ML20260H152
| ML20260H152 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/14/2019 |
| From: | Exelon Generation Co |
| To: | Todd Fish Operations Branch I |
| Fish T | |
| Shared Package | |
| ML19105A122 | List: |
| References | |
| CAC 000500 | |
| Download: ML20260H152 (28) | |
Text
ES-301 Administrative Topics Outline FormES3011 Facility: JamesA.Fitzpatrick Date ofExamination:Feb2020 Examination Level: RO Operating Test Number:18-1 Administrative Topic (see Type Describe tobeperformed activity Note) Code*
Core Thermal Heat Balance Verification Using Turbine Conduct ofOperations P, D,R Steam Pressure 17-1 NRC K/A2.1.19 (3.9),OP-65, RAP-7.3.03 Perform RCICLineup Verification PerST-24A Conduct ofOperations N,S K/A 2.1.31 (4.6), ST-24A Explain RPS Operation UsingElectrical Drawings Equipment Control M,R K/A2.2.41 (3.5), 1.60-17, 1.67-97, 1.67-99, 1.67-101 Determine Worker Exposure forEmergent Work Radiation Control D,R K/A2.3.4 (3.2),RP-AA-203 NOTE:All items (five are total) required forSROs.ROapplicants requireonly four items unless they areretaking onlytheadministrative topics (which would requireallfive items).
TypeCodes andCriteria: (C)ontrol room, (S)imulator, orClass(R)oom (D)irect from bank(5 3for ROs;s4 for SROsandROretakes)
(N)ew or(M)odified from bank (21)
(P)revious 2 exams (51,randomly selected)
ES-301 Administrative Topics Outline FormES-301-1 Facility: James A.Fitzpatrick Date ofExamination:Feb2020 Examination Level: SRO Operating Test Number: 18-1 Administrative Topic (see Type Describe activity tobeperformed Note) Code*
Core Thermal Heat Balance Verification Using Turbine P, D,R Steam Pressure Conduct ofOperations 17-1 NRC K/A2.1.19 (3.8), OP-65, RAP-7.3.03 Determine ReportabilityRequirements -
Technical Conduct ofOperations N,R Specification Shutdown andGroup IIsolation K/A 2.1.18 (3.8), NUREG 1022, LS-AA-1400 ExplainRPS Operation Using Electrical Drawings and DetermineTechnical Specification Impact ofInoperability Equipment Control M,R K/A2.2.41 (3.9), 1.60-17, 1.67-97, 1.67-99, 1.67-101, Technical Specification 3.3.1.1 Determine Worker Exposure forEmergent Workand Radiation Control D,R Required Actions K/A2.3.4 (3.7), EN-RP-201 Determine Emergency Classification and Initiate Event Emergency Plan M,R Notification K/A2.4.40 (4.5), EP-AA-1014, EP-CE-114-100 NOTE:All items (five arerequired total) forSROs.ROapplicants require only four itemsunless they areretaking onlytheadministrative topics (which would require allfiveitems).
TypeCodes andCriteria: (C)ontrolroom, (S)imulator, orClass(R)oom (D)irect (5 Os;s4 for from b ank 3 for R SROsandROretakes)
(N)ew or(M)odified(21)from b ank (P)revious2 exams (51,randomly selected)
ES-301 Control Room/in-Plant Systems Outline FormES-301-2 Facility: James A.Fitzpatrick Date ofExamination:Feb2020 ExamLevel: RO /SRO-I Operating TestNumber:18-1 Control RoomSystems:* 8 for RO,7for SRO-I, and2 or3for SRO-U System/JPM Title TypeCode* Safety Function a.Control RoomHeating, Ventilation and AirConditioning /Isolate Control RoomandRelay RoomVentilation P,D,EN,S 9
17-1NRC K/A290003 A4.01(3.2/3.2),
OP-55B b.Reactor System Feedwater /Transfer Feedwater Level Control to Master-Auto, LevelDrifts Low M,A,L,S 2 K/A259001 A4.01(3.6/3.5),
OP-2A c.LowPressure CoreSpray /Shutdown Core Spray Following Terminate/Prevent andSubsequent Injection N,L,EN,S 4 K/A209001 A4.01(3.8/3.6),
EP-5, OP-14 d.A.C. Distribution Electrical /Restore L34toNormal Power Source, Lossof10400 Bus D, A, S 6 K/A262001 A4.01(3.4/3.7),
OP-46A, AOP-17 e.Primary ContainmentIsolation System /Nuclear Steam Supply Shut-Off Group
/Reset 2 Isolation, RestoreRWCU,RWCUSteam Leak M,A,EN,S 5 K/A223002 A4.03 AOP-15, (3.6/3.5), OP-28 f.Control RodDriveHydraulic System /Restore CRDtoNormal Alignment ATWS,CRDController Following Fails inAutomatic D,A,S 1 K/A201001 A2.07 EP-3, (3.2/3.1), OP-25 g.Main andReheat Steam System /Perform Main Steam System Shutdown N,L,S 3 K/A239001 A4.01 OP-1 (4.2/4.0),
h.Average PowerRange Monitor/Local Power Range Monitor /
K/A215005 A4.06(3.6/3.8),
OP-16 D,S 7
in-Plant Systems:* 3for RO,3for and3or2for SRO-l, SRO-U i.Primary Containment System Isolation /Nuclear Steam Supply P,D,A,E Shut-Off /Restore H2/O2 MonitorsFollowing Isolation 5 17-1NRC K/A223002 A2.09(3.6/3.7), EP-2, OP-37 j.D.C. ElectricalDistribution /Perform In-PlantActions forStation Blackout D,R,E 6 K/A295003 AA1.04 (3.6/3.7), AOP-49 k.Control RodDrive Hydraulic System /Swap CRDFlow Control Valves D,R 1 K/A201001 2.1.20 (4.6/4.6), OP-25 AIIROandSRO-I room(and control in-plant)systems mustbedifferent andserve safety different functions,all five SRO-Usystemsmustserve different safety functions, andin-plantsystems and functions mayoverlap those tested inthe control room.
Type Codes Criteria for R/SRO-l/SRO-U (A)Iternatepath 4-6/4-6 /2-3 (C)ontrolroom (D)irect from bank 5 9/s 8/s 4 (E)mergency orabnormal in-plant 2 1/21/21 (EN)gineered safety feature 2 1/2 1/21(control roomsystem)
(L)ow-Power/Shutdown 2 1/2 1/21 (N)ew or(M)odified from 1(A) bankincluding 2 2/2 2/21 (P)revious2 exams s3/s3/s2 (randomly selected)
(R)CA 2 1/2 1/21 (S)imulator
Appendix D Scenario Outline FormESD-1 Facility: Jh Scenario No.:NRC-1 Op-Test No.: j8-1 Examiners: . .
Operators:
Initial Conditions:The plant is operating atapproximately 93%power. RBCLC pumpA isoutof service formaintenance. SRV A is inoperable. Line3isout ofservice andready toberestored.
Turnover: RestoreLine 3toservice per OP-44 G.9.Then, raise Reactor to98%using power Recirculation flow.
Event Malf. Event Event No. No. Type* Description N -
RestoreLine 3toService 1 N/A BOP, SRO OP-44 R -
Raise Reactor Power with Recirculation Flow 2 N/A ATC, SRO OP-27 C - Loss ofOffsitePower 3 ED44 SRO AOP-72, TechnicalSpecifications C -
SRVInadvertently Opens 4 AD06:C BOP, SRO AOP-36, TechnicalSpecifications FW05:A Feedwater PumpVibration andDelayed PumpTrip 5 C All FW01:A ARP09-6-4-11, AOP-41 Steam LeakinDrywell AOP-39, AOP-1 Loss ofCoolant Accident 7 RR15:A M All -
FirstTorus Spray Valve UsedFails toOpen 8 Remote ATC, SRO EOP-4 9 HPO2 C All EOP-2 (N)ormal, (R)eactivity,(1)nstrument, (C)omponent, (M)ajor
I Appendix D ScenarioOutline FormES-D1 Facility: James A.Fitzpatrick SCenario No.:
NRC-1 Op-Test 18-1 No.:
1.Malfunctions afterEOPentry (1-2) 2 Events 8& 9 2.Abnormal events (2-4) 4 Events 3,4,5,6 3.Major transients (1-2) 1 Event 7 4.EOPsentered/requiring substantive actions(1-2) 2 EOP-2, EOP-4 5.Entry acontingency into EOPwith substantive 2 actions (21per scenario set)
EOP-2 Alternate Level Control Leg EOP-2 Emergency Depressurization Leg 6.Pre-identified critical tasks (22) 2 CRITICAL TASKDESCRIPTIONS:
CT-1: Given acoolant leakinside theContainment, thecrew will spray theDrywell, inaccordance with EOP-4. Drywell spray mustbeinitiated within15 minutes ofTorus pressure exceeding 15psig.
CT-2: Given a coolant leak,a loss ofhighpressure injection systems, andtheinability torestoreand maintain Reactor water levelabove theTopofActive Fuel (TAF), thecrew will initiate actions an for Emergency RPVDepressurization, inaccordance with EOP2.Reactor water level mustberestored andmaintained above TAFwithin thirty minutesof lowering below TAF.
Appendix D Scenario Outline FormES-D-1 Facility: h Scenario No.:NRC-2 Op-Test j8-1 No.:
Examiners: Operators:
Initial Conditions:The plant is operating atapproximately 71%power. RBCLCpumpA isoutof service formaintenance.
Turnover: SwapFeedwaterlevel control from level column A toB per OP-2A G.27.
section Then, erform aControl Rod attern ad'ustment inaccordance with Reactor En ineerin instructions.
Event Malf. Event Event No. No. Type* Description N -
SwapFeedwater Level Control Instruments 1 N/A BOP, SRO OP-2A R -
performControl Rod Pattern Adjustment 2 N/A ATC, SRO OP-26 C -
CRDFlow ControlValve Fails Closed 3 RD03:A ATC, SRO OP-25 Recirc Flow UnitFailure 4 RR23:B I All -
OP-16, Technical Specifications C -
Loss ofRBCLCFlow toRecirculation PumpB 5 SW01:B BOP, SRO OP-27, AOP-8, Technical Specifications Thermal Hydraulic Instability AOP-8, AOP-1 Hydraulic toScram Failure 7 m M M -
EOP-3 C -
InadvertentGroup Iisolation 8 RP03 BOP, SRO EOP-3 C -
FirstSLCPumpDelayed Trip 9 SL01 ATC, SRO EOP-3 (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline FormES-D-1 Facility: James A.Fitzpatrick Scenario NRC-2 No.: Op-Test 18-1 No.:
1.Malfunctions after EOPentry (1-2) 2 Event 8& 9 2.Abnormal events (2-4) 2 Events 5& 6 3.Major transients(1-2) 1 Event 7 4.EOPs entered/requiring substantive actions(1-2) 1 EOP-2 5.Entry acontingency into EOPwith substantive 1 actions (21per scenario set)
EOP-3 6.Pre-identified criticaltasks (22) 2 CRITICAL TASKDESCRIPTIONS:
CT-1: Given afailure toscramwith Reactor power above 2.5%, thecrew willlower Reactor power by oneormoreofthefollowing methods, inaccordance with EOP-3:
Terminating andpreventing all RPVinjection except SLC,RCIC, andCRD Tripping Recirculation pumpA Injecting boron TheReactor power reduction mustbeinitiated within five minutes ofthestart ofthefailure toscram.
CT-2: Given afailure toscram, thecrew willinitiate Control Rodinsertion, inaccordance withEOP3.All insertable control rods mustbeinserted withinone hourofthestart ofthefailure toscram.
Appendix D Scenario Outline FormES-D-1 Facility: W Scenario No.:NRC-3 Op-Test No.: j8-1 Examiners: Operators:
Initial Conditions:The plant is operating atapproximately 100%power. RBCLC pumpA isoutof service formaintenance.
Turnover: Swa CRD um s er OP-25 section G.10.
Event Malf. Event Event No. No. Type* Description N -
Swap CRD Pumps 1 N/A BOP, SRO OP-25 R -
Condensate Booster Pump Trips 2 FW25:C ATC, SRO ARP09-6-3-22, AOP-41, RAP-7.3.16 3 NM14:A ISRO ATC' APRMFails As-Is ARP09-5-2-2(44), OP-16 4
HP05 I BOP, HPCIInadvertently
- Initiates; Turbine Trip Pushbutton Fails override SRO AOP-77, AOP-32, Technical Specifications EPICFails 5 YC01 I-SRO ARP09-8-1-4, ST-40C, Technical Specifications Remaining Condensate Booster PumpsTrip AOP-41, AOP-1, EOP-2 RR33 Steam Leak inDrywell 7 M All-MSO2 EOP-2, EOP-4 BOP' RCICFails toAutomatically Start RCO2 ISRO 8
EOP-2 RR33 RR16 Multiple Level Instrument Failures 9 RR17 I AII RR19 RR31 (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor
Appendix D ScenarioOutline FormESD-1 Facility: James A.Fitzpatrick Scenario NRC-3 No.: No.:
Op-Test 18-1 1.Malfunctions after EOPentry (1-2) 2 Event 8& 9 2.Abnormal events (2-4) 3 Events 2,4,6 3.Major transients (1-2) 1 Event 7 4.EOPsentered/requiring substantive actions(1-2) 2 EOP2,EOP4 5.Entry acontingency into EOPwith substantive 1 actions (21per scenario set)
EOP-7 6.Pre-identified critical tasks (22) 2 CRITICAL TASKDESCRIPTIONS:
CT-1: Given acoolant leakinside theContainment, thecrew will spray theDrywell, inaccordance with EOP4.Drywell spray mustbeinitiated within15 minutes ofTorus pressure exceeding 15psig.
CT2:Given anunknown Reactor water the level, crew will flood theRPV,inaccordance with EOP7.
TheRPVmustbeflooded totheMainSteam Lines within 30minutes ofwhenReactor waterlevel becomes unknown.
Appendix D Scenario Outline FormESD1 Facility: Jh ScenarioNo.:NRC-4 Op-Test J.8-1 No.:
Examiners: Operators:
Initial Conditions:The plant is operating atapproximately 90%power. RBCLCpumpA is outof service formaintenance. Torus Cooling is following inservice completion ofRCICsurveillance testing.
Turnover: Secure Torus Cooling per OP-13B. Then, raise Reactor power using control rodsand Recirculation flowertherovided reactivit instructions.
Event Malf. Event Event No. No. Type* Description N- SecureTorus Cooling 1 N/A BOP, SRO OP-13B C - RHRSW PumpsTrip 2 SW04:A SRO ARP09-3-1-25, Technical Specifications R -
Raise ReactorPower withControl Rods andRecirculationFlow 3 N/A ATC, SRO OP-65, OP-26 C -
Stuck ControlRod 4 RD10 ATC, SRO OP-25 C -
RCICSteam Leak, Fails toAutomatically Isolate 5 RC09 BOP, SRO ARPs,EOP-5, Technical Specifications Loss ofMain Condenser Vacuum 6 MC01 C All AOP-31, AOP-1, EOP-2 Coolant LeakinDrywell 7 m M M-EOP-2, EOP-4 C TenControl RodsFail toScram; CRDDrive Water Pressure 8 RD13 ATC, Control ValveFails As-Is SRO EOP-3 FW01 C -
Feedwater PumpsTrip; HPCIFails toAutomatically Start 9 BOP, HP01 SRO EOP-2/3 (N)ormal, (R)eactivity, (I)nstrument,(C)omponent, (M)ajor
Appendix D Scenario Outline FormES-D-1 Facility: James A.Fitzpatrick SCenario NRC4 No.: No.:
Op-Test 18-1 1.Malfunctions after EOPentry (1-2) 2 Events 8& 9 2.Abnormal events (2-4) 2 Events 5& 6 3.Major transients(1-2) 1 Event 7 4.EOPsentered/requiring substantive actions(1-2) 2 EOP-2, EOP4 5.Entry acontingency into EOPwith substantive 1 actions (21per scenario set)
EOP-3 6.Pre-identified critical tasks (22) 3 CRITICAL TASKDESCRIPTIONS:
CT-1: Given acoolant leakinside theContainment, thecrew willspray theDrywell, inaccordance with EOP4.Drywell spray mustbeinitiated within15 minutes ofTorus pressure exceeding 15psig.
CT2:Given acoolant leakinside theContainment anddegraded high pressure injection sources, the crew will establish injection totheReactor, in accordance with EOP-2 and/or EOP3.Injection mustbeestablished suchthat Reactor water level doesnotlower below -19".
CT-3: Given a failuretoscram, thecrew initiate will Control Rodinsertion, inaccordance with EOP-3. All insertable control rods mustbeinserted withinone hour ofthestart ofthefailure toscram.
ES-401 1 FormES-401-1 Tier Group ROK/ACategory Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total 1, 1 4 4 3 3 3 3 20 4 3 7 Emergency and 2 1 1 1 N/A 2 1 N/A 1 7 2 1 3 Abnormal Plant EvolutionsTier Totals5 5 4 5 4 4 27 6 4 10 2 1 2 2 3 2 2 3 2 2 3 2 3 26 3 2 5 Plant 2 2 0 1 1 1 1 1 1 1 2 1 12 0 1 2 3 Systems TierTotals4 2 4 3 3 4 3 3 4 4 4 38 4 4 8 3.GenericKnowledge andAbilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 1 3 2 2 1 2 Note: 1. Ensurethatatleasttwotopics from every applicable K/A category are sampled within eachtier oftheROand SRO-onlyoutlinesections (i.e.,
except foronecategory in Tier 3oftheSRO-only section, the"Tier Totals"in eachK/Acategory shallnotbeless than two). (one Tier3 radiation control K/A isallowed ifi t i sreplaced by a K/Afromanother Tier3 category.)
- 2. Thepointtotalfor each group andtier inthe proposed outline must match that specified inthe table. Thefinal point total foreach group andtier maydeviate by11from that specified inthe table based onNRCrevisions.
ROexammusttotal Thefinal 75points, andtheSRO-only exammusttotal 25points.
- 3. Systems/evolutions within each group areidentified onthe outline. Systems or evolutions that donotapply at should thefacility bedeleted withjustification.
Operationally important, site-specific systems/evolutions that arenotincludedontheoutline should beadded. RefertoSection D.1.b ofES-401 for guidance regarding the ofinappropriate elimination K/Astatements.
- 4. Select topicsfrom asmanysystems andevolutions aspossible. Sample every systemor evolution inthe groupbeforeselectinga second topicfor anysystem orevolution.
- 5. Absenta plant-specific priority, only those K/As having animportance rating (IR) of2.5orhigher. Use theRO andSROratings fortheROandSRO-only portions, respectively.
SROtopics
- 6. Select forTiers 1 and2 from theshaded systems andK/Acategories.
- 7. Thegeneric(G) K/As i n Tiers 1and 2shall be selected from S ection 2 ofthe K/Acatalog, but thetopicsmust berelevanttothe applicableevolution orsystem. Refer toSection D.1.b ofES-401 for the applicable K/As.
- 8. Onthefollowingpages, enter theK/Anumbers, a brief description ofeach topic, the topics'IRsfor the applicable licenselevel,andthepoint totals(#) for eachsystem andcategory. Enter thegroup andtier totals for eachcategory inthetable above. Iffuel-handling equipment issampled ina category other than CategoryA2 orG*onthe SRO-only exam,enter itonthe left side ofColumn A2for Tier 2,Group 2.(Note 1 doesnotapply.) Useduplicate pages forROandSRO-only exams.
9.ForTier3,select topicsfrom Section 2 ofthe K/Acatalog, andenter theK/Anumbers, descriptions, IRs,and point (#)
totals onFormES-401-3. LimitSROselections toK/As that are linked to10CFR55.43.
G* Generic K/As Thesesystems/evolutions mustbeincluded aspart (as ofthesample applicable tothe facility)whenRevision 3 oftheK/Acatalog isused todevelop the sample plan. Theyarenotrequired tobeincluded whenusing earlier oftheK/Acatalog.
revisions Thesesystems/evolutions maybeeliminated from (as thesample applicable tothe facility) whenRevision 3 of theK/Acatalog isused todevelop the sample plan.
ES401 2 FormES401-1 ES-401 BWRExamination Outline FormES-401-1 Emerenc andAbnormal Evolutions-Tier Plant 1/Group 1(RO/SRO E/APE # /Name/ Safet Function K1 K2 K3 A1 A2 G* K/ATo ics IR Q#
295021 (APE 21)Loss of Shutdown Cooling / X 2.1.23 Ability toperform specific system and4.4 76 4 integrated plant procedures during all modes ofplant operation.
295023 (APE 23)Refueling Accidents /8 X AA2.03 Ability todetermine and/or interpret 3.8 77 the following asthey apply toREFUELING ACCIDENTS: Airborne contamination levels 295018 (APE 18)Partial orComplete Loss of X AA2.02 Ability todetermine and/or interpret 3.2 78 CCW/8 the following asthey apply toPARTIAL OR COMPLETE LOSSOFCOMPONENT COOLING WATER: Cooling water temperature 295030(EPE 7)LowSuppression PoolWater X 2.2.38 Knowledge ofconditions and 4.5 79 Level
/5 limitations inthe facilit license.
295037 (EPE 14)Scram Condition Present X EA2.01 Ability todetermine and/or interpret 4.3 80 andReactor PowerAbove APRMDownscale the following asthey apply toSCRAM orUnknown /1 CONDITION PRESENT ANDREACTOR POWER ABOVE APRMDOWNSCALE OR UNKNOWN: Reactor ower 295004 orComplete Partial Loss ofD.C. X AA2.03 Ability todetermine and/or interpret 2.9 81 Power thefollowing asthey apply toPARTIAL OR COMPLETE LOSS OFD.C. POWER:
Battevolta e 295038 (EPE 15)High Offsite Radioactivity X 2.4.20 Knowledge of theoperational 4.3 82 ReleaseRate /9 implications ofEOP warnings, cautions,and notes.
295001 (APE 1)PartialorComplete Lossof X AK2.07 Knowledge oftheinterrelations 3.4 1 ForcedCore FlowCirculation /1&4 between PARTIAL ORCOMPLETE LOSS OFFORCED CORE FLOWCIRCULATION andthe followin :Core flow indication 295003 (APE 3)PartialorComplete Lossof X AA2.02 Ability todetermine and/or interpret 4.2 2 ACPower /6 thefollowing asthey apply toPARTIAL OR COMPLETE LOSSOFA.C. POWER:
Reactor ower/ ressure /andlevel 295004 (APE 4)PartialorTotal Loss ofDC X AA2.03 Ability todetermine and/or interpret 2.8 3 Power/6 thefollowing asthey apply toPARTIAL OR COMPLETE LOSSOFD.C. POWER:
Battevolta e 295005 (APE 5)MainTurbine Generator Trip / X 2.4.31 Knowledge ofannunciator alarms, 4.2 4 3 indications, orres onserocedures.
295006 (APE 6)Scram /1 X AK3.06 Knowledge ofthereasons for the 3.2 5 following responses asthey apply to SCRAM: Recirculation pumpspeed reduction: Plant-Specific 295016 (APE 16)Control RoomAbandonment X AK3.01 Knowledge ofthe reasons for the 4.1 6
/7 following responses asthey apply to CONTROLROOMABANDONMENT:
Reactor SCRAM 295018 (APE 18)Partial orComplete Loss of X AK1.01 Knowledge oftheoperational 3.5 7 CCW/8 implications ofthe followingconcepts as they apply toPARTIAL ORCOMPLETE LOSSOFCOMPONENT COOLING WATER: Effects oncomponent/system operations
ES401 3 FormES-401-1 295019(APE 19)PartialorComplete Lossof X AA1.01 Ability tooperate and/or monitor the3.5 8 InstrumentAir /8 following asthey apply toPARTIAL OR COMPLETE LOSSOFINSTRUMENT AIR:
Backuair su I 295021 (APE 21)Loss of Shutdown Cooling/ X AA1.02 Ability tooperate and/or monitor the3.5 9 4 following asthey apply toLOSSOF SHUTDOWN COOLING: RHR/shutdown coolin 295023 (APE 23) Refueling Accidents /8 X AK2.05 Knowledge ofthe interrelations 3.5 10 between REFUELING ACCIDENTS andthe following: Secondary containment ventilation 295024 High DrywellPressure /5 X EK1.01 Knowledge ofthe operational4.1 11 implications ofthefollowing concepts as they apply toHIGHDRYWELL PRESSURE D ell inte rit:Plant-S ecific 295025 (EPE 2)HighReactor Pressure /3 X EA1.04 Ability tooperate and/or monitor the3.8 12 following asthey apply toHIGHREACTOR PRESSURE: HPCl: Plant-S ecific 295026 (EPE 3) Suppression Pool High Water X EK3.01 Knowledge ofthereasons for the 3.8 13 Temperature /5 following responses asthey apply to SUPPRESSION POOLHIGHWATER TEMPERATURE: Emergency/normal depressurization 295028 (EPE 5)High Drywell Temperature X 2.2.42 Ability to recognize system 3.9 14 (Mark IandMark only)
II /5 parameters that are entry-level conditions for Technical S ecifications.
295030 (EPE 7)LowSuppression Pool WaterX EK1.02 Knowledge of theoperational 3.5 15 Level /5 implications ofthe following concepts as they apply toLOWSUPPRESSION POOL WATER LEVEL: Pum NPSH 295031 (EPE 8) Reactor LowWater Level/2 X 2.4.34 Knowledge ofROtasksperformed 4.2 16 outside themain control room during an emergency andtheresultant operational effects.
295037 (EPE 14)Scram Condition Present X EK2.03 Knowledge oftheinterrelations 4.1 17 andReactor Power Above APRMDownscale between SCRAMCONDITION PRESENT orUnknown /1 ANDREACTOR POWER ABOVE APRM DOWNSCALE ORUNKNOWN andthe followin :ARI/RPT/ATWS: Plant-S ecific 295038 (EPE 15)High Offsite Radioactivity X EK1.02 Knowledge oftheoperational 4.2 18 Release Rate /9 implications ofthe following concepts as they apply toHIGHOFF-SITE RELEASE RATE: Protection oftheeneral ublic 600000 (APE 24) PlantFire OnSite /8 X AA2.14 Ability todetermine andinterpret the3.0 19 following asthey apply toPLANT FIRE ON SITE: Equipment that will beaffected byfire su ression activities ineachzone AK2.02 Knowledge oftheinterrelations 700000 (APE 25) Generator Voltage and X between GENERATOR VOLTAGE AND 3.1 20 Electric Grid Disturbances /6 ELECTRIC GRIDDISTURBANCES andthe followin :Breakers, rela s
ES-401 4 FormES4011 ES-401 BWRExamination Outline FormES-401-1 Emerencand Abnormal Evolutions-Tier Plant 1/Grou 2 RO/SRO E/APE# /Name/ Safet Function K1 K2 K3 A1 A2 G* K/AToics IR Q#
295033 (EPE 10)High Secondary X EA2.03 Abilitytodetermine and/or interpret 4.2 83 ContainmentArea Radiation Levels /9 thefollowing asthey apply toHIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: tCause ofhigh area radiation 295014 (APE 14)Inadvertent Reactivity X 2.1.7 Abilitytoevaluate plant performance 4.7 84 Addition
/1 andmakeoperational judgments based on operating characteristics, reactor behavior, andinstrument inter retation.
295010 (APE 10)High Drywell Pressure /5 X AA2.01 Abilitytodetermine and/or interpret 3.8 85 the following asthey apply toHIGH DRYWELL PRESSURE: tLeak rates AK2.01 Knowledge oftheinterrelations 295013 (APE 13)High Suppression Pool X between HIGHSUPPRESSION POOL 3.6 21 WaterTemperature/5 WATER TEMPERATURE andthe followin :Su ression ool coolin 295020 (APE20) Inadvertent ContainmentX AK1.02 Knowledge oftheoperational 3.5 22
/5 & 7 Isolation implications ofthe followingconcepts as they applytoINADVERTENT CONTAINMENT ISOLATION: Power /
reactivit control 295029 (EPE6)High Suppression Pool Water X EA1.03Ability tooperateand/or monitor2.9 23 Level
/5 thefollowing as theyapply toHIGH SUPPRESSION POOL WATERLEVEL:
RHR/LPCI 295032 (EPE9)High Secondary Containment X EK3.01 Knowledgeof the reasons for the 3.5 24 AreaTemperaturel 5 following responses asthey apply toHIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Emergency/normal de ressurization 295009 LowReactor Water Level X AA2.01 Abilitytodetermine and/or interpret 4.2 25 the following asthey apply toLOW REACTOR WATERLEVEL: Reactor water level 295035 (EPE 12)Secondary Containment X 2.4.1 Knowledge ofEOPentry conditions 4.6 26 Hih Differential Pressure /5 andimmediate actionsteps.
295036 (EPE 13)Secondary Containment X EA1.01 Abilitytooperate and/or monitor3.2 27 HighSump/Area Water Level /5 thefollowing asthey apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATERLEVEL: Secondary containment equipment andfloor drain s stems
ES-401 5 FormES-401-1 ES-401 BWRExamination Outline FormES-401-1 S stems-Tier Plant 1 RO/SRO 2/Grou System #/Name K1 K2K3K4K5K6A1A2A3A4 G* K/ATopic(s) IR Q#
262001 (SF6AC)AC Electrical X A2.06 Ability (a) to predict theimpacts ofthe 2.9 86 Distribution following onthe A.C. ELECTRICAL DISTRIBUTION: and(b) based onthose predictions, useprocedures tocorrect, control, ormitigate the consequences of those abnormal conditions oroperations: De-energizing a plant bus 203000 SF4RHR/LPCI)
(SF2, X 2.1,31Ability tolocate control roomswitches, 4.3 87 RHR/LPCI: Mode Injection controls, and indications, and to determine that they correctly reflectthe desired plant lineup.
211000 (SF1SLCS)Standby Liquid X A2.01 Ability (a) to predict theimpacts ofthe 3.8 88 Control following ontheSTANDBY LlQUID CONTROL SYSTEM; and(b) based onthose predictions, useprocedures tocorrect, control, ormitigate theconsequences of those abnormal conditions oroperations:
Pumptrip 215005 (SF7PRMS)Average Power X A2.07 Ability (a) to predict theimpacts ofthe 3.4 89 Range Monitor/Local Power Range following onthe AVERAGE POWERRANGE Monitor MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and(b) based onthose predictions, useprocedures tocorrect, control, or mitigate the consequences of those abnormal conditions oroperations:
Recirculation flow channels flow mismatch 209001 SF4LPCS)
(SF2, X 2.4.9 Knowledge of low power/shutdown 4.2 90 Low-Pressure CoreSpray implications inaccident (e.g., loss ofcoolant accident orloss ofresidual heat removal) mitigation strategies.
203000 SF4RHR/LPCI)X (SF2, K1.17 Knowledge ofthephysical connections 4.0 28 RHR/LPCI: Mode Injection and/or cause/effect relationships between RHR/LPCl: INJECTION MODE(PLANT SPECIFIC) andthe following: Reactor pressure 205000 (SF4SCS)Shutdown Cooling X A1.01 Ability topredict and/or monitor 3.3 29 changes inparameters associated with operating the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls including: Heat exchanger cooling flow 205000 (SF4SCS)Shutdown Cooling X K3.02 Knowledge oftheeffect that a loss or 3.2 30 malfunction ofthe SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have onfollowing: Reactor water level: Plant-Specific 206000 SF4HPCIS)
(SF2, X A1.06 Ability topredict and/or monitor 3.8 31 Coolant High-Pressure injection changes inparameters associated with operating the HIGHPRESSURE COOLANT INJECTION SYSTEM controls including:
System flow
ES-401 6 FormES4011 209001(SF2, SF4LPCS) X K5.04 Knowledge oftheoperational 2.8 32 Low-Pressure Core Spray :
implications ofthe following concepts asthey apply toLOWPRESSURE CORESPRAY SYSTEM: Heat removal (transfer) mechanisms 211000 (SF1 SLCS) Standby Liquid X A3.05 Ability tomonitor automatic operations 4.1 33 Control oftheSTANDBY LIQUID CONTROL SYSTEM including: Flow indication: Plant-Specific 212000 (SF7 RPS) Reactor Protection X K4.02 Knowledge ofREACTOR 3.5 34 PROTECTION SYSTEM design feature(s)
. and/or interlocks which provide forthe following: Theprevention ofa reactor SCRAM following asingle component failure 215003 (SF7 IRM) X ..
. K2.01 Knowledge ofelectrical power supplies2.5 35 Intermediate-Range Monitor .
tothe following: IRMchannels/detectors 215003 (SF7 IRM) X A4.01 Ability tomanually operate and/or 3.3 36 Intermediate-Range Monitor monitor inthecontrol room: IRMrecorder indication 215004 (SF7 SRMS) Source-Range X A3.04 Ability tomonitor automatic operations 3.6 37 Monitor oftheSOURCE RANGE MONITOR (SRM)
SYSTEM including: Control rodblock status 215005 (SF7 PRMS) Average Power .
X 2.1.28 Knowledge ofthe purpose and 4.1 38 Range Monitor/Local Power Range function of major system components and Monitor controls.
217000 (SF2,SF4RCIC) Reactor A2.08 Ability to (a) predict the impacts ofthe 3.0 39 Core IsolationCooling following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC); and (b) based onthose predictions, use procedures tocorrect, control, ormitigate the consequences ofthose abnormal conditions oroperations: Loss oflube oil cooling 218000 (SF3 ADS) Automatic X K3.02 Knowledge ofthe effect that a loss or 4.5 40 Depressurization malfunction ofthe AUTOMATIC DEPRESSURizATION SYSTEM will have on following: Ability torapidly depressurize the
... reactor 223002 (SF5 PCIS) Primary X K3.19 Knowledge oftheeffect that a loss or 2.8 41 Containment Isolation/Nuclear Steam : A malfunction ofthe PRIMARY CONTAINMENT Supply Shutoff ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have onfollowing:
Containment atmosphere sampling 239002 (SF3 SRV) Safety Relief X K6.05 Knowledge oftheeffect that a loss or 3.0 42 Valves ..
. malfunction ofthe following will have onthe RELIEF/SAFETY VALVES: Discharge line vacuum breaker n
259002 (SF2 RWLCS) Reactor WaterX K1.16 Knowledge ofthe physical connections 3.4 43 Level Control .. and/or cause-effect relationships between REACTOR WATERLEVELCONTROL SYSTEM andthe following: HPCI: Plant-
- 7. ..
- Specific 261000 (SF9 SGTS) Standby Gas ." X A3.01 Ability tomonitor automatic operations 3.2 44 Treatment oftheSTANDBY GASTREATMENT SYSTEM including
- System flow 261000 (SF9 SGTS) Standby Gas X 2.1.30 Ability tolocate andoperate 4.4 45 Treatment .
components, including local controls.
ES-401 7 FormES4011 262001 (SF6 AC)ACElectrical X A4.01 Ability tomanually operate and/or 3.4 46 Distribution monitor inthe control room: All breakers and disconnects (including available yard):
switch Plant-Specific 262002 (SF6UPS)Uninterruptable X A2.02 Ability (a) to predict theimpacts ofthe 2.5 47 Power Supply(AC/DC) following onthe UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.); and(b)based onthose predictions, useprocedures to correct, control, ormitigate the consequences ofthose abnormal conditions oroperations:
Over voltage 263000 (SF6DC)DCElectrical X K2.01 Knowledge ofelectrical power supplies 3.1 48 Distribution tothe following: Major D.C. loads 264000 (SF6EGE)Emergency X K6.08 Knowledge ofthe effectthata loss or 3.6 49 Generators EDG (Diesel/Jet) malfunction ofthe following willhave onthe EMERGENCY GENERATORS (DIESEL/JET): A.C. power 264000 (SF6EGE)Emergency X K5.05 Knowledge ofthe operational 3.4 50 Generators EDG (Diesel/Jet) implications ofthefollowing concepts asthey apply toEMERGENCY GENERATORS (DIESEL/JET): Paralleling A.C. power sources 300000 (SF8IA) instrument Air X K4.03 Knowledge ofINSTRUMENT AIR 2.8 51 SYSTEM design feature(s) andorinterlocks which provide for the following:Securingof IASupon loss ofcooling water 300000 (SF8IA)
Instrument Air X 2.4.49 Ability to perform without reference to 4.6 52 proceduresthose actions that require immediate operation of systemcomponents andcontrols.
400000 (SF8CCS)Component X K6.05 Knowledge ofthe effect that a loss or 2.8 53 Cooling Water malfunction ofthe following will haveonthe CCWS: Motors K/ACategory Point Totals: 2 2 3 2 2 3 2 2/ 3 2 3 Group Point Total: 26/5 3 /2
ES401 8 FormES-401-1 ES-401 BWRExamination Outline FormES-401-1 S stems-Tier Plant 2/Grou2 RO/SRO S stem#/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/ATo ics IR Q#
290002(SF4 RVI)Reactor Vessel Internals X 2.2.25 Knowledge ofthebases in 4.2 91 Technical Specifications for limiting conditions for o erations andsafelimits.
234000Fuel HandlingEquipment X A2.01 the Ability following (a) to predict theimpacts ontheFUELHANDLING of 3.7 92 EQUIPMENT; and(b) based onthose predictions, useprocedures tocorrect, control, ormitigate the consequences of those abnormal conditions oroperations:
Interlock failure 202002(SF1 RSCTL) Recirculation FlowControl X 2.2.40 Abilitytoapply Technical 4.7 93 S ecifications for as stem.
201001 CRDH)
(SF1 CRDHydraulic X 2.2.12 Knowledge ofsurveillance 3.7 54 rocedures.
201003 CRDM)
(SF1 Control RodandDrive X A1.03 Ability topredict and/or monitor 2.9 55 Mechanism changes inparameters associated with operating the CONTROL RODAND DRIVE MECHANISM controls including:
CRDdrive water flow 201002 RMCS)
(SF1 Reactor Manual Control X K1.05 Knowledge ofthephysical 3.4 56 connections and/or cause-effect relationships between REACTOR MANUAL CONTROL SYSTEM andthe following: Rodworth minimizer: Plant-S ecific 202001(SF1, SF4RS) Recirculation X K5.10 Knowledge ofthe operational 2.8 57 implications ofthe following concepts as they apply to RECIRCULATION SYSTEM: Motor generatorset operation:
Plant-Secific 204000 RWCU)
(SF2 Reactor Water Cleanup X K4.06 Knowledge ofREACTOR WATER 2.6 58 CLEANUP SYSTEM design feature(s) and/or interlocks which provide for the following: Maximizeplant efficiency (use ofreenerative heat exchan er 214000(SF7 RPIS)RodPosition Information X K6.02 Knowledge ofthe effect that aloss2.7 59 ormalfunction ofthe followingwill have on theRODPOSITION INFORMATION SYSTEM: Position indication robe 215001(SF7 TIP)Traversing In-Core Probe X A2.07 the Ability following (a) to predict ontheTRAVERSING theimpacts IN-of 3.4 60 CORE PROBE; and(b) based onthose predictions, useprocedures tocorrect, control, ormitigate theconsequences of those abnormal conditions oroperations:
Failure toretract during accident conditions: Mark-l&II 215002 RBMS)
(SF7 RodBlock Monitor X A4.03 Abilitytomanually operate and/or2.8 61 monitor inthecontrol room: Trib asses 219000 RHRSPC)
(SFS RHR/LPCl: X A4.04 Abilitytomanually operate and/or3.0 62 Torus/Suppression Pool Cooling Mode monitor inthecontrol room: Minimum flow valves 223001(SF5 PCS) Primary Containment and X A3.04 Abilitytomonitor automatic 4.2 63 Auxiliaries operations ofthePRIMARY CONTAINMENT SYSTEM AND AUXILIARIES including: Containment /
d ell resonse durin LOCA 256000Reactor Condensate System X K3.02 Knowledge ofthe effect that aloss3.2 64 ormalfunction ofthe REACTOR CONDENSATE SYSTEM will have on followin :CRDh draulics s stem
ES-401 9 FormES-401-1 241000(SF3 RTPRS) Reactor/Turbine Pressure X K1.31 Knowledge ofthephysical 3.1 65 Regulating connections and/or cause-effect between relationships REACTOR/TURBINE PRESSURE REGULATING SYSTEM andthe followin
- Turbine rotection K/ACategoryPointTotals: 2 0 1 1 1 1 1 1 1 2 1 GroupPoint Total: 12/3
/1 /2
Category K/A # Topic RO SRO-oni IR # IR #
2.1.26 Knowledge ofindustrial safety procedures (such asrotating 3.4 66 equipment, electrical,high temperature, high pressure, caustic, chlorine, o enandh droen 2.1.44 Knowledge ofROduties inthe controlroomduring fuel handling 3.9 67 such asresponding toalarms from the fuelhandling area, communication with the fuel storage facility, systems operated from thecontrol room in support of fueling operations, and supporting 1.Conduct of instrumentation.
Operations 2.1.37 Knowledge ofprocedures, guidelines, orlimitations associated with 4.3 68 reactivit manaement.
2.1.13 Knowledge offacilityrequirements forcontrolling vital/controlled 3.2 94 access.
2.1.41 Knowled e oftherefuelin rocess. 3.7 95 Subtotal 3 2 2.2.14 Knowledge oftheprocess forcontrollingequipment configuration or 3.9 69 status.
2.2.39 Knowledge ofless than orequal toonehour Technical Specification 3.9 70 action statements for s stems.
2.Equipment2.2.22 Knowled e oflimitin conditions foro erations andsafet limits. 4.0 71 Control 2.2.7 Knowled e oftherocess forconductin s ecial orinfre uent tests. 3.6 96 2.2.18 Knowledge oftheprocess formanaging maintenance activities 3.9 97 during shutdown operations, such asrisk assessments, work rioritization, etc.
Subtotal 3 2 2.3.5 Ability touseradiation monitoring systems, such asfixed radiation2.9 72 monitors andalarms, portable survey instruments, personnel monitorin e uiment, etc.
3.Radiation2.3.12 Knowledge ofradiological safety principlespertaining tolicensed 3.7 98 Control operator duties, such ascontainment entry requirements, fuel handling responsibilities, access tolocked high-radiation areas, ali ninfilters, etc.
Subtotal 1 1 2.4.41 Knowledge oftheemergency action levelthresholds and 2.9 73 classifications.
2.4.3 Abilit toidentiost-accident instrumentation. 3.7 74
- 4. 2.4.26 Knowledge offacilityprotection requirements, including fire brigade3.1 75 Emergency and ortable firefihtin e uimentusae.
nceures
/ 2.4.18 Knowled 2.4.30 Knowledge e ofthespecific ofevents bases related forEOPs.
tosystem operation/status that mustbe 4.0 99 4.1 100 reported tointernal organizations orexternal agencies, such asthe State, theNRC,orthe transmission s stemo erator.
Subtotal 3 2 Tier 3Point Total 10 7
ES-401 Record ofRejected K/As FormES-4014 Tier / Randomly Selected K/A Reason for Rejection Grou Thefollowin toledAVAs Were excluded$di#the s'ehilMhtic andrandodsam -
inAroness:
295027 High Containment This topic appliestoplants with Mark III Temperature containments only. Thefacility hasa MarkI 1/1 containment.
295011 HighContainment This topic appliestoplants with Mark III Temperature containments only. Thefacility hasa MarkI 1/2 containment.
207000 Isolation(Emergency) This system isnotinstalled atthe facility.
2/1 Condenser 209002 HPCS This system isnotinstalled atthe facility.
201004 RSCS This system is no longer installed atthe facility.
201005 RCIS This system isnotinstalled atthe facility.
2.2.3 Knowledge ofthe design, This K/Aapplies tomulti-unit facilities only.
procedural, andoperational G differences between units.
2.2.4 Ability toexplain the This K/Aapplies tomulti-unit facilities only.
variations incontrol board/control roomlayouts, G systems, instrumentation, and procedural actionsbetween units atafacility.
ES-401 Record ofRejected K/As FormES-4014 The followin V/As were re'ectedibilowinfthe s stematiciliHifft%ndom stunk racess:.
Question 5 Anacceptable question could not bedeveloped duetolack ofa direct turbine generator trip on 295006 Scram a Reactor scram atthe facility.
AK3.05 -
Knowledge ofthe Randomly resampled K/A295006 Scram 1/1 reasons for the following AK3.06Knowledge ofthereasons for the responses asthey apply to following responses asthey apply toSCRAM:
SCRAM: Direct turbine Recirculation pumpspeed reduction: Plant-generator trip: Plant-Specific Specific.
Question 6 Anacceptable question could notbedeveloped without toomuchoverlap from thelast twoNRC 295016 Control Room exams.
Abandonment AK3.03Knowledge ofthe Randomly resampled K/A295016 Control reasons for the following the Room Abandonment AK3.01Knowledge of 1/1 reasons for the f responses ollowing asthey responses asthey apply to apply to CONTROL ROOMABANDONMENT:
CONTROL ROOM ABANDONMENT: DisablingReactor SCRAM~
control roomcontrols Question 13 Anacceptable question could not bedeveloped duetosimplistic K/A, lack ofspecific bases 295026 Suppression Pool High related toK/A, andsimilarity toQuestion 21 Water Temperature Randomly resampled K/A295026 Suppression EK3.02Knowledge ofthe High following Pool Water TemperatureEK3.01 -
1/1 reasons for the Knowledge ofthe reasons for the following responses asthey apply to responses as they apply toSUPPRESSION SUPPRESSION POOLHIGH POOLHIGHWATER TEMPERATURE:
WATER TEMPERATURE: Emergency/normal depressurization.
Suppression pool cooling Question 14 Anacceptable question could notbedeveloped 295028 High Drywell duetolack ofsystem setpoints, interlocks and automatic actions associated with theEOP Temperature entry condition for high Drywell temperature.
1/1 2.4.2Knowledge ofsystem set Randomly resampled K/A295028 High Drywell points, interlocks andautomatic Temperature 2.2.42 -
torecognize Ability actions associated with EOP system parameters that areentry-level entry conditions. conditions forTechnical Specifications.
ES-401 Record ofRejected K/As FormES-401-4 Question18 Anacceptable question could notbedeveloped duetolack oftestable ROlevel material.
295038 High Offsite Radioactivity Release Rate Randomly resampled K/A295038 High Offsite EK1.01 -
Knowledge of the Radioactivity Release Rate EK1.02 -
Knowledge ofthe operational implications ofthe 1/1 operational implications ofthe following concepts asthey apply toHIGHOFF-following concepts asthey SITERELEASE RATE: Protection ofthe apply to HIGH OFF-SITE general public RELEASE RATE: Biological effects ofradioisotope ingestion Question 25 Anacceptable question could notbedeveloped 2 504 Seconda without oversampling Secondary Containment Controlconcepts also 27,and83).
(see Questions #24,26, Radiation Randomly resampledK/A 295009 LowReactor EA2.02 -
Ability todetermineWater Level AA2.01Ability -
to determine and/or interpret the followingas and/or interpret the following asthey applyto C NTA ENTVENT TION t ev I' HIGHRADIATION: Cause of high radiation levels Question 41 Anacceptable question could not bedeveloped duetosimplistic natureof K/A (anyfailure of soaton ucearStea up ly Shutoff i"n r'ad'i"a Randomly e s e
resampled usly lead b only K/A223002 Primary K306 Knowledge oftheeffect Containment Isolation/Nuclear Steam Supply 2/1 tph a osys or9 a ulnc onofthe Shutoff loss K3.19Knowledge ormalfunction ofthe oftheeffect that a PRIMARY ISOLATION CONTAINMENT ISOLATION PPLYSHUT-OFF w Iha e *
- 00
- 09 D R**R onfollowing: Turbine buildingatmosphere sampling.
4,
ES-401 Record ofRejected K/As FormES-401-4 Question 46 Anacceptable question could notbedeveloped 262001 AC Electrical without lowLODortesting either GFEStype knowledge.
Distribution Randomly resampled K/A262001 ACElectrical A4.02 -
Ability tomanually Distribution A4.01 Abilitytomanually operate 2/1 operate and/or monitor inthe and/or control room: Synchroscope, monitorinthecontrol room: All breakers anddisconnects (including available switch including understanding of yard): Plant-Specific.
running and incoming voltages Question 50 Anacceptable question could notbedeveloped without toomuchoverlap from thelast twoNRC 264000 Emergency Generators exams' (Diesel/Jet) EDG K5.06Knowledge ofthe Randomly resampled K/A264000 Emergency EDG operational implications Generators ofthe Knowledge of (Diesel/Jet) K5.05 -
2/1 theoperational implications ofthe following concepts asthey following concepts asthey apply to apply toEMERGENCY GENERATORS (DIESEL/JET):
EMERGENCY GENERATORS (DIESEL/JET):
Load sequencing Paralleling A.C. power sources.
Question 59 Anacceptablequestion could notbedeveloped 214000 RodPosition without toomuchoverlap from the last twoNRC Information exams.
Randomly resampled K/A 214000 RodPosition K6.01Knowledge ofthe effect Information K6.02 -
Knowledge ofthe that effect that a loss ormalfunction ofthe a loss ormalfunctionofthe following have will fpo oSN*'lH SYSTEM: A.C.
a9vepon hleg electrical OD ontheRODPOSITION power SYSTEM: Position INFORMATION indication probe.
Question 64 An acceptable question could notbedeveloped without oversampling RHRconcepts acrossthe 230000 RHR/LPCI: exam.
Torus/Suppression PoolSpray Mode Randomly resampled K/A256000 Reactor K3.02Knowledge oftheeffect Condensate System K3.02Knowledge ofthe that a loss ormalfunction effect ofthe REACTOR thata lossormalfunction ofthe 2/2 CONDENSATE SYSTEM will have onWWng: W WauH wh.
TORUS/SPPRESSION POOL SPRAY MODEwill have on following: Suppression pool temperature
ES-401 Record ofRejected K/As FormES-401-4 Question 68 Anacceptable question could not bedeveloped 2.1.15- Knowledge of atadiscriminating level duetolimited related for ROs(they administrative requirements for administrative review these requirements aspart ofturnover).
just temporary management 3 directives, suchasstanding Randomly resampled K/A2.1.37 -
Knowledge orders, night orders, operations ofprocedures, guidelines, orlimitations memos, etc. associated with reactivity management.
Question 81 Anacceptable question could notbedeveloped attheSROlevel without being lowLODand 295006 Scram overlapping operating with exam.
AA2.03 -
Ability todetermine Randomlyresampled K/A295004 Partialor 1/1 and/or interpretthefollowing as Complete Loss ofD.C. Power AA2.03Ability they apply toSCRAM: Reactor todetermine and/or interpretthe followingas water level they apply toPARTIAL ORCOMPLETE LOSS OF D.C. POWER: Battery voltage.
Question 86 Anacceptable question could notbedeveloped attheSRO level without being lowLODdueto 262001 ACElectrical the simplistic nature of theK/A.
Distribution K/A262001ACElectrical A2.07Ability to(a)predict the Randomly resampled DistributionA2.06Ability to(a) predict the impacts ofthefollowing onthe impacts ofthe following on theA.C.
A.C. ELECTRICAL ELECTRICAL DISTRIBUTION; and(b) based 2/1 DISTRIBUTION; and(b) based onthose predictions, use procedures tocorrect, onthose use predictions, control, ormitigate theconsequences ofthose procedures tocorrect, control, abnormal conditions oroperations: De-ormitigate theconsequences of energizing a plant bus.
those abnormal conditions or operations: Energizing a dead bus
t ES-401 Record ofRejectedK/As FormES-401-4 Question 92 Anacceptable could question notbedeveloped 259001 Feedwater attheSROlevel being without lowLODand overlapping exam.
theoperating A2.03 -
Ability impacts of the (a) to predict following the onthe RandomlyresampledK/A234000Fuel REACTOR FEEDWATER Handling Equipment the predict A2.01Ability ofthe impacts to(a) onthe following FUEL SYSTEM; and(b) based on HANDLING 2M those predictions, use EQUIPMENT; and(b) based on procedures to correct, those control,control, use predictions,procedures tocorrect, ormitigate the consequences or of abnormalmitigate ofthose theconsequences those abnormal conditions or conditions or Interlock operations:
operations: Lossof condensate failure.
pump(s)