ML16216A648
| ML16216A648 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/02/2016 |
| From: | Palagi B Operations Branch III |
| To: | Exelon Generation Co |
| Shared Package | |
| ML15274A320 | List:
|
| References | |
| SVP-16-001 | |
| Download: ML16216A648 (20) | |
Text
{{#Wiki_filter:ES-401 BWR Examination Outline FORM ES.4O1-1 Date of Exam: 4118116 Facility Name: Quad Cities Tier Group Points A SRO-Only Points K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G Total A2 L7 Total 1. Emergency & Abnormal Plant Evolutions 'l 3 3 4 N/A 3 3 N/A 4 20 4 3 7 2 2 0 2 1 0 2 7 2 1 3 Tier Totals 5 3 6 4 3 b 27 6 4 10 2. Plant Systems 1 3 2 3 3 3 3 2 1 3 2 1 26 2 3 5 2 1 0 2 1 1 2 2 1 0 1 1 12 0 2 '1 3 Tier Totals 4 2 5 4 4 5 4 2 3 3 2 38 4 4 B
- 3. Generic Knowledge and Abilities Categories 1
2 3 4 10 1 2 3 4 7 2 3 2 3 2 2 1 2 Ensure that at least two topics from every applicable llA 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'"fier Totals" in each K/A category shall not be less than two).(One Tier 3 Radiation Control llA is allowed if the llA is replaced by aKlA f rom another Tier 3 Category). The point total for each group and tier in the proposed outline must match that specfied in the table. The final point total for each group and tier may deviate by +1 from that specified n the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 ponts. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply ai the facility should be deleted and justified; operationally mportant, 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 l(/A statements. Select topics f rom 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. Absent a plant-specific priority, only those llAs having an importance rating (lR) ol 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 and2 from the shaded systems and lVA categories' The genec (G) llAs in Tiers 1 and 2 shall be selected from Section 2 of the tlA Catalog, but the topics muslbe relevant to the applicable evolution or system. Refer to Sectlon D.1.b of ES-401 for the applicable l(As. On the following pages, enter the llA 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 other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2iorTier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. For Tier 3, select topics from Section 2 of the KA 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. Generic KAs Note: 1 2. 3. 4. 5. 6. 7. 8. 9. G-
ES-401 2 Form ES-401-1 ES-401 BWR Examinalion Outline Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (BO) Form ES-401-1 EIAPE # I Name / Safety Functon K 1 K 2 K 3 A 'f A 2 ( K/A Topic(s) IR 295001 Partial or Complete Loss of Forced Oore Flow Circulation / 1 & 4 0 5 Abilily lo operate and/or monitor the followng as they apply lo Partial or Complte Loss of Forced Core Flow Crculationi Recirculation flow control systm J.J 1 295003 Partial or Complete Loss of AC / 6 n J Knowldge of the inlerrlations beween Partal or Complete Loss of AC and the lollowing: A.c. eleclrcal distribulon system 3.7 1 295004 Partial or Total Loss of DC Pwr / 6 0 1 Knowledge of the reasons for th followng responses as lhey apply to Partal or Total Loss of DC Pwr; Load shedding: Plant-Specfc 2.6 '1 295005 Main Turbine Generator Trip / 3 0 1 Knowldge of the operational mplicatons of the following concepts as they apply lo l\\4ain Turbine Generalor Trip: Pressure sffects on reactor power 4.O 1 295006 scRAM / 1 0 7 Knowledge of the interrelations between SCRAM and the following: Reactor pressure ronlrol 4.0 1 29501 6 Control Room AbandonmenT I 7 01 31 Abiity to locate control room swilches, controls, and ndcatons. and to determine that they corrclly eflect the desired plant neup. 4.6 1 295018 Partial or Total Loss of CCW / B 0 2 Ablity to operale and/or montor the lollowng as they apply to Parlial or Total Loss of 0CW: Syslem loads 3.3 1 2950 1 9 Partial or Total Loss of lnst. Air / B 0 J Ablity to operate and/or monitor lhe followng as they apply to Partial or Total Loss of nst. Air: lnstrument air compressor power supplies 3.0 1 295021 Loss of Shutdown Cooling / 4 0 2 Knowledge of the operational implicalions of the following concepts as they apply to Loss of Shutdown C@ling: Thermal stralif icaton 3.3 1 295023 Refueling Acc / B 0 2 Abilityto determne and/or interprel lhe followng as they apply to Refuelng Accidents: Fuel pool level 3.4 1 295024 High Drywell Pressure / 5 0 3 Abilily lo determins and/or inlerpret the following as they appiy to High Drywell Pressur: Suppresson pool level 3.8 1 295025 High Reactor Pressure / 3 01, 23 Ablily to prform specfic system and intgratsd phnt procedures during all modes of rlant operaton. 4.3 1 295026 Suppression Pool High Water Iemp. / 5 0 5 (nowledge of the reasons for the following responses as they apply to Suppression )ool High Water Temp.; Reactor SCRAI\\4 3.9 1 295027 High Containment Temperature / 5 0 295028 High Drywell Temperature / 5 04. 45 Ability to prioritize and interprt the signfcanc of each annunciator or alarm. 4.1 1 295030 Low Suppression Pool Wtr Lvl / 5 0 2 Ability to detsrmne and/or interpret the followng as thsy apply to Low Suppression Pool Wtr Lvl: Suppresson pool temperature 3.9 1 295031 Reactor Low Water Level l2 04. 02 Knowledge of system set points, interlocks and automatic actions associated wth EOP entry conditons. 4.5 1 295037 SCRAM Condition Present and leactor PowerAbove APRM Downscale or Jnknown / 1 0 1 Knowledge of the operational implications of the followng concepts as they apply to SCRAM Conditon Pressnt and Reactor Powr Above APRM Downscale or Unknown: Reactor pressur effects on reactor powr 4.1 1 295038 High Off-site Release Rate / I 0 4 Knowledge of lhe reasons for ihe followng responses as they apply to High off-site Release Rale: Emergency depressurzaton 3.6 1 i00000 Plant Fire On Site / I 0 4 Knowledge of the rsons for the followng responses as they apply lo Plant Fre On Sile: Actions contained n the abnormal predur for plant fire on site 2,8 1 200000 Generator Voltage and Electric Grid )isturbances / 6 n 3 Knowledge of the nterrelations bstween Generator Voltage and Electrc Grid Dsturbances and th following: sensrs, detectors, indicators 3.0 1 (/A Category iotals: 3 3 4 3 3 4 Group Point Total: 20
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (BO) EIAPE # I 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 04. 49 Ability to perform wlhout reference to predures those actons that rquire immedate operation of system components and controls 4.6 1 295008 High Reactor Water Level / 2 0 295009 Low Reactor Water Level / 2 0 1 Knowledg of the reasons for the following responses as they apply to Low Reâctor Waler Level: Recirculation pump run back: Planl-Specific 3.2 1 295010 High Drywell Pressure / 5 0 29501 1 High Containment Temp / 5 0 295012 High Drywell Temperature / 5 0 295013 High Suppression Pool Temp. / 5 0 295014 lnadvertent Reactivity Addition / 1 0 ¿ Knowldge of lhe operational implications of the following concpts as they apply lo lnadvrtent Reaclivty Addition: Reactvty anomaly 3.3 1 295015 lncomplete SCBAM / 1 0 295017 High Off-site Release Rate / 9 0 295020 lnadvertent Cont. lsolation / 5 & 7 0 295022 Loss of CRD Pumps / 1 0 1 Abtityto operate and/or monitor the following as they apply to Loss of CRD Pumps: cRD hydraulic system 3.1 1 295029 High Suppression Pool Wtr Lvl / 5 04. 45 Abiitylo proritize and intsrpret the sgnitcance of each annuncator or alarm. 4.1 1 295032 High Secondary Containment Area femperature / 5 295033 High Secondary Containment Area adiation Levels / 9 0 J Knowldge of lhe operational mplications of the followng concepts as they apply to Hgh Secondary Containment Area Radation Levelsl Radiation rleases 3.9 1 295034 Secondary Containment Ventilation {igh Radiation / 9 0 295035 Secondary Containment High )ifferential Pressure / 5 n 295036 Secondary Containment High Sump/Area Water Level / 5 e Knowledge of lhe reasons for the following responses as they apply to Secondary Containment High Sump / Area Water Level: lsolating affected systems 3.5 1 i00000 High CTMT Hydrogen Conc. / 5 K/A Category lotals: 2 U 2 0 2 Group Point Total: 7
ES-401 4 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2/Group 1 (RO) Form ES-401-1 ES-401 IR K 1 K ¿ K 3 K 4 K 5 K 6 A I A 2 A J A 4 G l(A Topic(s) System # / Name 3.4 1 0 I (nowledge of lhe effect that a loss or malfunction of the following will have on
- he RHB/LPCI: lnjection Mode: Nuclear boilr nstrumentalion 203000 RHB/LPCI: lnjection Mode 3.1; 3.6 2
205000 Shutdown Cooling n 'I 0 Ã <nowsdge of eleclrcal power supplies to the following: Pump molors; (nowedge of Shutdown C@ling design feature(s) and/or nterlocks whch )rovde for lhe followng: Reactor cooldown rate 2.7 1 Abilty lo (a) predct the mpacts of lhe following on lhe HPCI; and (b) based on lhose predictons, us procedures to correct, control, or mtigate the conssqusnces of those abnormal conditions or operationsl A.C. failures: BWF-206000 HPcl 0 4 0 207000 lsolation (Emergency) Oondenser 2.6 1 Knowledge of the operational mplicalions of the followng concpts as thoy applylo LPcS: lndcations of pump cavtation 209001 LPCS 0 1 TJ 209002 HPCS 4.3 1 Knowledge of the efft that a loss or malfuncton of the SLC will have on lollowng: Ability lo shutdown the reactor n crtan conditons 2t1000slc 0 1 3.6 1 0 1 Knowledge of the effl lhât a loss or malfuncton of the following wll have on the RPS: A.C. electrcal dstr ibulon 212000 RPS 3; 2.8 2 0 â U .J Knowledge of the operalional implcatons of lh followng concpts as thy apply to IRM: Changing detector positioni Knowledge of lhe elf ect that a loss or malfunction of lhe following will have on the lRl\\4: Delector drve motor 215003 rRM 3.9; 4.4 2 0 1 01. 30 Ablly to manually oprate and/or montor in the control room: SRM count rate and perod; Ability to locate and operate components, ncluding local conlrols, 215004 Source Range Monitor 3.2 I 0 7 Knowledg of the effect that a loss or malfunction of the APRM / LPRM will have on following: Rod block monitor: Planlspecific 2.15005 APRM / LPRM 2
- 3. 1; J.O 217000 Rctc 0
7 0 2 Knowledge of the physcal connectons and/or cause-effecl relationships betwen FICIC and the followng: Leak deteclion; Ability to monitor aulomatc opsrations of lhe RCIC includng: Turbne startup 1 eo 21BOOO ADS 0 6 Knowledge of the physcal connections and/or cause-effect relationships bstwsen ADS and the followng: Safety/relief valves 3.3 I Knowldge of PCIS/Nuclear Steam Supply Shutoff design feature(s) and/or nterlocks whch provid for the following: Manual defeatng of selected solâtons durinq sDecif ied emerqencv conditons 223002 PCIS/Nuclear Steam Supply Shutoff 0I 3.9 1 0I Ability to monitor automatic operatons of the SRVs including; Low low set logic: PlanFSpecific 239002 SRVS 2.9 1 Knowledge of th efect lhal a loss or maffuncton of the Ractor Water Level Sonlrol wll have on following: Recirculation systmr Plant-Spific 259002 Reactor Water Level Control 0 4 3.f 1 0 7 Ability to manually operats and/or monilor n the conlrol room: System flow 261000 SGTS 3.f 1 U 2 Abilty to prdict and/or montor changes n paramelers assocated wth rperaling the AC Electrcal Distrbuton controls ncluding: Éffects of loads when snsrqzinq a bus 262001 AC Electrical Distribution 3.1 1 0 I (nowldge of UPS (AC/DC) design feature(s) and/or intrlocks which provde 'or the following: Transfer from preferred power to alternate power supples 262002 UPS (AC/DC) 3.1 1 1 <nowledge of electrical power supplies to the Tollowing: Major D.C. loads 263000 DC Electrical Disiribution 3.1 'l 0 2 Ability to monitor aulomatic operations of the EDGs including: l\\,4nimum time for load pick up 2&000 EDGS tq 1 0 1 Knowledge of the operalional implicatons of lhe following concepts as lhey apply to lnsument Air : Air compressors 300000 lnstrument Air 2.8 1 0 2 Abilty lo predict and/or monitor changes in parametrs associaled with operalng the Componenl Cooling Water controls ncluding: CCW temperature 400000 Component Cooling Water 3.5 1 0 2 Knowledge of the physical conneclons and/or cause-effect relationshps between REACTOB CORE ISOLATION COOLING SYSTEM (RCIC) and the followno: Nuclear Boiler Svslem. 217OOO SSMP 26 2 1 Group Point Total (A Category Totals: 3 2 J J 3 2 1 J tllt
ES-401-1 5 Form ES-401-1 BW R Examination Outline Plant Systems - Tier 2/Group 2 (RO) Form ES-401-1
- S-401 IR G
K/A Topic(s) K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 4 System # / Name 0 201001 CRD Hydraulic 3.4 1 Knowledge of the effect that a loss or malfunclon of the RMCS will have on tollowinq: Abiltylo move conlrol rods 0 1 201OO2 RMCS 1 2.6 Knowledge of lhe physi@l connections and/or cause-effect relatonshps celween Conlrol Rod and Drve l\\4echanism and the followng: CRD mchanism 0 201003 Control Rod and Drive Mechanism 0 201004 RSCS 0 201005 RCIS 0 201006 RWM 0 202001 Recrculation 3.6 1 Abilily to predict and/or monitor changes in paramelers associated wth operatinq the Recirculation Flow Control controls ncludng: Reaclor power 0 202002 Recirculation Flow Control 0 2O4OOO RWCU 3.0 'I Knowledge of RPIS design feature(s) and/or interlocks which provde for the followng: Reed swtch localions 0 1 21 4000 RPIS 3.0 1 0 3 Ability to manually operate and/or monitor n the control room: lsolaton valves: Mark-l&ll(Not-BWR1) 21 5001 Traversing ln-core Probe 2.5 1 Knowledge of lhe effect lhal a loss or malfuncton of the following wll have on lhe BBM: Essenlal power: Phnl-specfic 0 3 21 5002 RBM 0 21 6000 Nuclear Boiler lnst. 0 21 9000 BHR/LPCI: Torus/Pool Cooling Vode 0 223001 Primary CTMT and Aux. 2.9 0 3 Knowledge of the effect lhat a loss or malfunction of the RHR/LPCI: CTM I Spray Mode will have on folbwng: Contanment/drywelysuppression chamber 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode ee 18 Knowledge of the specific bases for EOPs. 233000 Fuel Pool Cooling/CleanuP 0 234000 Fuel Handljng Equipment 0 239001 lMain and Reheat Steam 0 239003 MSIV Leakage Control 0 241 000 Reactor/Turbine Pressure Regulator 1 3.7 0 4 Abilitylo (a) predict lhe mpacls of the following on lhs Man Turbine Gen. / Aux.; and (b) based on those predctions, use procedures lo correct, conlrol, or 245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 1 2.8 0 4 Knowldg of the effect that a loss or malfunction of lhe followjng will have on lhe Fir Protecton: Dissel fu lransfer system: PlanFSpecifc 286000 Fire Protection 3.2 1 apply lo Plant Ventilaton : Diffrnlal pressure control Knowledge of lhe operatnal mplcations of the followng concepts as they 0 2 288000 Plant Ventilation 0 290001 Secondary CTMT 2.5 1 Ability to predct and/or monitor changes in paramelers associaled wth cperating the Control Room HVAC controls ncluding; Control room pressur 0 4 290003 Control Room HVAC 0 290002 Reactor Vessel lnlernals 1 Group Point Total: 1 0 2 1 1 2 2 1 0 1 (/A Category Totals: TI TIIIII
ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SnO) Form ES-401-1 EIAPE # I Name / Safety Function K 1 K 2 K 3 A 1 A 2 G l(/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 02. 22 Knowledge of limiting conditons for operations and safety lmts. 4.7 1 295004 Partial orTotal Loss of DC Pwr/6 0 2 Ability to determine and/or interpret the following as they apply to Partial or Total Loss of DC Pwr: Extent of partial or complete loss of D.C. power 3.9 1 295005 Main Turbine Generator Trip / 3 0 235006 scRAM / 1 0 295016 Control Room Abandonment/7 0 295018 Partial or Total Loss of CCW / B 0 2 Ability to determine and/or interpret the following as they apply to Partial or Total Loss of CCW: Coolng water temperature 3.2 1 295019 Partial or Total Loss of lnst. Air / B 02. 37 Ability to determne operability and/or avalabilty of safety related equipment. 4.6 1 295021 Loss of Shutdown Cooling / 4 0 5 Ablty to determine and/or nterpret the following as they apply to Loss of Shutdown Cooling: Reactor vessel metal temperature E 1 295023 Refueling Acc / B 0 295024 High Drywell Pressure / 5 04. 46 Ability to verify that the alarms are consistenl with the plant conditions. 4.2 1 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water Iemp. / 5 0 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 0 1 Ability to determine and/or interpret the following as they apply to High Drywell Temperature: Drywell tmperature 4.1 1 295030 Low Suppression Pool Wtr Lvl / 5 0 295031 Reactor Low Water Level / 2 0 295037 SCBAM Condition Present and Reactor Power Above APRM Downscale or IJnknown / 1 295038 High Off-site Release Rate / 9 â00000 Plant Fire On Site / B 200000 Generator Voltage and Electric Grid Disturbances / 6 (/A Category Totals: 0 0 0 0 4 3 Group Point Total 7
-s-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO) EIAPE # / Name / Safety Functon K 1 K 2 K a A 1 A 2 G llA Topic(s) IB 295002 Loss of Main Condenser Vac / 3 04. 35 Knowledge of local auxliary operator tasks durng an emergency and the resuhânl operalonal effects. 4.0 1 295007 High Reactor Pressure / 3 0 295008 High Beactor Water Level / 2 0 1 Abilty to delermne and/or interprel the followng as they apply to Hgh Reactor Watel Level: Reactor water level 3.9 1 295009 Low Reactor Water Level / 2 0 295010 High Drywell Pressure/5 0 2 Abilily to determine and/or nterpret lhe following as they apply to Hgh Drywll Pressure: Drywell pressure 3.9 1 295011 High Containment Temp / 5 0 295012 High Drywell Temperature / 5 0 295013 High Suppression Pool Temp. / 5 0 295014 lnadvertent Reactivity Addition / 1 295015 lncomplete SCRAM / 1 0 295017 High Off-site Release Rate / I 0 295020 lnadvertent Cont. lsolation / 5 & 7 0 295022 Loss of CBD Pumps / 1 0 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area femperature / 5 295033 High Secondary Containment Area ladiation Levels / I 0 295034 Secondary Containment Ventilation High Badiation / 9 0 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Contanment High Sump/Area Water Level / 5 0 500000 High CTMT Hydrogen Conc. / 5 n l(/A Category Totals: 0 0 0 0 2 1 Group Point Total: 3
ES-401 4 Form ES-401-1 s-40,l BWR Examination Outline Plant Systems - Tier 2/Group 1 (SRO) Form ES-401-1 3ystem # / Name K 1 K K 3 K 4 K 5 K D A 1 A 2 A
A 4 G K/A Topic(s) IR 203000 RHR/LPCI: lniection 0 205000 Shutdown Cooling Mode 0 206000 HPCI 0 207000 lsolation (Emergency) Condenser 0 209001 LPCS 0 7 Ablly to (a) predct the impacts of th followng on the LPCS and (b) based on those predctons, use procedures to corect, control, or mitigate the consquences of those abnormal condtions or operations: Loss of room coolin( 2.8 1 209002 HPCS 0 21 1000 slc tl 212000 RPS 04. 30 Knowledge of events related to system operation/status lhal must be reported tc internal organzalons or extsrnal agncies, such as the State, the NRC, or the lransmssion svstem oDerator. 4.1 1 215003 IRM 0 215004 Source Range Monitor 21 5OO5 APRM / LPRM 217000 Rcrc 0 21BOOO ADS 0 223002 PCIS/Nuclear Steam Supply Shutoff 0 239002 SRVS 02. 22 Knowledge of limiling conditons for opratons and safely Iimits. 4.7 1 259002 Reactor Water Level Control 0 261000 sGTs 1 1 Abilily to (a) predict the impacls of the followng on lhe SGTS; and (b) based on those predictions, use procedurs lo correct, control, or mligal th consequences of lhos abnormal conditions or operatons: High containment 3.3 1 262001 AC Electrical Distribution n 262002 UPS (AC/DC) 02. 40 Abilíty to apply Tchnical Specifications for a system. 4.7 1 263000 DC Electrical Distribution 0 264000 EDGS 0 300000 lnstrument Air 0 400000 Component Cooling Water 0 (/A Category Totals: 0 0 0 0 0 2 n 3 Group Point Total: Ã
ES-401 5 Form ES-401-1 BWR Examination Outline Plant Systems - Tier 2/Group 2 (SRO) Form ES-401-1 -s-401 IR G K/A Topic(s) K 1 K 2 K 3 K 4 K t K 6 A 1 A 2 A 3 A 4 System # / Name 0 ¿01001 CRD Hydraulc 0 201002 RMCS 0 201003 Control Rod and Drive l\\echanism 0 201 004 RSCS 0 201005 RCIS 0 201006 RWM 0 202001 Recirculaton 0 202002 Recirculation Flow Control 1 4.4 01. 23 Ability to perform spcfic system and ntegratd plant procedures during all modes of plant operation. ZO4OOO RWCU 0 214000 RPls 0 215001 Traversing ln-core Probe 0 215002 RBI\\4 0 216000 Nuclear Boiler lnst. 0 21 9000 RHR/LPCI: Torus/Pool Coolng Mode 0 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTIVT SPraY l\\/ode 0 230000 RHF/LPCI: Torus/Pool Spray Mode 0 233000 Fuel Pool Cooling/Cleanup 3.7 1 o 1 Arbifity tola) pre¿ict the mpacts of the following on lhe Fuel Handlng Equpment; and (b) based on those predictons, use procedures to correcl, 234000 Fuel Handlng Equipment 0 239001 Man and Reheat Steam 0 239003 IVSIV Leakage Conlrol 0 241 000 Reactor/Turbine Pressure Regulator 0 245000 Man Turbine Gen. / Aux. 2.9 0 5 bilty to (a) predict the mpacts of the following on lhe Reactor condensate; and (b) based on those predictions, use procedures to correcl' conlrol, or 256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 286000 Fire Protecton 0 288000 Plant Ventilation 0 ¿90001 Secondary CTMT 0 290003 Control Room HVAC 0 290002 Reactor Vessel lnternals 1 Group Pont Total: 0 0 0 0 0 0 0 2 0 0 (/A Category Totals: IIIII tlll
ES-40f Generic Knowledqe and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Quad Cities Date of Exam:4/18/16 Category KlA# Topic t-{u IR IR 1. Conduct of Operations 2.1. 34 (nowlodge of primary and secondary plant chemistry limits. 2.7 3.5 1 2.1. 37 (nowl6dge of predurs, guidelnos, or limtâtions associated with eactvily nanagomgnt. 4.3 1 4.6 2.1. 04 Knowlsdge of indivdual licensed opsrator lesponsibilities rlatsd to shft staffing, such âs medical requirments, "no-solo" oporation, mantenanco of activa license status, 3.3 1 3.8 2.1. 35 Knowlsdgs of the fuel-handling responsiilities of SROs. 3.9 1 2.1. 2.1 Subtotal 2 2 2. Equipment Control 2.2.07 Knowledgs of tho process for conducting spal or nfrsquent tests. 2.9 1 3.6 2.2. 43 Knowladge of the procâss used to track inoprabls alarms. 3.0 1 3.3 2.2. 11 Knowledgs of the process for conlrolling temporary dosign changes. J.J 1 2.2. 12 Knowlsdgs of surueillance procedures. 3.7 4.1 'l 2.2.06 Knowlodge of ths process for making changes to predures. 3.0 1 3.6 2.2 Subtotal 3 2 3. Radiation Control 2.3. 12 Knowledga of radiologcal safety principls pertaining to licenssd operator duties, such as rontainment ntry requroments, fusl handling responsibilitss, accass to lockod high- ,¿ 1 3.7 2.3. 15 Knowlsdge of radiation monitoring sygtoms, such as fixed radiaton monitors and alarms, 3ortable survey insumonls, porsonnel monitoring equpmnt, etc. 2.9 1 3.1 2.3. 11 Abilid to control radiation releass. 3.8 4.3 1 2.3. 2.3. 2.3. Subtotal 2 1 4. Emergency Procedures / Plan 2.4.03 Ability to identify post-accdent instrumontation. 3.7 1 3.9 2.4. 41 Knowlodge of ths emsrgncy action lavel thresholds and classifications. 2.9 4.6 1 2.4.23 Knowledge of lha bases for priortizing emergency proceduro implmntation durng mergncy operations. 3.4 1 4.4 2.4. 11 Knowledgo of abnormal condition procedures. 4.0 4.2 1 2.4. 01 Knowledge of EOP entry conditions and immediate aclion steps. 4.6 1 4.8 2.4 Subtotal 3 2 Tier 3 Point Total 10 7
ES-401 Record of Rejected llAs (RO) Form ES-401-4 Tier 1 Group 1 Tier/ Group Randomly Selected l(A Reason for Rejection 111 295019 441.04 became 295019 441.03 System ration is not applicable to ad Cities Station 1/1 295024 42.05 became 295024 842.03 System monitoring point is not used during transient conditions at Quad Cities Station. Not operationally significant. 111 600000 K3.01 became 600000 K3.04 nal selection lmportance Rating <2.5 1
ES-401 Record of Rejected l</As (RO) Form ES-401-4 Tier 1 Group 2 Tier I Group Randomly Selected IVA Reason for Rejection None rejected 2
ES-401 Record of Reiected llAs (RO) Form ES-401-4 Tier 2 Group 1 Tier I Group Randomly Selected tlA Reason for Rejection 2/1 21 1000 K3.02 became 21 1000 K3.01 System inter-relation is not applicable to Quad Cities Station 2/1 223002K4.03 became 223002K4.08 System nter-relation is not applicable to Quad Cities Station 211 261000 K4.08 became 261000 K4.07 No valid question this aspect of the SBGTS at Quad cities. Rep aced with another syste system. m ndication (monitonng) question with n the same 3
ES-401 Record of l(/As Form ES-401-4 Tier 2 Group 2 Tier I Group Randomly Selected l(/A Reason for Rejection None rejected 4
ES-401 Record of Reiected l(As (RO) Form ES-401-4 Tier 3 Tier/ Group Randomly Selected l(/A Reason for Rejection 3 sG 2.4.35 became sG 2.4.03 SG 2.4.35 used on RO test in another of the test 3 sG2.1.27 Became sG 2,1.04 t(/R A too smple for License Examination. Did not pass first validation 5
ES-40r Record of Reiected llAs (SRO) Form ES-401-4 Tier 1 Group 1 Tier I Group Randomly Selected l(/A Reason for Rejection 1/1 295016 Generic became 295028 42.01 Sampled on RO Written exam 6
ES-401 Record of Reiected llAs (SRO) Form ES-401-4 Tier 1 Group 2 Tier / Group Randomly Selected l(/A Reason for Rejection 112 295008 442.05 became 295008 442.01 to write SRO level 7
ES-401 Record of Reiected llAs (SRO) Form ES-401-4 Tter 2 Group 1 -lier I Group Randomly Selected tlA Reason for Rejection 212000 G4.2.A9 became 212000 G2.4.30 Unable to write SRO level question 2/1 III B
ES-401 Record of Reiected llAs (SRO) Form ES-401-4 Tler 2 Group 2 Tier / Group Randomly Selected tVA Reason for Rejection 212 256000 G2.4.01 became 256000 42.05 System inter-relation is not applicable to Quad Cities on 2/2 2VA00 G2.4.50 became 234000 42.01 pling on the SBGTS. The is tested in a Simulator 9
ES-401 Record of Reiected l(As (SRO) Form ES-401-4 Tier 3 Randomly Selected IVA Reason for Rejection Tier / Group Unable to write SRO Only question on Plant Wide Announcsments 3 G 2.1.14 Became G2.1.35 3 G2.1.15 became G2.1.34 Unable to write SRO Only question on Daily Orders, Memos, etc 3 G2.2.20 Became G2.2.12 Unable to write SRO activities. Only question on Manageme.nt of troubleshóoting i; ¿ il:. "dtf. i" l;'i .t I 1_0}}