Text

2015 Dresden Station Initial License Examination Forms ES-401-1 and ES-401-3
	ML15287A279
Person / Time
Site:	Dresden
Issue date:	04/30/2015
From:	Randy Baker; Operations Branch III
To:	; Exelon Generation Co
Shared Package
ML14337A718	List: ML15287A232; ML15287A245; ML15287A267; ML15287A279; ML15287A337; ML15287A343; ML15287A351;
References
	Download: ML15287A279 (10)
	v • d • e

ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Dresden Date of Exam: 04/06/2015 RO KIA 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 4 4 3 3 3 20 4 3 7 Emergency &

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

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 3 2 2 2 1 2 2 Note: 1. Ensure that at least two topics from every applicable KJA 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 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 KJAs 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) Kl 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 KJA 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 E/APE #I Name I Safety Function G KIA Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced 0 Knowledge of the interrelations between Partial or Complete Loss of Forced Core Flow Circulation and the following : LPCI loop se lect logic: Plant-Specific 3.2 1 Core Flow Circulation I 1 & 4 5 0 Knowledge of the reasons for the following responses as they apply to Partial or 29500 3 Partial or Complete Loss of AC I 6 Complete Loss of AC : Ground isolation 3.0 1 4

0 Ability to operate and/or monitor the following as th ey apply to Partial or Total Loss or 295004 Partial or Total Loss of DC Pwr I 6 DC Pwr: D.C. electrical distribution systems 3.3 1 1

0 Ability to determine and/or interpret the following as they apply to Main Turbine 295005 Main Turbine Generator Trip I 3 Generator Trip: Reactor pressure 3.7 1 4

04. Knowledge of system set points, interlocks and automatic actions associated 'v'hth 295006 SCRAM I 1 EOP entry conditions.

4.5 1 02 0 Knowledge of the interrelations between Control Room Abandonment and the 2950 16 Control Room Abandonment/ 7 following: Loca l control sta tions: Plant-Specific 4.0 1 2

0 Knowledge of the opera tional implications of the following concepts as they apply to 295018 Partial or Total Loss of CCW I 8 Partial or Total Loss of CCW: Effects on componenUsystem operations 3.5 1 1

0 Knowledge of the reasons for the following responses as they apply to Partial or Total 295019 Partial or Total Loss of Inst. Air I 8 Loss of Inst. Air: Standby air compressor operation 3.5 1 2

0 Knowledge of the interrelations between Loss of Shutdown Cooling and the following:

~95021 Loss of Shutdown Cooling I 4 Component cooling water systems: Plant-Specific

3. 0 1 4

0 Knowledge of the reasons for the following responses as they apply to Refueling 295023 Refueling Ace I 8 Accidents: Interlocks associated with fuel handling eq uipment 3.4 1 2

1 Ability to operate and/or monitor the following as they apply to High Drywell Pressure:

295024 High Drywell Pressure I 5 Suppression pool coating 3.6 1 3

0 Ability to determine and/or interpret the following as they apply to High Reactor 295025 High Reactor Pressure I 3 Pressure: Suppression pool level 3.9 1 4

295026 Suppression Pool High Wa.ter 01 .

Ability to interpret reference materials, such as graphs. curves. tables. etc. 3.9 1 Temp. I 5 25 295027 High Containment Temperature I 5 0 0 Knowledge of the operational implications of the following concepts as they apply to 295028 High Drywell Temperature I 5 High Ory.yell Temperature: Rea ctor water level measurement 3.5 1 1

0 Knowledge of the interrelations between Low Suppression Pool Wtr Lvl and the 295030 Low Suppression Pool Wtr Lvl I 5 following: HPCI: Plant-Specific 3.8 1 1

0 Knowledge of the reasons for the following responses as they apply to Reactor Low 295031 Reactor Low Water Level I 2 Water Level: Emergency depressurization 4.2 1 5

295037 SCRAM Condition Present and Ability to operate and/or monitor the following as they apply to SCRAM Condition 0

Reactor Power Above APRM Downscale or Present and Reactor Povver Above APRM Downscale or Unknown: Neutron 4.1 1 6 monitoring system Unknown I 1 0 Ability to determine and/or interpret the following as they apply to High Off-site 295038 High Off-site Release Rate I 9 Release Rate: Radiation levels 3.5 1 3

01.

~ 00000 Plant Fire On Site I8 Ability to use plant computers to evalua te system or component status. 3.9 1 19 700000 Generator Voltage and Electric Grid 0 Knowledge of the operational implications of th e following concepts as they apply to Generator Voltage and Electric Grid Disturbances: Over-excitation 3.3 1 Disturbances I 6 2 KJA Category Totals: 3 4 4 3 3 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 E/APE # I Name I Safety Function G KIA Topic(s) IR #

1 2 3 1 2 0 Ability to operate and/or monitor the following as they apply to Loss of Main 295002 Loss of Main Condenser Vac I 3 Condenser Vac: Offgas system 2.9 1 2

0 Knowledge of the interrelations between High Reactor Pressure and the following :

295007 High Reactor Pressure I 3 RHR/LPCI: Plant-Specific 3.1 1 3

295008 High Reactor Water Level / 2 0 295009 Low Reactor Water Level/ 2 0 295010 High Drywell Pressure / 5 0 295011 High Containment Temp I 5 0 295012 High Drywell Temperature / 5 0 295013 High Suppression Pool Temp. / 5 0 02.

295014 Inadvertent Reactivity Addition/ 1 Kn olN!edge of conditions and limitations in the facility license. 3.6 1 38 295015 Incomplete SCRAM / 1 0 295017 High Off-site Release Rate / 9 0 0 Knowledge of the reasons for the following responses as they apply to Inadvertent 295020 Inadvertent Cont. Isolation I 5 & 7 Cont lsolation: Reactor water level response 3.8 1 5

0 Ability to determine and/or interpret the following as they apply to Loss of CRD 295022 Loss of CRD Pumps / 1 Pumps: CRD system status 3.3 1 2

295029 High Suppression Pool Wtr Lvl I 5 0 Knowledge of the operational implications of the following concepts as they apply to 295032 High Secondary Containment Area 0

3. 5 1 rremperature I 5 3 High Secondary Containment Area Temperature : Secondary containment leakage detection: Plant-Specific 1295033 High Secondary Containment Area 0

Radiation Levels I 9 295034 Secondary Containment Ventilation 0

High Radiation I 9 295035 Seco11dary Containment High 0 Knowledge of the operational implications of the following concepts as they apply to Secondary Containment High Differential Pressure: Secondary containment integrity 3.9 1 Differential Pressure I 5 1 295036 Secondary Containment High 0

Sump/Area Water Level I 5 500000 High CTMT Hydrogen Cone. I 5 0 KIA Category Tota ls: 2 1 1 1 1 1 Gro up Point Tota l: 7 ES-401 , Page 18 of 33

ES-401 4 Form ES-401-1 ES-40 1 BWR Examination Outli ne Form ES-401 -1 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A System #I Name G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 0 Knowledge of the operational implications of the following concepts as they 203 000 RHR/LPCI: Injection Mode apply to RHRJLPC I: Injection Mode: Core cooling methods

3. 5 1 2

0 Knowledge of the effect that a loss or malfunction of the following will have on 205000 Shutdown Cooling the Shutdown Cooli ng: D.C. electrical power 2.7 1 2

Ability to predict and/or monitor changes in parameters associated with operating the HPC I controls including: Suppression pool temperature: BWR-2, 0 0 3, 4; Ability to (a) predict the Impacts of the following on the HPCI; and (b) 4.1; 206 0 00 HPCI g based on those predictions, use procedures to correct. control, or mitigate the 2

5 3. 5 consequences of those abnormal conditions or operations: Low condensate storaae tank level: BWR-2, 3, 4 Ability to (a) predict the impacts of the following on the Isolation (Emergency) 207000 Isolation (Emergency) 0 Condenser; and (b ) based on those predictions. use procedures to correct.

control , or mitigate the consequences of those abnormal conditions or 3.5 1 Condenser 7 operations : Valve closures: BWR-2, 3 Knowledge of the operational implications of the following concepts as they 0 0 2.6; 209 0 01 LPCS apply to LPCS: Indications of pump cavitation; Ability to monitor automatic 2 1 3 operations of the LPCS including: System pressure 3.5 20900 2 HPCS 0 A bility to monitor automatic operations of the SLC including: Explosive valves 0 0 3.8; 211000 SLC indicating lights: Plant-Specific; Ability to manually operate and/or monitor in 2 3 5 the control room : Flow indication: P lant-Specific 4. 1 01.

212000 RPS Ability to locate and operate components. including loca l controls . 4.4 1 30 0 Knowledge of the physical connections and/or cause-effect relationships 215003 IRM between IRM and the following: RPS 3.9 1 1

Knowledge of electrica l power supplies to the following: SRM 0 0 2.6; 215 004 Source Range Monitor channels/detectors ; Knowledge of Source Range Monitor design feature(s) 2 1 3 andfor interlocks which provide for the following: Gamma compensation 2.4 0 Knowledge of the effect that a loss or malfunction of the APRM I LPRM will 215005 APRM I LPRM have on following: IRM: Plant-Specific 3.5 1 6

217000 RCIC 0 0 Knowledge of ADS design fea tu re(s) and/or interlocks w hich provide for the 218000 ADS following: ADS logic control 3.8 1 3

223002 PCIS/Nuclea r Steam Supply 0 Knowledge of the effect that a toss or malfunction of the following will have on the PCIS/Nuclear Steam Supply Shutoff: Containment instrumentation 3.0 1 Shutoff 5 0 K nowledge of the operational implications of the following concepts as they 239002 SRVs apply to SRVs: Tai l pipe tem perature monitoring 3.3 1 4

0 Ability to predict and/or monitor changes in pa rameters associated with 259002 Reactor Water Level Control o perating the Reactor Water Level Control controls including: Reactor power 3.8 1 3

Ability to (a) predict the impacts of the following on the SGT S; and (b) based 1 on those predictions, use procedures to correct. control, or mitigate the 261000 SGTS consequences of those abnormal conditions or operations : Hig h secondary 3.4 1 3

containment ventilation exhaust radiation Knowledge of the effect that a loss or malfunction of the following will have on 0 0 3.1; 262001 AC Electrica l Distri bution the AC Electrical Distribution: D.C. power; Abi lity to monitor automatic 2 1 4 operations of the AC Electrical Distribution including: Load sequencing 3.4 0 Abi lity to manually operate and/or monitor in the control room : Transfer from 262002 UPS (AC/DC) alternative source to preferred source 2.8 1 1

02.

263000 DC Electrical Distribution Knowledge of surveillance procedu res . 3.7 1 12 0 Knowledge of the physical connections and/or cause-effect relationships 264000 EDGs between EDGs and the following: Starting system 3.2 1 6

0 Knowledge of electrical power supplies to the following : Instrument air 300000 Instrument Air compressor 2.8 1 1

0 Knowledge of the effect that a loss or malfunction of the Component Cooling 400000 Component Cooling Water Water will have on following: Loads cooled by CCWS 2.9 1 1

Category Totals: 2 2 2 2 3 3 2 3 3 2 2 Group Point Tota l: 26 ES-401, Page 19 of 33

ES-401 -1 5 Form ES-401-1 ES-401 B WR E xami nation Outline Form E S -401-1 Plant Systems - T ier 2/Group 2 (RO)

K K K K K K A A A A Syste m # I N ame 1 2 3 4 6 1 2 3 4 G KIA Topic(s) IR #

5 0 Ability to manually operate and/or monitor in the control room : Drive water 201001 CRD Hydraulic 3. 1 1 4 header pressure control valve 201002 RMCS 0

,.,,,,.1 1u.., . ........... . ,.,, .., .... , ' ""'" ' ""' .... ,, ...., ,,"t:l' ... .. n .., ....... .......... ... .................. ............ .

0 201003 Control Rod and Drive Mechanism operating the Control Rod and Drive Mechanism controls including: CRD drive 2.8 1 2

201 004 RSCS 0 201005 RCIS 0 0 Ability to monitor automatic operatlons of the RWM inclu ding: System window 201006 RWM 3.2 1 1 and light indication: P-Spec(Not-BWR6) 202001 Recirculation 0 202002 Recirculation Flow Control 0 204000 RWCU 0 214000 RPI S 0 215001 Traversing In-core Probe 0 Ability to (a) predict the impacts of the following on the RBM: and (b) based on 0 those predictions, use procedures to correct, control , or mitigate the 215002 RBM 3 .1 1 3 consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3, 4, 5 216000 Nuclear Boiler Inst. 0 Knowledge of th e physical connections and/or cause-effect relationships 0

219000 RHR/LPCI: Torus/Pool Cooling Mode between RHR/LPCI : Torus/Pool Cooling Mode and the following: A.G. 3 .5 1 5

electrical oower 1 Knowledge of the effect that a loss or malfunction of the following will have on 223001 Primary CTMT and Aux. 3 .0 1 1 the Primary CTMT and Aux.: A.C. electrical distribution 226001 RHR/LPCI : CTMT Spray Mode 0 01 . Ability to pertorm specific system and integrated plant procedures during all 230000 RHR/LPCI: Torus/Pool Spray Mode 4.3 1 23 modes of plant operation .

0 Knowledge of Fuel Pool Cooling/Cleanup design feature(s) and/or interlocks 233000 Fuel Pool Cooling/Cleanup 7 which provide for the following: Supplemental heat removal capability 2.7 1 234000 Fuel Handling Equipment 0 239001 Main and Reheat Steam 0 239003 MSIV Leakage Control 0 241000 Reactor/T urbine Pressure Regulator 0 245000 Main Turbine Gen. I Aux. 0 256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwa ste 0 Ability to (a) predict the impacts of the following on the Offgas; and (b) based 1 on those predictions, use procedures to correct. control. or mitigate the 271000 Offgas 2.8 1 1 consequences of th ose abnormal conditions or operations: Offgas system low flow 0 Knowledge of electrical power supplies to the following: Main steamline 272000 Radiation Monitoring 2.5 1 1 radiation monitors 0 Knowledge of the operational implications of the following concepts as they 286000 Fire Protection 2 .6 1 2 apply to Fire Protection : Effect of Halon on fires: Plant-Specific 288000 Plant Ventilation 0 0 Knowledge of the effect that a loss or malfunction of th e Secondary CTMT will 290001 Secondary CTMT 4 .0 1 1 have on following: Off-site radioactive release rates 290003 Control Room HVAC 0 290002 Reactor Vessel Internals 0 KIA Category Totals: 1 1 1 1 1 1 1 2 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 E/APE #I Name I Safety Function G KIA Topic(s) IR #

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

Core Flow Circulation I 1 & 4 0 Ability to determine and/or interpret the following as they apply to Partial 295003 Partial or Complete Loss of AC I 6 3.7 1 1 or Complete Loss of AC: Cause of partial or complete loss of A.G. power 0 Ability to determine and/or interpret the following as they apply to Partial 295004 Partial or Total Loss of DC Pwr I 6 3.6 1 1 or Total Loss of DC Pwr: Cause of partial or complete loss of D.C. power Ability to interpret control room indications to verify the status and 02.

295005 Main Turbine Generator Trip I 3 operation of a system, and understand how operator actions and 4.4 1 44 directives affect plant and system conditions.

295006 SCRAM I 1 0 295016 Control Room Abandonment I 7 0

~95018 Partial or Total Loss of CCW I8 0 0 Ability to determine and/or interpret the following as they apply to Partial 295019 Partial or Total Loss of Inst. Air I 8 3.6 1 1 or Total Loss of Inst. Air: Instrument air system pressure 295021 Loss of Shutdown Cooling I 4 0 295023 Refueling Ace I 8 0 295024 High Drywell Pressure I 5 0 295025 High Reactor Pressure I 3 0 295026 Suppression Pool High Water 0

Temp . I 5 01 .

295027 High Containment Temperature I 5 Ability to interpret and execute procedure steps. 4.6 1 20 Ability to determine and/or interpret the following as they apply to High 0

295028 High Drywell Temperature I 5 Drywell Temperature: Torus/suppression chamber pressure: Plant- 3.8 1 5

Specific 295030 Low Suppression Pool Wtr Lvl I 5 0

02. Ability to analyze the effect of maintenance activities, such as degraded 295031 Reactor Low Water Level I 2 4.2 1 36 power sources, on the status of limiting conditions for operations.

295037 SCRAM Condition Present and Reactor Power Above APRM 0 Downscale or Unknown I 1 295038 High Off-site Release Rate I 9 0 600000 Plant Fire On Site I 8 0 700000 Generator Voltage and Electric Grid 0

Disturbances I 6 KIA Category Tota ls : 0 0 0 0 4 3 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 E/APE #I Name I Safety Function G KIA Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac I 3 0 295007 High Reactor Pressure I 3 0 295008 High Reactor Water Level I 2 0 295009 Low Reactor Water Level I 2 0 1295010 High Drywell Pressure/ 5 0 295011 High Containment Temp/ 5 0 295012 High Drywell Temperature/ 5 0 295013 High Suppression Pool Temp. I 5 0 295014 Inadvertent Reactivity Addition / 1 0 0 Ability to determine and/or interpret the follov.ing as they apply to Incomplete 295015 Incomplete SCRAM / 1 SCRAM: Reactor power 4.3 1 1

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

Temperature I 5 295033 High Secondary Containment Area 0

Radiation Levels I 9 295034 Secondary Containment Ventilation 0

High Radiation I 9 295035 Se condary Containment High 0

Differential Pressure I 5 295036 Secondary Containment High 02.

Knollllledge of limiting conditions for operations and safety limits. 4.7 1 Sump/Area Water Level/ 5 22

04. Ability to diagnose and recognize trends in an accurate and timely manner utilizing 500000 High CTMT Hydrogen Cone. I 5 4.2 1 47 the appropriate control room reference material.

KIA Category Totals: 0 0 0 0 1 2 Group Point Total: 3 ES-40 1, 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 System # I Name G KIA Topic(s) IR #

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

04. Knowledge of the operational implications of EOP warnings. cautions. and 205000 Shutdown Cooling Mode notes.

4.3 1 20 206000 HPCI 0 207000 Isolation (Emergency) 02.

Ability to determine operability and/or availability of safety related equipment. 4.6 1 Condenser 37 209001 LP CS 0 209002 HPCS 0 211 000 SLC 0 212000 RPS 0 Ability to (a) predict the impacts of the following on the IRM: and (b) based on 0

215003 IRM those predictions, use procedures to correct. control, or mitigate the 3.1 1 3 consequences of those abnormal conditions or operations: Stuck detector 215004 Source Range Monitor 0 215005 APRM I LPRM 0 217000 RCIC 0 Ability to (a) predict the impacts of the following on the ADS; and (b) based on 0

218000 ADS those predictions. use procedures to correct, control, or mitigate the 3.6 1 2 consequences of those abnormal conditions or operations: Large break LOCA 223002 PCIS/Nuclear Steam Supply 0

Shutoff Ability to (a) predict the impacts of the following on the SRVs: and (b) based on 0

239002 SRVs those predictions, use procedures to correct, control. or mitigate the 4.2 1 3 consequences of those abnormal conditions or operations: Stuck open SRV 259002 Reactor Water Level Control 0 26 1000 SGTS 0 262001 AC Electrical Distribution 0 262002 UPS (AC/DC) 0 263000 DC Electrical Distribution 0 264000 EDGs 0 300000 Instrument Air 0 400000 Component Cooling Water 0 KIA Category Totals: 0 0 0 0 0 0 0 3 0 0 2 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 System # I Name G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 1201001 C RD Hydraulic 0 1201002 R MCS 0 1201003 C ontrol Rod and Drive Mechanism 0 1201004 R SCS 0 1201005 R CIS 0 1201006 RWM 0 1202001 R ecirculation 0 1202002 R ecirculation Flow Control 0 Ability to (a) predict the impacts of the following on the RWCU; and (b ) based 0 on those predictions, use procedures to correct, control, or mitigate the 204000 RWCU consequences of those abnormal conditions or operations: Loss of plant air 2.6 1 7

svstems 214000 RPIS 0 215001 Traversing In-core Probe 0 215002 R BM 0 216000 Nuclear Boiler Inst. 0 1219000 RHRILPCI: Torus/Pool Cooling 0

Mode 1223001 P rimary CTMT and Aux. 0 1226001 R HR/LPCI: CTMT Spray Mode 0 1230000 R HRILPCI : Torus/Pool Spray Mode 0 1233000 Fuel Pool Cooling/Cleanup ' 0 1234000 Fuel Handling Equipment 0 1239001 Main and Reheat Steam 0 1239003 MSIV Leakage Control 0 1241000 ReactorfTurbine Pressure Regulator 0 245000 M ain Turbine Gen. I Aux. 0 256000 Reactor Condensate 0 04.

1259001 Reactor Feedwater KnoVv'ledge of abnormal condition procedures. 4.2 1 11 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 01.

290002 Reactor Vessel Internals Ability to explain and apply system limits and precautions. 4.0 1 32 KIA Category Totals: 0 0 0 0 0 0 0 1 0 0 2 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 :04/06/2015 KU SRO-Only Category KIA# Topic IR # IR #

2.1.

2.1. 34 Knowledge of primary and secondary plant chemistry limits. 2.7 3.5 1 Knowledge of industrial safety procedures (such as rotating equipment. electrical. high 2.1. 26 3.4 1 3.6

1. temperature. high pressure. caustic. chlorine. oxygen and hydrogen).

Conduct of 3.7 3.9 2.1 . 03 Knowledge of shift or short-term relief turnover practices. 1 Operations 2.1 . 40 Knowledge of refueling administrative requirements. 2.8 3.9 1 2.1 . 29 Knowledge of how to conduct system lineups. such as valves. breakers. switches. etc. 4.1 1 4.0 Subtotal

-~,-,,.

3

.. :;* 2 2.2. 05 Knowledge of the process for making design or operating changes to the facility. 3.2 1 2.2. 06 Knowledge of the process for making changes to procedures. 3.0 1 3.6 2.2. 14 Knowledge of the process for controlling equipment configuration or status. 3.9 1 4.3 2.

Equipment 2.2. 13 Knowledge of tagging and clearance procedures. 4.1 1 4.3 Control 2.2.

2.2.

ii Subtotal 3 ~ 1 2.3. 06 Ability to approve release permits. 3.8 1 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 2.3. 14 or emergency conditions or activities. 3.4 3.8 1 Ability to comply with radiation work permit requirements during normal or abnormal 2.3. 07 3.5 1 3.6

3. conditions.

Knowledge of radiological safety principles pertaining to licensed operator duties. such as Radiation 2.3. 12 containment entry requirements. fuel handling responsibilities. access to locked high- 3.2 1 3.7 Control radiation ar0 *

alionino filters etc.

2.3.

Subtotal 2 2 2.4. 29 Knowledge of the emergency plan. 3.1 4.4 1 2.4. 41 Knowledge of the emergency action level thresholds and classifications. 2.9 4.6 1

4. 2.4. 37 Knowledge of the lines of authority during implementation of the emergency plan. 3.0 1 4.1 Emergency Procedures 2.4. 25 Knowledge of fire protection procedures. 3.3 1 3.7 I Plan 2.4.

2.4.

Subtotal 2 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33