ML17194A759
| ML17194A759 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/03/2017 |
| From: | NRC/RGN-III |
| To: | Detroit Edison, Co |
| Shared Package | |
| ML17061A779 | List: |
| References | |
| Download: ML17194A759 (10) | |
Text
ES40I BWR Examination Outline Form ES-401-l Facility: Fermi2 Date of Exam:312012017 Tier Group RO tlA Category Points SRO-Only Points K K K K K K A A A A \, A2 \, Total 1 2 3 4 5 6 1 2 3 4 Total
- 1. 1 3 5 5 3 2 2 20 5 2 7 Emergency & N/A N/A 2 2 2 1 1 1 0 7 2 1 3 Abnormal Plant Evolutions Tier Totals 5 7 6 4 3 2 27 7 3 10 1 3 2 3 3 3 3 2 1 1 3 2 26 4 1 5 2.
Plant 2 1 1
,l 1 2 1 1 1 1 1 1 12 0 2 1 3 Systems Tier Totals 4 3 4 4 5 4 3 2 2 4 3 38 6 2 I
- 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 10 7 2 3 3 2 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable l(/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 l(/A category shall not be less than two). (One Tier 3 Radiation Control KA is allowed if the 1(A is replaced by a l(A from another Tier 3 Category.)
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The flnal point total for each group and tier may deviate by t1 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 with justification; operationally important, site-specific systems/evolutions 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 l(/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 l(As having an importance rating (lR) 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 l(/A categories.
7 . The generic (G) l(As in Tiers 1 and 2 shall be selected from Section 2 of the l(/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 llAs.
- 8. On the following pages, enter the ](/A numbers, a brief description of each topic, the topics' importance ratings (lRs) 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 a category 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 l(/A catalog, and enter the l(/A numbers, descriptions, lRs, and point totals (#) on Form ES-401-3. Limit SRO selections to llAs that are linked to 10 CFR 55.43.
U Generic K/As
ES40l 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emerqencv and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE # / Name / Safety Function K K K A A g llA Topic(s) IR #
,l 2 3 1 2 295001 Partial or Complete Loss of Forced 0 Knowledge of the interrelations between Partial or J-O Core Flow Circulation / I & 4 1 Complete Loss of Forced Core Flow Circulation and the fllwn: Rcirculâln svstem 295003 Partial or Complete Loss of AC / 6 0 Knowledge of the reasons for the following responses as 3.7 5 they apply to Partial or Complete Loss of AC Power:
Reâctr SCRAM 295004 Partial or Total Loss of DC Pwr / 6 0 Abilty to operate and/or monitor the following as they apply 3.8 3 2 to Partial or Complete Loss of DC Power: Systems necessâru to âssrrre sâfe lânt shtrtdwn 295005 Main Turbine Generator Trip / 3 0 Ability to determine and/or interpret the followng as they 3.8 4 5 eoolv to Mâin Turbine Generetor TrD: Ractor oower 295006 SCRAM / 1 0 Knowledge of the operational implications of the followng 3.7 5 1 concepts as they apply to SCMM: Decay heat generation
ând removâl 295016 Control Room Abandonment / 7 Knowledge of the interrelations between Control Room 4.4 6 1 Abandonment and the follownq: Remote shutdown panel 295018 Partial or Total Loss of CCW / I 0 l(nowledge of the reasons for the following responses as 3.3 7 2 they apply to Partal or Complete Loss of CCW: Reactor oower reduction 295019 Partial or Total Loss of lnst. Air / 8 01 Abilty to evaluate plant performance and make operational 4.4 I 07 judgments based on operating characteristics, reactor behavior. and instrument interpretation 295021 Loss of Shutdown Cooling / 4 0 Knowledge of the nteffelations between Loss of Shutdown 2.7 v 5 Cooling and the following: Fuel pool cooling and cleanup svstem 295023 Refueling Acc / I 0 3
Knowledge of the reasons for the following responses as lhev âDolv t Refuelino Accidents: Ventlation solation 3.3 10 295024 High Drywell Pressure / 5 1 Ability to operate and/or monitor the following as they apply 3.4 11 4 to Hioh Drvwell Pressure: Drvwell ventlation svstem 295025 Hgh Reactor Pressure / 3 0 Knowledge of the operational mplications of the following 3.9 12 1 concepts as they apply to High Reactor Pressure: Pressure effects on reactor Dower 295026 Suppression Pool High Water 0 Knowledge ofthe interrelations between Suppression Pool 3.6 13 Temp. / 5 2 High Water Temperature and the following: Suppression oool sorav l,lAFeml 295028 High Drywell Temperature / 5 0 Ablity to determine and/or interpret the following as they 3.7 14 3 aoDlv to Hiqh Drvwell Temperature: Reactor water level 295030 Low Suppression Pool Wtr Lvl / 5 0 Knowledge of the operational implications of the following 3.5 15 2 concepts as they apply to Low Suppression Pool Water Level: Pump NPSH 29503'l Reactor Low Water Level I 2 1 Knowledge of the interrelations between Reactor Low 4.1 16 6 Water Level ând the followino: Reactor water level control Knowledge of the reasons for the following responses as 3.2 aa 295037 SCRAM Condition Present and 0 Reactor Power Above APRM Downscale or 4 they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Hot shutdown Unknown / 1 boron weioht 295038 High Off-site Release Rate / 9 0 Ability to operate and/or monitor the following as they apply J.O 18 7 t Hioh Otf-ste Rlease Rete: Control room ventilation 600000 Plant Fire On Site / I 01 20 Ability to interpret and execute procedure steps 4.6 19 700000 Generator Voltage and Electric Grid 0 Knowledge of the reasons for the following responses as 3.9 20 Disturbances / 6 I they apply to Generator Voltage and Electrc Grid Disturbances: Reactor and turbine trip crteria l(/A Cateqory Totals: 3 5 5 3 2 2 Group Point Total: 20
ES-401 3 Form ES-401-l ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO)
EIAPE# I Name / Safety Function K K K A A u t(A Topic(s) IR #
1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 0 Knowledge of the interrelations between LOSS OF MAIN 3.1 21 2 CONDENSER VACUUM and the following: Main turbine 295007 High Reactor Pressure / 3 0 Ability to operate and/or monitor the following as they apply to 3.9 22 4 Hgh Reactor Pressure: Safety/relief valve operation: Plant-Specific 295008 High Reactor Water Level / 2 0 Knowledge of the operational implications of the following 3.0 23 1 concepts as they apply to High Reactor Water Level: Moisture carryover 295009 Low Reactor Water Level / 2 0 Ability to determine and/or interpret the following as they apply 4.2 24 1 to Low Reactor Water Level: Reactor Water Level 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 0 Knowledge of the operational implications of the following JJ 25 I concepts as they apply to High Drywell Temperature:
Pressure/temperature relationship 295013 High Suppression Pool Temp. / 5 29SOl4lnadvertent Reactivity Addition / 1 295015 lncomplete SCRAM / 1 295017 High Off-site Release Rate / I 295020 lnadvertent Cont. lsolation / 5 & 7 295022 Loss of CRD Pumps / 1 0 Knowledge of the reasons for the following responses as they 3.7 26 1 apply to Loss of CRD pumps: Reactor SCRAM 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Contanment Area Radiation Levels / 9 295034 Secondary Containment 0 Knowledge of the interrelations between SECONDARY 3.9 27 Ventilation High Radiation / 9 4 CONTAINMENT VENTILATION HIGH RADIATION ANd thE followng: Secondary containment ventilation 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 1(/A Category Point Totals 2 2 1 1 1 0 Group Point Total: 7
ES-401 4 Form ES-401-l ES-401 BWR Examination Outline Form ES-401-1 Plant Svstems - Tier 2/Grouo 1 IRO)
System # / Name K K K K K K A A A A G" l(/A Topic(s) IR #
I 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: lnjection 0 Knowledge of the effect that a loss or malfunction of ths 4.6 28 4 RHR/LPCI: INJECTION MODE wll have on followng:
Mode Adouel cors coolino 205000 Shutdown Cooling 0 0 Knowledg6 of SHUTDOWN COOLING SYSTEM (RHR 3.8 29 3 4 SHUTDOWN COOLING MODE) dssgn feature(s) and/or interlocks whch provide for th followng: Low ractol wator lvel Ability to manually operate and/or monitor n the control 3.4 30 rm Hâl ârchândr colno wâlr vlvs 206000 HPct 0 02 Knowledgo of the operatonal mplcâtons of lhe followng 3.3 31
à 39 mncepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSTEM: Turbne sp6ed control Knowledge of less thn or equal to one hour iechnil 3.9 32 Scificâtin âcton statemenls for the svslsm 2O70OO lsoletion Condenser l,A Fsmi 209001 LPCS 0 0 Knowledge of ths offct thât a loss or malfundon of the 3.8 33 2 3 followng will hav on the LOW PRESSURE CORE SPRAY SYSTEM: Emrgency genorators Ability to predict and/or monitor changos n paramotrs 3.8 34 assocated wth oporatng the LOW PRESSURF CORE SpFAY SYSTFM cnlrls nchr.lind Râtrwâtâr lâvl 209002 HPCS NA Fermi 21 1000 slc n Abilty to manually operate and/or montor n tho control room: Lghts ancl âlarms 3.6 35 7
212000 RPS 0 Knowledge of the physl connections and/or cause-etfect 3.5 36 6 relationships between REACTOR PROTCTION SYSTEM and lhs followino: Control od driv hvdraulc svstem 215003 tRM 0 Knowledge of the physical connctons and/or us-effect 3.9 37 1
relatonshps betwâen IRM System and the iollowing: RPS 215004 Source Range Monitor n Knowl6dg of electrcal power supples to tho followng: ¿.o 38 1
SRM channels/dstectors Knowldgo of th effect that â loss or malfuncton of the 3.2 10 215005 APRM / LPRM 0 7 APRM/LPRM wll have on following: Rod block monitor 217000 RClC 0 Knowledgs of REACTOR CORE lSoLATloN cooLlNG 3.5 40 6 SYSTEM (RCIC) design feâture(s) and/or intsrlocks whch Drovdo for the followino: Manuâl intialion 21 8000 ADS U Knowledga of tho opsrational implicâtions of the following 3.8 41 1
concpts as they apply to Automatic Dspressurizalion Sv.tân ADS ldic ratin 223002 PCIS/Nuclear Steam 0 Knowledgo of tho effct that a loss or malfunclon of th 3.3 42 4 following will havo on the PRIMARY CONTAINMENT Supply Shutoff ISOLATION SYSTEM/NUCLAR STEAM SUPPLY SHUT-OFF: Nuclear boiler instrumsntaton 239002 SRVs n Ability to predict and/or monitor changes in parameters 2.9 43 7 associatod with operatng the RELIEF/SAFETY VALVES contrls includino: Turbino load 259002 Reactor Water Level 0 Ability to (a) predct the impacts of the followng on the 3.3 44 6 REACTOR WATER LEVEL CONTROL SYSTEM ; and (b)
Control based on thos6 prodctions, use proceduras to correct, control, or mtgat tha nsequsnces of thoss âbnormal conditions or ooeratons: Loss of controllr sional outout 261000 SGTS 0 Ablity to monitor automalic opsrations of the STANDBY 3.0 45 GAS TREATMENT SYSTEM ncludng: Valve opralon 262001 AC Electrical 0 Ability to manually opsrats and/or montor n th conlrol 3.3 46 5 room: Voltags, curent, power, and fraquency on A.C.
Distribution buses 262002 UPS (AC/DC) 1 Knowlodgs of the physical connsctons ând/or cause-effct 2.5 47 1
r6latonships betwan UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) and the following: Control room rcorders: Plant-Socfic 263000 DC Electrical 0 Knowledge of slectrical power supplies to tho followng: 3.1 48 Major DC loads Distribution 1 264000 EDGs 0 04 Know6dge of the sffsct that a loss or malfuncton o lhe 4.1 49 3 11 EMERGENCY GENERATORS (DIESEUJET) will have on followng: Major loads powsred from electrical buses fsd by 4.O 50 the smergency gnrator(s)
Knwla.lâ f âhnrmâl cndlin orduros 300000 lnstrument Air 0 0 Knowladge of (INSTRUMENT AIR SYSTEM) dsgn 3.0 51 2 1 feature(s) and or nterlocks which provde for ths following:
Cross-over to othar air systems Knowldge of the oprational mplcations of th followng 2.5 52 concepts as they apply to tho INSTRUMENT AIR SYSTEM:
Air comrssors 400000 Component Cooling n Knowledge of the effect thst a loss or malfunction of the 3.0 53 4 following will have on tho CCWS: Pumps Water rl(/A Cateoorv Point Totals: 3 2 3 3 3 3 2 1 1 3 2 Total 26
ES401 5 Form ES,40l-l ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)
System # / Name K K K K K K A A2 A A u l(/A Topic(s) IR #
1 2 3 4 5 6 1 3 4 201001 CRD Hydraulic 01 Abilty to monitor automatic opsrâtons of the Control 3.0 54 Rod Drive Hydraulic System includng: Valve operaton 201002 RMCS 02 Ablity to (a) predict the mpâcts of tho followng on ths 3.2 55 REACTOR MANUAL CONTROL SYSTEM ; and (b) based on thoss prsdictions, use procedurss to corrct, control, or mitigat the nsequoncss of those abnormal conditons or operatons: Rod drift alarm 201003 Control Rod and rive Mechanism 201004 RSCS 20r 005 Rcts 201006 RWM 202001 Recirculation 03 Knowledge of tho operatonal mplcatons of the 2.7 56 Followng concpts as they apply to Recrculation Systom: Pump/motor cooling: Planfspcifc 202002 Recrculâtion Flow Control 05 Knowledge of the offact that a loss or malfunc{ion of ths 3.2 57 RECIRCULATION FLOW CONTROL SYSTEM will hâve on following: Recrculation pump speed: Plant-Specifc 204000 RWcu 01 Knowledg of th ffect that a loss or malfunction of ths 3.1 58 following wll have on lho REAcToR WATER CLEANUP SYSTEM : Component coolng water systems 214000 RPtS 215001 Traversing ln-Core Probe 215002 RBM 216000 Nuclear Boiler lnst. 01 Ability to manually oparale and/or montor n the control 3.3 59 room: Rcorders 21 9000 RHR/LPCI: Torus/Pool Cooling lvlode 223001 Prmary CTMT and Aux. 01 Know6dge of tho operatonâl mplications of lho 3.1 60 followng concepts as they apply to PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES i Vacuum br8aker/risf opration 226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Coolng/Cleanup 01 Knowldgo of systm purpose and/or function 3.9 61 27 234000 Fuel Handling Equpment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241 000 Reactor/Turbine Pressure 06 Knowlsdge of the physcal connections and/or cause- 3.8 82 egulator ffoct relatonshps btween REACTOR/TURBINE PRESSURE REGULATING SYSTEM and tha following:
Bypass valvss 245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate 01 Knowledg of sloctrcal power supples to tha followng: 2.7 63 Systom pumps 259001 Reactor Feedwater 268000 Radwaste 271 000 Offgas 12 Abilty to predct and/or monitor changes in paramotors 3.1 64 associatd with operating th OFFGAS SYSTEM controls includng:: Procsss radâton montorng indicâtions 272000 Radation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT Knowledgo of CONTROL ROoM HVAC dosign foâture(s) and/o. 3.1 65 290003 Control Room HVAC 01 intrlocks whlch provlde fortho followingr Systom inltiations/reconlguratlon: Plsnt-Specifc 290002 Reactor Vessel lnternals
(/A Category Point Totals: I 1 1 1 2 1 1 I I 1 I Group Point Total: 12
ES.401 2 Form ES-4,01-l ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group I (SRO)
EIAPE# I Name / Safety Function K K K A A u l(A Topic(s) IR #
I 2 3 1 2 295001 Partial or Complete Loss of Forced 0 Abilty to determne and/or interpret the following as they 3.1 76 Core Flow Circulation / 1 & 4 4 apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : lndividual et pump flows:
Not-BWR-1&2 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC Pwr / 6 02. Ability to apply Technical Specifcations for a system 4.7 77 40 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 04. Knowledge of the parameters and logic used to assess the 4.6 78 21 status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
295016 Control Room Abandonment / 7 0 Ability to determine and/or interpret the following as they 3.5 79 6 apply to CONTROL ROOM ABANDONMENT : Cooldown rate 295018 Partial or Total Loss of CCW / I 295019 Partial or Total Loss of lnst. Air / I 0 Abilty to determne and/or interpret the following as they 3.6 80 1 apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : lnstrument air system pressure 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / I 295024 High Drywell Pressure / 5 0 Ability to determine and/or interpret the following as they 3.9 8'l 4 apply to HIGH DRYWELL PRESSURE: Suppression chamber pressure: Plant-Specifc 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water Temp.
t5 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 295030 Low Suppression Pool Wtr Lvl / 5 29503'l Reactor Low Weter Level I 2 0 Ability to determine and/or interpret the following as they 4.8 82 4 apply to REACTOR LOW WATER LEVEL : Adequate core cooling 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / I 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / I 700000 Generator Voltage and Electric Grid Disturbances / 6 KA Category Totals: 5 2 Group Point Total: 7
ES40I ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
EIAPE # lName / Safety Function K K K A A G* K/A Topic(s) IR #
I 2 3 I 2 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 0 Ability to determine and/or interpret the following as 3.7 83 2 they apply to LOW REACTOR WATER LEVEL : Steam flow/feed flow mismatch 295010 High Drywell Pressure / 5 29501 I High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 02 Ability to determine operabilty and/or availability of safety 4.6 84 37 related equipment 295014lnadvertent Reactivity Addition / 1 295015 lncomplete SCRAM / 1 0 Ability to determine and/or interpret the following as 4.3 85 1 they apply to INCOMPLETE SCRAM: Reactor power 295017 High Off-site Release Rate / 9 295O2O lnadvertent Cont. lsolation /5&7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 KA Category Point Totals: 2 1 Group Point Total 3
ES401 4 Form ES-40r-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)
System # / Name K K K K K K A A A A u l(A Topic(s) IR #
I 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: lnjection 1 Ability to (a) predict the impacts of the following on 3.5 86 Mode 0 the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) ; ând (b) based on those predctions, use procedures to correct, control, or mitgate the consequences of those abnormal conditrons or operations: Nuclear boiler instrument failures 205000 Shutdown Cooling 206000 HPct 207 OO0 lsolation (Emergency) NA Ferm Condenser 209001 LPCS 0 Ablty to (a) predict the impacts of the followng on 3.1 87 I the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mtigate the consequences of those abnomal condtions or operations: Valve openings 209002 HPCS {AFemi 21 1 000 slc 212000 RPS 02 Knowledge of lmiting conditions for operations and 4.7 88 22 safety limits 215003 tRM 2'15004 Source Range Monitor 215005 APRM / LPRM 217000 RCIC 21 8000 ADS 0 Ability to (a) predict the impacts of the following on 4.3 89 6 the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on those predictons, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operatons: ADS initiation signals present.
223002 PC lS/N uclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level 0 Ability to (a) prdict thâ impacts of the following on the 3.4 90 REACTOR WATER LEVEL CONTROL SYSTEM ; âNd (b)
Control 5 basod on thos prsdictons, uso procedures to correct, control, or mitigate the consgqusnces of thos abnormal condtions or operations: Loss of applcable plânt air systems 261000 SGTS 262001 AC Electrical Distribution 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGS 300000 lnstrument Air 400000 Component Cooling Water l(/A Category Point Totals: 4 1 Group Point iotal: 5
ES-401 5 Form ES40l-l ES-401 BWR Examination Outline Form ES-401-1 Plant Svstems - Tier 2/Grou 2 (SRO)
System # / Name K K K K K K A
,l A A A KA Topic(s) IR #
1 3 4 5 6 2 3 4 201001 CRD Hydraulic 20t002 RMcs 201003 Control Rod and Drve Mechanism 201004 RSCS 201005 RClS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWcu 2'14000 RPts 215001 Traversng ln-Core Probe 215002 RBM 2'16000 Nuclear Boiler lnst.
219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.
226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray 0 Ability to (a) predict the mpacts of the 3.2 91 Mode 3 followng on the RHR/LPCI:
TORUS/SUPPRESSION POOL SPRAY MODE ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal condilins r oDeratons:: Velve closures 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241 000 Reactor/Turbine Pressure Reoulâtor 245000 Main Turbine Gen. / Aux. 02 Knowledge of the bases in Technical 4.2 92 25 Specifications for limiting conditions for ooerations end safetv limits.
256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitorng 286000 Fire Protection 288000 Plant Ventilation 290001 SecondaryCTMT 0 Ability to (a) predict the impacts of the 3.3 93 5 following on the SECONDARY CONTAINMENT ; and (b) based on those predictions, use procedures to correct, control, or mtigate the consequences of those abnormal conditions or operations:
Hioh area temoerature 290003 Control Room HVAC 290002 Reactor Vessel lnternals KA Category Point Totals: 2 1 Group Point Total 3
ES40r Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Fermi2 Date of Exam: 312012017 Category KIA# Topic RO SRO-Only IR # IR #
2.1.1 Knowledge of conduct of operations requirements. 3.8 66 2.1.26 Knowledge of industrial safety procedures (such as rotating 3.4 67 equipment, electrical, high temperature, high pressure, caustic,
Conduct of Operations 2.1.35 Knowledge of the fuel-handling responsibilities of SROs 3.9 94 2.1.39 Knowledge of conservative decision making practices. 4.3 95 Subtotal 2 2 2.2.12 Knowledge of surveillance procedures. 3.7 68 2.2.13 Knowledge of tagging and clearance procedures, 4.1 69 2.2.17 Knowledge of the process for managing mantenance activities 3.8 96 during power operations, such as risk assessments, work
- 2. prioritization, and coordination with the transmission system Equipment operator.
Control 2.2.20 Knowledge of the process for managing troubleshooting 3.8 97 activities.
2.2.14 Knowledge of the process for controlling equipment configuration 3.9 70 or status.
Subtotal 3 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.7 98 emergency conditions.
2.3.13 Knowledge of radiological safety procedures pertaining to 3.4 71 licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.
Radiation 2.3.12 Knowledge of radiological safety principles pertaining to licensed 3.2 72 Control operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
2.3.15 Knowledge of radiation monitoring systems, such as fixed 2.9 73 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
Subtotal 3 1 2.4.2 Knowledge of system set points, interlocks and automatic actions 4.5 74 associated with EOP entry conditions.
2.4.12 Knowledge of general operating crew responsibilities during 4.0 75
- 4. emergency operations.
Emergency Procedures / 2.4.25 Knowledge of fire protection procedures. 3.7 99 Plan 2.4.41 Knowledge of the emergency action level thresholds and 4.6 100 classifications.
Subtotal 2 2 Tier 3 Point Total 10 7