ML15314A052

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2015 Clinton Power Station Initial License Examination Forms ES-401-1 and ES-401-3
ML15314A052
Person / Time
Site: Clinton Constellation icon.png
Issue date: 11/09/2015
From:
NRC/RGN-III
To:
Exelon Generation Co
Zoia, C D
Shared Package
ML15124A069 List:
References
Download: ML15314A052 (11)
v • d • e


Text

ES-40 1 BWR Exam i nat i on Outline F ORM ES-40 1-1 Facility Name: Clinton Date of Exam: 3/16/2015 R O KI A Category Points SR O-O nly Points Tier Group K K K K K K A A A A G G* Total A2 Total 1 2 3 4 5 6 1 2 3 4

  • 1. 1 3 4 3 3 4 3 20 4 3 7 Emergency

& Abnormal 2 1 1 1 N/A 1 2 N/A 1 7 2 1 3 Plant Evolutions Tier Totals 4 5 4 4 6 4 27 6 4 10 1 3 3 2 3 2 2 2 3 2 2 2 26 3 2 5 2. Plant 2 1 1 1 1 2 1 1 1 1 1 1 12 0 2 1 3 Systems Tier Totals 4 4 3 4 4 3 3 4 3 3 3 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 10 7 3 2 3 2 2 2 2 1 Note: 1. Ensure that at least two top ics 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 KJA 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 0.1.b of ES-401 for guidance regarding the elimination of inappropriate KJA 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 K/As having an importance rating (IA) 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 KJA categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJA numbers , a brief description of each topic , the topics' im portance 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 equ i pment 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 KJA catalog , and enter the KJA numbers, descriptions , I Rs , 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-40 1 .. ES-401 BWR Ex aminatio n Outlin e Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 1 (RO) Q# E/APE #I Name I Safety Fun c t io n K K K A A G 1 2 3 1 2 KIA Topic(s) IR # 46 1295001 Partial or Complete Los s of Forced 0 Knowledge of the reasons for the followi n g responses as they apply to Partial or C ore Flow C i rculation

/ 1 & 4 6 Complete Loss of Forced Core Flow Circula t ion: Core f low indica t ion 2.9 1 58 295 003 Partial or Complete Loss of AC I 6 0 Knowledge o f the interrelations between Partial or Complete L oss of A C and the 4 following: A.G. electrica l loads 3.4 1 53 295 004 Partial or Total Lo s s of DC Pwr 1 6 0 Ab ili ty to determine and/or interpret the following as th e y apply to Partial or T otal 4 Loss of DC Pwr: Syste m lineups 3.2 1 39 295 005 Main Turbine Generator Trip I 3 0 Kn o wledge of th e operational implications of the following concep t s as they appty t o 3 Ma in Turbi n e Ge n era t or Trip: Pressu r e effects on reactor level 3.5 1 50 1295006 SCRAM I 1 0 Ability to operate and/or monitor the following as th ey apply to SCRAM: N e utr on 5 moni t oring system 4.2 1 49 1295016 Control Room Abandonment 1 7 0 Ability t o operate and/or mo n itor the following as they apply to Control Room 8 Abandonment:

Reactor pressure 4.0 1 47 1295018 Partial or Total Loss of CCW / 8 0 Kn o wl edge of th e r easo n s for th e f onowi ng responses as they apply to Partial or 1 Total Loss of CC W: Isolation of non-essential heat loads: Plant-Specttic 2.9 1 43 1295019 Part i al or Total Loss of Inst. Air/ 8 0 K nowledge of the interrelations between Panial or Total L oss of In st. A ir and t h e 1 following: CRD hydraulics 3.8 1 44 1295021 Loss of Shutdown Cooling/ 4 0 Kn owledge o f the interrela t ions between L oss of Shutdown Cooli ng and th e 6 following: R eactor vessel headspray: Plant-Specific 2.5 1 54 129 5023 Refueling Ace I 8 01. Ability t o pertorm specific system and integrated plant procedures during all modes 23 of plant operatton. 4.3 42 1295024 High Drywell Pressure I 5 0 Knowledge of the i nterrelat ions between High Drywall Pressure and th e following: 2 HPCS: Plant-Specttic 3.7 1 57 1295025 High R eac tor Pressure I 3 0 Ability t o determine and/or interpret the following as they appty to H ig h R eactor 3 Pressu r e: Suppression pool temperature 3.9 1 45 295026 Suppress io n Pool H i gh Water -0 Ab ility to determine and/or interpret the fo llowin g as they appty t o Suppression Poot tTemp. / 5 1 H igh W ater Temp.: Suppression pool w ater t emperature 4.1 1 55 1295027 High Containment Temperature/

5 . 01. A bility t o eva luat e plant performance and make operatio n al judgments based on 07 opera t ing characteristics, r eactor beha vi or, and in s trument interpre t ation. 4.4 1 56 1295028 High Drywell Temperature/

5 02. Ab ility t o in t erp r et control room indications to verify the sta tu s and ope r ation o f a 44 system, and understand how operator actions and d i rectives affect plant and syste m 4.2 1 conditions.

51 1295030 Low Suppression Pool Wtr Lvl I 5 0 A bility t o determine and/or interpret the f ollo w ing as th ey apply to L o w Suppressio n 3 Pool Wtr Lvt: Reactor pressure 3.7 1 41 1295031 Reactor Low Water Level/ 2 0 Kn owledge of th e operational implica ti ons of the f ollo wing concep t s as th e y apply t o 3.7 1 3 !'.1* Reactor Low W ate r Level: W at er level e ff ects on reactor power 1295037 SCRAM Condition Pre sent and I; Kn o wl edge of the operaHonal implicatlons o f the following concepts as they appty t o 40 Reactor Power Abov e APRM Downscale or 0 6 SCRA M Condition Present and Reactor Pow er A bove APRM Downsca l e o r 4.0 1 Unknown/ 1 1 , U nknown: Cooldown effects on reactor power 52 295038 High Off-site Release Rate/ 9 0 Kn o wl edge o f th e reasons f or th e following re spo n ses as they apply to H igh Off-site 4 Release Rate: Emergency depressurization 3.6 1 48 600000 Plant Fire On Site I 8 0 9 1 , Ab ility t o oper at e and/or mon i tor th e following as they apply to Plant Fire On Site: Pl ant fire zone panel (indu ct ing detector k>catton) 2.5 1 700000 Generator Voltage and Electric Gr i d ' Disturbances I 6 0 . KIA Category Totals: 3 4 3 3 4 3 Group Point Total: r ES-401 , Page 17 of 33 ES-40 1 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abn orma l Plant Evolutions

-Tier 1/G roup 2 (RO) Q# E/APE #I N ame I Safety Function K K K A 1: A G KI A Topic(s) IR # 1 2 3 1 I< 62 1295002 Loss of Main Condenser Va c I 3 0 Ability t o operate and/or monitor the following as they apply t o Loss of Main 5 Condenser Va c: Main turbine 3.2 1 I i l.295007 High R eactor Pressure I 3 ' 0 u , 29500 8 High R eactor W ater Lev el I 2 1 , 0

  • 63 295009 Low Reactor W ater Level I 2 I f 0 Ability to determine and/or interpret the following as they apply to Low Reactor 3.6 1 1., 2 Water Level: Steam flow/feedflow mi s match 1295010 High Drywell Pressure I 5 I t 0 1 . 64 1295011 High Containment Temp I 5 i 04. ' .. 46 Ability to verify that the alarms are consistent with the plant conditions.

4.2 1 295012 High Drywell Temperatu r e I 5 I>>. 0 1 11 1295013 High Suppression Poo l Temp. I 5 1 , '. 0 60 1295014 Inadv ertent Reactivity Addit ion I 1 1 I> Kn owle dg e of the interrelations between Inadvertent Reactivity Addition and the 1 ' foUowing:

Recirculation flow control 3.6 1 61 1295015 Incomplete SCRAM I 1 0 ii ' Knowk!dge of the reasons for the following responses as they apply to In complete *,* 3.4 1 1 SCRAM: Bypassing rod insertion blocks r t* ._ 2 9501 7 H i gh Off-site Re lease Rate I 9 1 1* 0 l 1295020 Inadvert ent Cont. Isolation I 5 & 7 0 . 59 1295022 Loss of CRD Pumps I 1 0 Knowledg e of the operational implications of the following concepts as they apply to 1

  • Loss of CAD Pumps: Reactor pressure vs. rod insertion capability 3.3 1 65 1295029 High Suppression Pool Wt r Lvl I 5 Ability to determine and/or interpret the following as they apply to High Suppression 1 , i Pool W tr Lvl: Suppression pool water level 3.5 1 295032 High Secondary Conta inment Are a IT emperature I 5 0 1295033 High Secondary Containment A rea Rad iation Levels I 9 ' 0 1295034 S eco nd a ry Containment Vent ilation High Radiation I 9 ... 0 l295035 Sec on dary Containment High . Differential Pressure I 5 0 29 5036 Secondary Containment H igh Sump/Area Wate r Level I 5 l ei' 0 .. 500000 High CTMT Hydrog en Cone. I 5 , < 0 IKIA Category Tota ls: 1 1 1 1 '2 1 Group Point Total: 7 ES-401, Page 18 of 33
  • ES-401 4 Form ES-401-1 ES-40 1 BWR Examination Outline Form ES-401-1 11 Plant Systems -Tier 2/Group 1 (RO) 0# System # I Name K K K K K K A A A A G KIA Topic(s) IA I. 1 2 3 4 5 6 1 2 3 4 4 203000 RHR/LPCI:

Injection Mode 0 Knowledge of electrical power supplies to the following: Initiation logic 2.7 1 3 7 205000 Shutdown Cooling 0 Knowledge of Shutdown Cooling design feature(s) and/or interlocks whk:h 3.7 1 2 provide for the following:

High pressure isolation: Plant-Specific 206000 H PCI 0 Isolation (E m erge n cy) 0 Condenser 21 20900 1 LPCS 02. Ability to analyze the effect of maintenance activities , such as degraded power 3.1 1 3 6 sources, on the status of limiting conditions for operations. 0 01. Knowledge of the physical connections and/or cause-effect relationships between 2.5; 2,22 209002 H PCS 9 27 HPCS and the foUowing: Leak detection:

BWA-5, 6; Knowledge of system 3.9 2 purpose and/or functk>n. 17 211000 SLC 0 Ability to monitor automatic operations of the SLC including: Flow indication:

4.1 1 5 Plant-Specific 6 212000 RPS 1 Knowledge of the effect that a loss Of of the RPS will have on 3.0 1 1 following: Recirculation syste m 1 215003 I R M 0 Knowledge of the physical connecttons and/or cause-effect relationships between 3.0 1 7 I AM and the following: Reactor v essel 19 215004 So ur ce R a ng e M on i tor 0 Ability to manually operate and/or monitor in the control room: Alarms and lights 3.2 1 6 0 0 Knowledge of electrical power supplies to the following: APRM channels; 2.6; 3,24 2 1 5005 A PRM I LP RM 2 6 Knowledge of APRM I LPRM design feature(s) and/or inter1ocks which provide 2.6 2 for the following: Effects of detector aging on LPRM/APRM reading s 10, 0 0 Knowledge of electrical power supplies to the f ollowing: Motor operated valves; 2.8; 25 217000 RCIC 1 2 Knowledge of the operational implications of the following concepts as they apply 3.1 2 to RCIC: Flow indicatioo 14 218000 A DS 0 Ability to predK;t and/or monitor changes in parameters associated with operating 3.4 1 1 the ADS contrOO; including: ADS valve tail pipe temperatures 8 223002 PCIS/N u clea r S tea m S upp l y 0 Knowledge of PCIS/Nuctear Steam Supply Shutoff design feature(s) and/or 3.0 1 Shutoff 1 interlocks which provide for the following: Redundancy 18 239002 S R V s 0 Ability to monitor automatic operaUons of the SAVs including: Acoustical monitor 3.6 1 ' 4 noise: Plant-Specttic 11 259002 R eactor W ater Le v el Control 0 Ability to manually operate and/or monitor in the control room: All individual 3.7 1 2 component controllers in the automatic mode Ability to (a) predict the impacts of the following on the SGTS; and (b) based on 1 6 261000 SGTS 1 those predictions, use procedures to correct, control, or mitigate the 3.2 1 1 consequences of those abnormal conditions or operations

High containment pressure Knowledge of the physical connections and/or cause.effect relation ships between 15, AC Electrical Distribution and the following: Emergency generatOfS (dieseViet);

262 0 01 A C Elec t rical D i str ib u tion 0 . 1 Ability to (a) predict the impacts of the following on the AC Electrical Distribution; 3.8; 2 26 1 1 and {b} based on those predichons, use procedures to correct, control, or 3.2 mijigate the consequences of those abnonnaf concitions Of operations

Degraded system voltages 20 262002 U P S (A C/DC) 0 Knowledge of the effect that a loss Of mattunction of the following will have on 2.7 1 the UPS (AC/DC): A.C. electrical power 1 263000 D C Electrical Distribution 0 Knowledge of the effect that a loss or mattunc1ion of the DC Electrical Oistributioo 5 will have on following: Systems wlth O.C. components

{i.e. valves, motors , 3.4 1 3 solenoids.

etc.) : Ability to predict and/or monitor changes in parameters associated with operating 13, 0 0 the EDGs controls including: Operating voltages , currents, and temperatures

264000 EDGs Ability to (a) predict the impacts of the following on the EDGs
and (b) based on 2.8; 2 23 3 3 those predictions , use procedures to correct, control, or mitigate the 3.4 consequences of those abnormal conditions or operations
Operating unloaded , lightly loaded. and highly loaded 9 300000 I nstrume n t A ir ' 1 3 Knowledge of the operational implications of the following concepts as they apply 2.9 lo Instrument Air : Fitters 1 12 400000 Component Cooli n g W a t er 0 Knowledge of the effect that a k>ss or malfunction of the following will have on 2.9 1 6 the Component Cooling Water: Heat exchangers and condensers KIA Category Totals: 3 3 2 3 2 2 2 3 2 2 1/ Group Point Total: 26 ES-4 01 , P age 19 o f 33 ES-401-1 5 Form ES-401-1 ES-401 BWR Ex aminatio n Outline Form ES-401-1 Pla n t Systems -T ier 2 (RO) Q# System # I Nam e K K K K K K A A A A G K/A Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 . Ability to (a) predict the impacts of the following on the CAD Hydraul ic System; 34 1201001 CRD Hydraulic 0 and (b) based on those predictions, use procedures to correct, control, or 3.0 1 3 mitigate the consequences of t hose abnormal conditions or operations
Power suoplv failures 201002 RMCS 0 201003 Control Rod and Drive Mechanism

' 0 201004 RSCS t 0 ' 201005 RCIS 0 201006 RWM i 0 29 ?02001 Recirculation 0 Ab ility to monitor automat i c operations of the Recirculation inclu d ing: Pump trips: 3.3 1 7 Plant-Specific I 1202002 Recirculation Flow Control T 0 ' 1204000 RWCU ' 0 1214000 RPIS ' 0 1215001 Traversing In-core Prob e 0 12 1 5002 RBM 1 1* 0 33 1216000 Nuclear Boiler In st. 0 Ability to predtct and/or monitor changes in parameters associated with 2.9 1 3 operating the Nuclear Boiler Inst. controls including: Surveillance testing 1219000 RHR/LPCI: Torus/Pool Coo l ing 0 Mode 27 223001 Primary CTMT and A u x. 0 ' Knowledge of the physical connections and/or ca u se-effect relationships 3.4 1 6 l between Primary CTMT and A ux. and the following: RHR/LPCI 31 226001 RHR/LPCI:

CTMT Spray Mode 0 Ability to manually operate and/or monitor in the control room: System flow 3.2 1 8 230000 RHR/LPCI:

Torus/Pool Spray Mode 0 28 233000 Fuel Pool Coo lin g/Cleanup 0 Knowledge of the effect that a loss or mattunction of the following will have on 2.5 1 1 the Fuel P ool Cooling/Cleanup

A.C. electrical power 234000 Fuel Handl i ng Equipment " I' 0 .. 36 239001 Ma in and Reheat Steam 0 Knowledge of t he operational implications of the f ollowi ng concepts as they 2.8 1 6 apply to Main and Reheat Steam: A ir operated M SIV's 1239003 MSIV Leakage Con tr ol 0 35 1241000 Reactorffurbine Pressure R eg ula t or 0 . Kno wledg e of the effect t hat a loss or matt unction of the Rea ctor/T urb ine 4.1 1 6 Pressure Regulator will have on following:

Bypass valve s 1245000 Main Turbine Gen. I Aux. 0 1256000 R eacto r Condensate 0 32 1259001 Reactor Feedwater 0 Knowledge of electrical power supplies to the following: RFP auxiliary oil 3 268000 Radwaste I I 0 271000 Offgas 0 272000 Radiation M o nrt oring 0 286000 Fire Protection 0 30 288000 Plant V en t ilatio n 0 Knowledge of Plant Ventilation design fea tu re(s) and/or intertocks wh ich prov i de 3.7 1 , for the following: AutomaUc initia t ion of standby gas tre atment system , , 1290001 Secondary CTMT 0 38 1290003 Cont r ol R oom HVAC 0 Knowledge of th e operational implications of the following c oncepts as they 2.8 1 2 apply to Control Room HVAC : Differential pressure control 37 1290002 Reactor V esse l I nternals 04. Knowledge of th e specific ba ses for EOPs. 3.3 1 18 KIA Category Totals: 1 1 1 1 2 1 1 1 1 1 1 Group Po int Total: 12 ES-40 1, P ag e 20 of 33 ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-4-.. Emergency and A bnormal Plant Evo l utions -Tier 1/Group 1 (SRO) Q# E/AP E #I Name I Sa f ety Fu n ction K K K A A G KI A Topic(s) IA # 1 2 3 1 2 79 295001 Partial or Complete Loss of Forced 02. Ability to recogn i ze system parameters that are entry-level conditions for 4.6 1 Core Flow Circulation I 1 & 4 4 2 Technical Specifications. 295003 Partial or Complete Loss of AC I 6 0 77 295004 P artial or Total Loss of DC Pwr I 6 0 Ability to determine and/or i nterpret the following as they apply to Partial or 2.9 1 3 Total Loss of DC Pwr: Battery voltage 295005 Main Turbine Generator Trip I 3 0 81 295006 SCR A M I 1 0 2. A bility to apply Technical Specifications for a system. 4.7 1 40 82 295016 Control Room Abandonment 17 0 Ab[lity to determine and/or i nterpret the following as they apply to Control 4.3 1 2 Room A bandonment:

Rea c tor water level 29501 B Partial or Total Loss of CC W I B 0 295019 Partial or Total Loss of Inst. A ir I B 0 295021 Loss of Shutdo w n Cooling I 4 < 0 295023 Refueling Ace I 8 1295024 High Drywell Pressure I 5 0 1295025 High Reactor Pressure I 3 0 78 1295026 Suppression Pool High Water '0 Ability to determine and/or interpret the following as they apply to 4.2 1 ITemp. / 5 1 Suppression Pool High Water Temp.: Suppression pool water temperature 76 295027 Hi gh Containment Tempera t ure/ 5 0 A bility to determine and/or interpret the following as they apply to High 3.3 1 I*/ 3 Containment Temperature:

Reactor pressure: Mark-Ill ' 295028 High Drywell Temperature/

5 0 295030 Low Suppression Pool Wtr Lvl I 5 ! 0 ?95031 Reactor Low W ater Level/ 2 0 1295037 SC RA M Condition Present land Reactor Power Above A PRM 0 Do w nscale or Unknown / 1 1295038 H ig h Off-site Release Rate / 9 ; 0 600000 Plant Fire On Site I B 0 BO 700000 Generator V oltage and Electric Grid I C* 02. A bility to determine operability and/or availability of safety related 4.6 1 Disturbances I 6 3 7 equipment.

1 1 KI A Category Totals: 0 0 0 0 I' 4 3 Group P oint Total: , ES-4 0 1, Page 1 7 of 33 ES-401 3 Form ES-401-1 ES-401 BWR Examinat io n Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2 (SRO) Q# E/APE #I Name I Safety Function K K K A A G KIA Topic(s) IA # 1 2 3 1 2

  • 295002 Loss of Main Condenser Vac I 3 0 83 295007 High Reactor Pressure I 3 0 Ability to d e termine and/or interpret the following as they apply to High Reactor 4.1 1 2 Pressure: Reactor power 295008 High Reactor Water Level I 2 0 295009 Low Reactor Water Level I 2 0 1295010 High Drywell Pressure I 5 0 1295011 High Containment Temp I 5 > 0 04. Kn owledge of the parameters and logic used to assess the status of sa f ety 84 1295012 High Drywell Temperature I 5 21 functions. such as reactivity control, core coofing and heat removal , reactor coolant 4.6 1 system integrity, containment conditions, radioactivity release control , etc. 1295013 High Suppression Pool Temp. I 5 0 1295014 Inadvertent Reactivity Addi tion I 1 0 295015 Incomplete SCRAM I 1 0 I* 295017 High Off-s ite Release Rate I 9 0 .. 295020 Inadvertent Cont. Isolation I 5 & 7 0 295022 Loss of CAD Pumps I 1 I t 0 ' 1295029 High Suppression Pool Wtr Lvl I 5 0 85 1295032 High Secondary Containment Ar ea o* Ability to determine and/or interpret the following as they apply to High Secondary 3.8 1 IT emperature I 5 1 Containment Ar ea Temperature
Are a temperature 1295033 High Secondary Containment Area 0 Radiation Levels I 9 295034 Secondary Containment Ventilation 0 High Radiation I 9 295035 Secondary Containment High 0 Differential Pressure I 5 295036 Secondary Containment High 0 Sump/Area Water Level I 5 500000 High CTMT Hydrogen Cone. I 5 0 KIA Category Totals: 0 0 0 0 2* 1 Group Point Total: 3 ES-401 , Page 18 of 33 ES-401 4 Form ES-401-1 ES-401 BWR Examin atio n Outline Form ES-401-111 Plant Systems -Ti er 2/Group 1 (SRO) Q# System # I Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 88 203000 RHR/LPCI: Inj ection 01. 20 Ability t o interpret and execute procedure steps. 4.6 1 0 A bility to (a) predict the impacts of the follo wi ng on the Shu td own Coo ling: and 86 205000 Shutdown Cooling Mod e 3 (b) based on those predictions, use procedures t o correct, control, or mi tigate 3.2 1 the consequences of tho se abnormal conditions o r ope r ations: A.C. failure 2 06000 HPCI 0 207000 Isolation (Emergency) 0 Condenser 209001 LPCS 0 209002 HPCS 0 *' 211000 SLC 0 21200 0 RPS 0 215003 IRM 0 215 004 Sourc e Range Monitor 0 1215005 APRM I LPRM 0 89 217000 RCIC 04. Knowledge of low power/shutdown i mpl ications in accident (e.g., k>ss of 4.2 09 coolant accident or loss of residual heat removal) mitigat io n strategies.

1218000 AD S 0 223002 PCIS/Nuclear Steam Supply A bil ity to (a) predict the impa c t s of the f o ll owi ng on the PCIS/Nudear Steam 87 0 Supp ly Shutoff; and (b) based on th ose predictions , use procedures to correct, 3.2 1 Shutoff 1 , 2 contro l , or mitigate the consequences o f those abnormal condi t ions or operations:

O.C. electrica l dist ri bution failures 239 002 SRV s 0 1; . 259002 Re ac tor Water Level Con t rol 0 261000 SGTS 0 262 001 AC Electrical Di s tribution 0 I< 26200 2 UPS (AC/DC) 0 -0 Ability to (a) predict the impacts of the f o ll o wi ng on the DC Elec tri ca l 90 263000 DC Electrical Distribution Distribution; and {b) based on those predictions, use procedures to correc t , '<1 control, or mitigate the consequ.ences of t hose abnorma l con d itions or 3.2 1 \. ooerations:

Grounds 264000 EDG s / 0 ' 300000 Instrument A ir 1 1-0 I I 400000 Component Cooling Water I" 0 1 r

  • KIA Category Totals: 0 0 0 0 0 0 0 1;3 0 0 Group Poin t Total: 5 ES-4 01 , Page 19 of 33 ES-401 5 Form ES-401-1 ES-401 B WR E xamination Outline Form ES-401-1 Pla n t Sy stems -Tier 2/Group 2 (SRO) Q# System # I Name K K K K K K A A A A \, KIA Topic(s) 1 2 3 4 5 6 1 2 3 4 G IR # 20 1001 CRD Hydrauli c ; 0 ?01002 RMCS !*. t I 0 201003 Control Rod and Drive Mechanism

, f ' 0 201004 RSCS 0 1201005 RCIS 0 1201006 RWM 0 1202001 Recirculat io n J 0 ' Ab i lity to (a) predict the impacts of the following on th e Rec i r cu lation Flow 93 1202002 Recirculation Flow Control 0 Control; and (b) based on those predictions , u se pr ocedures to co rrect , control , 3.3 1 9 ,, or mitigate the consequences of those abnormal conditions or operations

R ecirc ulation flow m ismatch: Pl an t-Specific l204000RWCU 0 Ability t o (a) predict the impact s of the following on the RWCU; and (bl. based 91 6 on those p redictions , use p roced ur es to correct, control, or mitigate the 2.6 1 *' consequences of those abnormal conditio ns or operations
A.C. fallure 92 1214000 RPIS 0 2. Knowledge of the bases in Techn ical Specifications for limiting co nditions for 4.2 1 *25 operations and safety limits. 1215001 Traversing In-core Probe 0 1215002 RBM 0 1216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 0 Mode ' 22 3001 Primary CTMT and A ux. 0 226 001 RHR/LPCI: CTMT Spray Mode 0 2 30000 RHR/LPCI: Torus/Pool Spray Mode I : 0 233 000 Fuel Pool Coo ling/Clea.nup I 0 , .. 234000 Fuel Handling Equipment I' -0 2 39001 Main and Reh e at Steam 0 1239003 MSIV Leakage Control 1:* 0 1241000 Reactor/Turbine Pressure Regula t or 0 1245000 Main Turbine Gen. I A ux. 0 1256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radw as te 0 271000 Offgas 0 2 72000 Radiation Monitoring 0 286000 Fire Prote ctio n 0 2 88000 Plant Ventilat io n 0 1290001 Secondary CTMT 0 1290003 Control Room H V AC 0 1290002 Reactor Vessel Internal s 0 KI A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401 , Page 20 of 33 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 !Facil i ty Name: Cl i nton Date of Exam:3/16/2015 I Categ o ry KIA# Top i c RO SHU-On l y -IR IR Q# # # 94 2.1. 34 Knowledge of primary and secondary plant chemistry limi t s. 2.7 3.5 1 -98 2.1. 09 Ability to direct personnel activities inside the control room. 2.9 4.5 1 -66 2.1. 45 Ability to identify and interpret diverse indications to validate the response of another 4.3 1 4.3 1. indicator. -67 Conduct of 2.1. 29 Knowledge of how to conduct system lineups, such as valves , breakers , switches , etc. 4.1 1 4.0 -Operations 75 2.1. 32 Ability to explain and apply system limits and precautions. 3.8 1 4.0 -2.1. -Subtotal 3 2 95 2.2. 15 Ability to determine the expected plant configuration using design and configuration 3.9 4.3 1 control documentation , such as drawings, line-ups , tag-outs. etc. -100 2.2. 14 Knowledge of the process for controlling equipment configuration or status. 3.9 4.3 1 -68 2. 2.2. 22 Knowledge of limiting conditions for operations and safety limits. 4.0 1 4.7 -69 Equipment 2.2. 21 Knowledge of pre-and post-maintenance operability requirements. 2.9 1 4.1 ,___ Contro l 2.2. -2.2. --Subtota l 2 2 96 2.3. 05 A bility to use radiat i on monitoring systems, such as fixed radiation monitors and alarms , 2.9 2.9 1 portable survey instruments.

personnel monitoring equipment. etc. ,____ Knowledge of radiological safety procedures pertaining to l icensed operator dut i es. such 99 2.3. 13 as response to radiat i on monitor alarms. containment entry requirements , fuel handling 3.4 3.8 1 responsibilities. access to locked high-radiation areas , alig n ing filters , etc. -7 0 3. 2.3. 11 Ability to control radiation release s. 3.8 1 4.3 -Radiat i on 71 Control 2.3. 15 Knowledge of radiation monitoring systems. such as fixed radiation monitors and alarms , 2.9 1 3.1 portable survey instruments.

personnel monitoring equipment, etc. -7 4 2.3. 14 Knowledge of radiation or contamination hazards that may arise during normal , abnormal , 3.4 1 3.8 or emergency conditions or activities. -2.3 . .......__

-Subtotal 3 2 97 2.4. 25 Knowledge of fire protection procedures.

3.3 3.7 1 ,____ Knowledge of EOJ;' implementat i on hierarchy and coordination with other support 72 2.4. 16 procedures or guidelines such as, operating proced u res. abnormal operating procedures, 3.5 1 4.4 -and severe accident manaoement ouidel i nes. 73 4. 2.4. 04 Ability to recognize abnormal indications for system operating parameters that are entry-4.5 1 4.7 level conditions for emergency and abnormal operating procedures. -Emergency Procedures 2.4. -I Plan 2.4. -2.4. -Subtotal 2 1 Tier 3 Po i nt Total 10 7 ES-401 , Page 26 of 33 Written Exam Status NUREG-1021-Rev 9 Sup 1 Criteria "O :>: "O :>: "O :>: "O :>: GI :>: GI :>: GI :>: 0 GI :>: 0 "O GI 0 "O GI 0 "O GI a: "O GI a: GI > GI > "O GI a: GI > GI *:.; "O GI > GI *:.; "O GI > GI > "O > GI GI "O *:.; GI GI a: "O GI > GI GI I/) "O GI > GI GI GI 0 GI GI GI 0 GI 0 GI 0 c. a: iii c. GI a: iii GI a: iii GI IF-u D:. a: c u D:. a: c u Cl D:. a: *;:: u Cl ll: a: GI :0 .I::. :!:? Cl GI :0 .I::. :!:? Cl GI :0 .I::. :!:? Cl GI :0 .I::. Qi -,.. 0 iii ;;; ,.. 0 ;;; ,.. 0 ;;; ,.. .. GI GI Ul GI 0 .. Qi GI Ul GI iii 0 .. Qi GI Ul GI iii 0 .. Qi GI Ul 0 I/) a. a: a. I-> (.) 0 I/) a. a: a. I-> (.) 0 I/) a. a: a. I-> (.) 0 I/) a. a: a. f-Total 100 10 0 0 0 6 3 ' .Jo, ,4 !* ,,, . ** I ,,, *1*, ; 25 2 0 0 0 19 25' 1 0 0 0 10 25 1 0 0 0 12 25 6 0 0 1 x N M 26 x N M 51 x N M 76 x N 2 x B H 27 x M M 52 x B M 77 x N 3 x B M 28 x B M 53 x B M 78 x M 4 x B H 29 x B M 54 x M H 79 x M x 5 x B H 30 x B M 55 x N M 80 x N 6 x N H 31 x N H 56 x N H 81 x N 7 x N x H 32 x N M 57 x N H 82 x N 8 x B M 33 x N M 58 x M H 83 x N x 9 x N M 34 x N H 59 x B H 84 x B 10 x B H 35 x B H 60 x B M 85 x B 11 x N H 36 x N M 61 x B M 86 x N 12 x B H 37 x B M 62 x B x H 87 x N 13 x N H 38 x N M 63 x N H 88 x N 14 x N H 39 x N H 64 x B M 89 x N 15 x B H 40 x B M 65 x B H 90 x N 16 x N H 41 x B M 66 x N H 91 x N 17 x B M 42 x M H 67 x N M 92 x N 18 x N H 43 x B H 68 x B M 93 x N 19 x B H 44 x N M 69 x N M 94 x B x 20 x B H 45 x B M 70 x B M 95 x N x 21 x N H 46 x N x H 71 x B M 96 x M 22 x B H 47 x N H 72 x N H 97 x B x 23 x N x H 48 x B M 73 x B H 98 x B 24 x B M 49 x B H 74 x N H 99 x B x 25 x B H 50 x B H 75 x B M 100 x N *" "' <"' , .. '" ' " *)4 ,., . : !Qu es tio ns Ready_ to Validate RO Ex am T o t a ls Combi n ed E x am Total s Memory (30-37) Memory Memory Higher (38-45) Higher Higher New High New High \lew High New New New Modified Modified Modified Bank Bank (<76) Bank (<19) Ref Pr o vid e d Ref Provided (<11) Provided (<7) Selected -draft question was found in any ban k or new question dr afted OR questi o n is ready for psychometric or techn ical reviews (X is ready for review I D is draft ed) Pedigree -Qu es tion ped igree New I Mod i fied I Dir ect from B ank Ref Provided -A re fer ence is provid ed for th e quest ion (X-ye s) Reviewed -question has b een checked for Techn ical accuracy , Psy cho m etrics , KIA match, and SRO only applicability. (X is OK I T , P , K or S i ndi cates issue) Validated

-question validated by operators (X) Cognigitive

-Question cognit ive l evel Memory I High er (Comprehens i o n , An a lysis , etc) Exelon Nuclear Confidential 1/13/2015 "O GI .! "' c :!:? Cl iii 0 > (.) 0 22 H H H H H H H H H H H H H H H H M H H H H H M H M 3 22

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