 239002 SRVs SRV solenoids 2.8 1 1

0 60 259002 Reactor Water Level Control Reactor water level 3.8 1 1

0 0 3.7; 65, 10 261000 SGTS Automatic system initiation; System flow 2 1 1 3.2

01. Ability to locate and operate components, including local 23 262001 AC Electrical Distribution 4.4 1 30 controls.

0 68 262002 UPS (AC/DC) Static inverter 2.7 1 3

0 71 263000 DC Electrical Distribution A.C. electrical distribution 3.2 1 1

0 72 264000 EDGs Synchroscope 3.4 1 2

0 1 2.7; 70, 22 300000 Instrument Air Service air; Breakers, relays and disconnects 2 2 2 2.9 0 0 2.9; 9, 75 400000 Component Cooling Water Loads cooled by CCWS; CCW indications and control 2 1 1 3.1 0

K/A Category Totals: 3 2 2 3 2 3 2 2 2 3 2 Group Point Total: 26 ES-401, Page 20 of 34

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

57 201001 CRD Hydraulic 2 Scram valve solenoids 3.6 1 201002 RMCS 0 0

37 201003 Control Rod and Drive Mechanism 1 Stuck rod 3.4 1 201004 RSCS 0 201005 RCIS 0 201006 RWM 0 0

11 202001 Recirculation 7 Pump trips: Plant-Specific 3.3 1 202002 Recirculation Flow Control 0 0

63 204000 RWCU 4 Component cooling water systems 2.9 1 214000 RPIS 0 0

3 215001 Traversing In-core Probe 3

Isolation valves: Mark-I&II(Not-BWR1) 3.0 1 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 1 Prevention of leakage to the environment through system 51 3.3 1 Mode 0 heat exchanger: Plant-Specific 1

16 223001 Primary CTMT and Aux. 1 Temperature measurement 2.7 1 226001 RHR/LPCI: CTMT Spray Mode 0 0

66 230000 RHR/LPCI: Torus/Pool Spray Mode 1 Pumps 3.7 1 233000 Fuel Pool Cooling/Cleanup 0 234000 Fuel Handling Equipment 0 0

39 239001 Main and Reheat Steam 2 Plant air systems 3.2 1 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0

01. Knowledge of operator responsibilities during all modes of 45 245000 Main Turbine Gen. / Aux. 4.1 1 02 plant operation.

256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 0

43 271000 Offgas 8 System flow 3.1 1 272000 Radiation Monitoring 0 286000 Fire Protection 0 288000 Plant Ventilation 0 290001 Secondary CTMT 0 290003 Control Room HVAC 0 0

69 290002 Reactor Vessel Internals 3 Reactor power 3.3 1 0

K/A Category Totals: 1 1 1 1 1 1 1 1 1 2 1 Group Point Total: 12 ES-401, Page 22 of 34

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 02. Knowledge of the bases in Technical Specifications for 77 4.2 1 Core Flow Circulation / 1 & 4 25 limiting conditions for operations and safety limits.

0 Whether a partial or complete loss of A.C. power has 90 295003 Partial or Complete Loss of AC / 6 4.2 1 5 occurred 295004 Partial or Total Loss of DC Pwr / 6 0 295005 Main Turbine Generator Trip / 3 0

01. Ability to manage the control room crew during plant 92 295006 SCRAM / 1 4.8 1 06 transients.

0 97 295016 Control Room Abandonment / 7 Reactor water level 4.3 1 2

295018 Partial or Total Loss of CCW / 8 0 0 Status of safety-related instrument air system loads 100 295019 Partial or Total Loss of Inst. Air / 8 3.7 1 2 (see AK2.1-AK2.19) 295021 Loss of Shutdown Cooling / 4 0 295023 Refueling Acc / 8 0 295024 High Drywell Pressure / 5 0 295025 High Reactor Pressure / 3 0 Knowledge of criteria or conditions that require plant-295026 Suppression Pool High Water Temp. 01.

87 wide announcements, such as pump starts, reactor 3.1 1

/5 14 trips, mode changes, etc.

295027 High Containment Temperature / 5 0 295028 High Drywell Temperature / 5 0 295030 Low Suppression Pool Wtr Lvl / 5 0 295031 Reactor Low Water Level / 2 0 295037 SCRAM Condition Present 0

79 and Reactor Power Above APRM Reactor power 4.3 1 1

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 4 3 Group Point Total: 7

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 0

94 295009 Low Reactor Water Level / 2 Steam flow/feedflow mismatch 3.7 1 2

295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 0 0

88 295012 High Drywell Temperature / 5 Drywell temperature 3.9 1 1

295013 High Suppression Pool Temp. / 5 0 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 04.

89 295022 Loss of CRD Pumps / 1 Knowledge of abnormal condition procedures. 4.2 1 11 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 0

Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 0 0 0 0 2 1 Group Point Total: 3 ES-401, Page 19 of 34

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

81 205000 Shutdown Cooling Mode Recirculation loop high temperature: Plant-Specific 3.3 1 1

206000 HPCI 0 207000 Isolation (Emergency) 04.

83 Knowledge of EOP mitigation strategies. 4.7 1 Condenser 06 209001 LPCS 0 209002 HPCS 0 0

96 211000 SLC Failure of explosive valve to fire 3.9 1 2

212000 RPS 0 215003 IRM 0 215004 Source Range Monitor 0 0

85 215005 APRM / LPRM Recirculation flow channels flow mismatch 3.4 1 7

217000 RCIC 0 218000 ADS 0 223002 PCIS/Nuclear Steam Supply 0

Shutoff 239002 SRVs 0 259002 Reactor Water Level Control 0 261000 SGTS 0 262001 AC Electrical Distribution 0 262002 UPS (AC/DC) 0 01.

80 263000 DC Electrical Distribution Ability to explain and apply system limits and precautions. 4.0 1 32 264000 EDGs 0 300000 Instrument Air 0 400000 Component Cooling Water 0 0

K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 20 of 34

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 0 201005 RCIS 0 201006 RWM 0 202001 Recirculation 0 202002 Recirculation Flow Control 0 204000 RWCU 0 Ability to recognize abnormal indications for system operating 04.

99 214000 RPIS parameters that are entry-level conditions for emergency and 4.7 1 04 abnormal operating procedures.

215001 Traversing In-core Probe 0 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 0

Mode 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode 0 0

91 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 241000 Reactor/Turbine Pressure Regulator 0 245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 0

76 259001 Reactor Feedwater 1 Pump trip 3.7 1 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 21 of 34

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Dresden Date of Exam:3/7/11 RO SRO-Only Category K/A # Topic Q# IR # IR #

4 2.1. 17 Ability to make accurate, clear, and concise verbal reports. 3.9 1 Ability to use procedures to determine the effects on reactivity of plant changes, such as 12 2.1. 43 reactor coolant system temperature, secondary plant, fuel depletion, etc. 4.1 1

1. 2.1.

Conduct of 2.1.

Operations Knowledge of individual licensed operator responsibilities related to shift staffing, such as 86 2.1. 04 medical requirements, no-solo operation, maintenance of active license status, 3.8 1 10CFR55, etc.

82 2.1. 40 Knowledge of refueling administrative requirements. 3.9 1 Subtotal 2 2 6 2.2. 03 Knowledge of the design, procedural, and operational differences between units. 3.8 1 26 2.2. 22 Knowledge of limiting conditions for operations and safety limits. 4.0 1 Ability to interpret control room indications to verify the status and operation of a system, 58 2. 2.2. 44 and understand how operator actions and directives affect plant and system conditions. 4.2 1 Equipment 2.2.

Control 78 2.2. 23 Ability to track Technical Specification limiting conditions for operations. 4.6 1 95 2.2. 35 Ability to determine Technical Specification Mode of Operation. 4.5 1 Subtotal 3 2 15 2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2 1 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 32 2.3. 12 containment entry requirements, fuel handling responsibilities, access to locked high- 3.2 1 radiation areas, aligning filters, etc.

3. 2.3.

Radiation 2.3.

Control 2.3.

84 2.3. 11 Ability to control radiation releases. 4.3 1 Subtotal 2 1 Knowledge of system set points, interlocks and automatic actions associated with EOP 2 2.4. 02 entry conditions. 4.5 1 20 2.4. 14 Knowledge of general guidelines for EOP usage. 3.8 1 38 4. 2.4. 32 Knowledge of operator response to loss of all annunciators. 3.6 1 Emergency Procedures 2.4.

93 / Plan Knowledge of facility protection requirements, including fire brigade and portable fire 2.4. 26 fighting equipment usage. 3.6 1 Knowledge of events related to system operation/status that must be reported to internal 98 2.4. 30 organizations or external agencies, such as the State, the NRC, or the transmission 4.1 1 system operator.

Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 27 of 34