ML20260H165

Draft Written Examination and Operating Test Outlines (Folder 2)

ML20260H165
Person / Time
Site:	Peach Bottom
Issue date:	06/30/2020
From:	Exelon Generation Co
To:	Todd Fish Operations Branch I
Fish T
Shared Package
ML19105A151	List: ML20184A247 ML20184A248 ML20260H163 ML20260H164 ML20260H165 ML20260H166 ML20260H167 ML21056A220 ML21056A221
References
CAC 000500
Download: ML20260H165 (32)

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ES-201 Examination Outline Quality Checklist FormES-2012 Facility:

W Date ofExamination:

Jo e # 20 Initials Item TaskDescription a b* c**

1. a.Verify that theoutline(s)fit(s) theappropriate model inaccordance with ES-401 orES-401N.L 4 Q' C W b. Assesswhether the outline wassystematically andrandomly prepared inaccordance with 4 ,

7 R section D.1 of ES-401 orES-401N andwhether allK/Acategories areappropriately sampled. '

I

[ c.Assess whetherthe outline overemphasizes anysystems, evolutions, orgeneric topics. M f7C

[ d.Assess whether thejustifications for deselected orrejected K/Astatements are appropriate.g g 4

2. a. Using FormES-3015, verify that the proposedscenario sets cover therequired number of S

normal evolutions, transients.

instrument and component technical failures, specifications, andmajor 4 TT$

I M b. Assess whether there are enough scenario sets (and spares) totest theprojected number and U mixofapplicants inaccordance with the expected crew composition androtation schedule L

A without least compromising applicants' audit examintegrity, oneneworsignificantly test(s), andthat modified and ensure that scenario, scenarios each applicant that noscenarios are will not berepeated onsubsequent canbetested duplicated from days.

using the at f- f)" @

T

c. Totheextent possible, assess whether the outline(s) conforms with thequalitative and quantitative criteria specified onFormES-301-4 anddescribed inAppendixD andin (includingC* @

Section D.5, "SpecificInstructions for the'Simulator Operating Test,'" of ES-301 overlap).

3. a. Verify that the systems walkthrough outline meets thecriteria specified onFormES-301-2:

(1) Theoutline(s) contains therequired number ofcontrol room and in-plant tasks distributed W among thesafety functions asspecified onthe form.

A (2) Taskrepetition from the last twoNRCexaminations iswithin thelimitsspecified onthe form. (A g L (3)Notasks are duplicated from theapplicant's audit test(s).

K (4) Thenumber ofnew ormodified tasks meets orexceeds the minimums speclied on the form.

T (5)Thenumber ofalternate-path, low-power, emergency, andradiologically controlled area H tasks meets the criteria onthe form.

R O b.Verify that theadministrative outline meets the criteriaspecified onFormES-301-1:

U (1) Thetasks are distributed among the topics asspecified onthe form.

G H

(2)Atleast (3) Nomore onetask than isneworsignificantly onetask isrepeated from modified.

the lasttwoNRClicensing examinations.

L&

(

c. Determine whether there areenough different outlinestotest theprojected number andmixof applicants andensure that noitems are duplicated onsubsequent days. C t ,

l '

4. a. Assess whether plant-specific priorities (including probabilisticrisk assessment andindividual plant examination insights) arecovered inthe appropriate examsections. <V 7 7 G

E b. Assess whether the10CFR55.41, 55.43, and55.45 sampling isappropriate. c // 7

c. Ensure that K/Aimportance ratings (except for plant-specific priorities) areatleast 2.5. c//-7 '

R A

d Check for duplicationandoverlap amongexamsections andthelast twoNRCexams 4' Q'@

~'

d' (

L e. Check theentire examfor balance ofcoverage.

f. Assess whether theexamfits theappropriate job level(RO orSRO). C // ff Printed Namg/Sighatwe / Date

a. Author dfd2tr eve 2M 2c @

b. Facility Reviewer (*) #

• c ,

1. ~

c. NRCChief Examiner (#)

d. NRCSupervisor m f Notapplicable for NRC-prepared examination outlines.

1. Theindependent NRCreviewer initials items incolumn "c"; thechief examiner's concurrence isrequired.

ES-301 Administrative Topics Outline FormES-301-1 Facility: Peach Bottom Date ofExamination:6/1/2020 ExaminationLevel: RO 2 SRO Q Operating Test Number: 2020NRC Administrative Topic (seeNote) Type Describe activitytobeperformed Code*

G2.1.5 (2.9)Application ofWorkHour Rules Conduct ofOperations N,R (PLOR-391C)

G2.1.31 (4.6) -

PerformanAPRMScram Conduct ofOperations M,S Margin Check (PLOR-219C)

G2.2.41 3BRBCCW (3.5) isolate the Heat Equipment Control D,R Exchanger Due toa Leak(PLOR-274C)

Radiation Control NA G2.4.39 (3.9) -

PerformState/Local Emergency Plan D,S Notificationsfor a Declared Emergency(PLOR-246C)

NOTE:All (five items total) SROs.ROapplicants arerequired for require onlyfouritemsunless they areretaking only topics theadministrative (which would r equireallfiveitems).

TypeCodes andCriteria: (C)ontrol room, orClass(R)oom (S)imulator, (D)irect (5 Os;s4 for frombank 3 forR SROsandROretakes) or from (N)ew(M)odified(21)b ank (P)revious 2 exams(51,randomly selected)

ES-301 Administrative Topics Outline FormES-301-1 Facility: Peach Bottom Date ofExamination: 6/1/2020 ExaminationLevel: RO O SRO 2 Operating Test Number: 2020 NRC Administrative Topic (seeNote) Type Describe activity tobeperformed Code*

2.1.32(4.0) Perform SROReview ofCompleted Conduct ofOperations D,R Surveillance Test (PLOR-365C)

G2.1.37 (4.6)Perform SROReview ofREMA Conduct ofOperations N,R (PLOR-394C)

G2.2.13 (4.3) Determination ofImpact ofTagout Equipment Control N,R onSystem Operability (PLOR-395C)

G2.3.13 (3.8) -

ReviewPrimary Containment Radiation Control M,R Purge /Vent Isolation ValveCumulative Log (PLOR-256C)

G2.4.41 (4.6) Classification ofEmergenciesand Emergency Plan M,S PARS NOTE:All (five items arerequired total) SROs.ROapplicants for require only four itemsunless they areretaking only theadministrative (which topics would require allfive items).

Type Codes andCriteria: (C)ontrol room, orClass(R)oom (S)imulator, (D)irect frombank(53forROs;5 4for SROsandROretakes)

(N)ew from or(M)odified bank (21)

(P)revious 2 exams(51,randomly selected)

ES-301 Control Room/In-Plant Systems Outline FormES-301-2 Facility: Peach Bottom Date ofExamination: 6/1/2020 ExamLevel: RO 2 SRO-ID SRO-U D Operating Test Number: 2020NRC Control RoomSystems:* 8 for RO,7 forSRO-I, and2 or3for SRO-U System/JPM Title TypeCode* Safety Function a.202002 A4.04 3.8/3.9 -

RaiseReactor Powerwith RecirculationA,N,S 1 Flow (Alternate Path) (PLOR-396CA) b.223002 A4.03 3.6/3.5 -

Reset HPCIIsolation (PLOR-019C) D,S,EN 2 c.218000 A4.03 4.2/4.2 -

ADSReset Following Blowdown (PLOR- D,S,EN,L 3 023C) d.217000 A4.03 3.4/3.3 -

Manually initiateRCIC(Alternate Path) A,D,S,EN 4 (PLOR-332CA) e.295029 EA1.032.9/3.0 Lower TorusWater LevelIAWAO10.1-2 N,S 5 (PLOR-398C) f.264000 A4.04 3.7/3.7-LoadDiesel Generator (AlternatePath A, D, S 6 Differential/Ground) (PLOR-373CA) g.201006 3.2/3.1 A3.01 -

theRWM(PLOR-366C)

Initialize D,S,L 7 h.400000 A4.01 3.1/3.0 -

HPSWInjection into the Reactor Vessel in A,D,S 8 accordance ON-124 with (Alternate Path) (PLOR-382CA)

In-Plant Systems:*

3for RO,3 for SRO-l, and3 or2 for SRO-U i.295037 EA1.053.9/4.0 -

Isolate andVent theScram AirHeader D,E,R 1

Unit 3 (PLOR-074P) j.264000 K4.07 3.3/3.4-Diesel Generator Air StartSolenoid D,E 6 Override (PLOR-049P) k.295031 EA1.083.8/3.8 -

FireSystem Injection IntoTheRPV D,R 2 (PLOR-104P)

ROandSRO-l All control room(and in-plant)systems andserve mustbedifferent different safety five functions, all SRO-U systemsmustserve different functions, safety andin-plant and systems mayoverlap functions thosetested inthecontrol room.

ES301 Control Systems Room/in-Plant Outline FormES-301-2 (A)lternate path /2-3 4--6/4-6 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant a1/21/21 (EN)gineered safety feature a1/21/21(control roomsystem)

(L)ow-Power/Shutdown 1/2 2 1/2 1 (N)ew or(M)odifiedfrom bank including1(A) 2 2/2 2/21 (P)revious 2 exams 5 3/s 3/s2 (randomly selected)

(R)CA 2 1/2 1/21 (S)imulator

ES-301 Control Room/In-Plant Systems Outline FormES-301-2 Facility: Peach Bottom Date ofExamination: 6/1/2020 ExamLevel: RO D SRO-I 2 SRO-U D Operating Test Number: 2020NRC Control RoomSystems:* 8for RO,7for SRO-I, and2 or3for SRO-U System/JPM Title Type Code* Safety Function a.202002 A4.043.8/3.9 -

Raise Reactor Power with RecirculationA,N,S 1 Flow (Alternate Path) (PLOR-396CA) b.223002 A4.033.6/3.5 -

Reset HPCIIsolation (PLOR-019C) D,S,EN 2 c.218000 A4.034.2/4.2 -

ADSReset FollowingBlowdown (PLOR- D,S,EN,L 3 023C) d.217000 A4.033.4/3.3 -

Manually InitiateRCIC(Alternate Path) A,D,S,EN 4 (PLOR-332CA) e.295029 EA1.032.9/3.0 Lower Torus Water LevelIAWAO 10.1-2 N,S 5 (PLOR-398C) f.264000 3.7/3.7 A4.04 -

Load Diesel Generator (AlternatePath A, D, S 6 Differential/Ground) (PLOR-373CA) 9 h.400000 A4.013.1/3.0 -

HPSWInjection intothe Reactor Vessel in A,D,S 8 accordance ON-124 with (Alternate Path) (PLOR-382CA)

In-Plant Systems:*3 for RO,3for SRO-l, and3 or2 for SRO-U i.295037 EA1.05 3.9/4.0 -

Isolate andVent theScram AirHeader D,E,R 1

Unit 3 (PLOR-074P) j.264000 K4.07 3.3/3.4 -

Diesel Generator AirStartSolenoid D,E 6 Override (PLOR-049P) k.295031 EA1.083.8/3.8 -

FireSystem InjectionIntoTheRPV D,R 2 (PLOR-104P)

ROandSRO-I All control room(and in-plant) systemsmustbedifferent andserve different safety five functions, all SRO-Usystems mustserve different safety andin-plant functions, and systems mayoverlap functions thosetested inthecontrolroom.

ES-301 Control Systems Room/In-Plant Outline FormES-301-2 (A)lternate path 4-6/4-6

/2-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant 2 1/2 1/21 (EN)gineered safety feature 2 1/2 1/2 room 1(control system)

(L)ow-Power/Shutdown 2 1/2 1/21 (N)ew or(M)odifiedfrom bank including 1(A) a2/22/21 (P)revious 2exams s3/s3/s2 (randomly selected)

(R)CA 2 1/2 1/21 (S)imulator

Appendix D Scenario Outline ES-D-1 Simulation Peach Facility BottomScenario No.#1 OpTest No. M Examiners Operator -

CRS(SRO)

URO(ATC)

PRO(BOP)

Scenario Thescenario begins withthereactor atapproximately 3%power during a reactor Summary startup.

Following shiftturnover, thePROwill commence Drywell nitrogen inerting using procedure SO7B.1.A-2, "Containment Atmosphere Inerting". ThePROwill start theStandby GasTreatment System, andthen align nitrogen gasflow tothe Primary Containment.

TheUROwill continue the startup byraisingreactor power to> 4%bywithdrawing control rods inaccordance withthe approved startup sequence until 2main turbine bypass valves areopen with reactor pressure at 910psig using procedure GP-2-2, "Normal Plant Startup".

A controlrod will become mispositioned due to a Reactor Manual Control System timer failure, requiring theUROtoexecute ON-122, "Mispositioned Control Rod" to thecontrol return rod tothe correct targetposition.

ThePROwill then respond toaninadvertent opening of an Automatic Depressurization System (ADS) safetyreliefvalve (SRV). The crewwill respond in accordance with procedure OT-114, "lnadvertent Openingof a Relief Valve". The PROwill initiate Torus cooling. ThePROwill besuccessful in closing the safety relief valve with its control switch. Onceclosed, the ADSvalvewill remain closed andwillnolonger function. TheSROwill declare the ADSvalve inoperable andwill enter/apply Technical Specifications 3.5.1.E.

Next,the startup level control valve will experience a loss ofair resulting in the startuplevel control valve failing open.

full Thevalve failing open will cause the RPVlevel torise. Thecrewwill recognize RPV therising water level andenter procedure OT-110, "Reactor High Level".TheUROwill recognize that placing the failed startup level control valve controller from AUTOtoMANUAL will notreturn ofthe control level control valve. TheUROwill re-establish RPVwater level controlbyeither throttling theMO-8090 "CFeedPumpDish Bypass" tocontrol orclosing level theMO-8090 "CFeedPumpDish Bypass" andmanipulating the "C"Reactor FeedPump(RFP) discharge valve and"C" RFPspeed tocontrol level.

ThePROwill then respond tothe inadvertent start ofa core spray subsystem. The PROwill secure the core spray system andthe SROwill declare thecore spray subsystem inoperable. TheSROwill enter/apply Technical Specifications 3.5.1.F.

(This Tech Spec w ill applydue to the already INOP ADS valve) 2020NRCScenario #1D-1Rev0

Appendix D Scenario Outline ES-D-1 A water leak willdevelop inthe Torus, resultingina lowering ofTorus water level.

Thecrew will enterT-102, "Primary Containment Control". Thecrew willbegin making upto the Torus using oneofseveral available systems (Condensate Transfer using SO14A.1.A, High Pressure Coolant Injection (HPCI) using T-233, or High Pressure Service Water (HPSW) usingT-231).

The crew will scram thereactor before Torus water level lowers to10.5 feet and enterT-101 WhenTorus water level cannot bemaintained above 10.5 feet, anEmergency Depressurization, IAW T-112, willbedirected.

Theprevious INOPADS SRVwill fail tofunction requiring the candidate toopena non-ADS SRVfor theEmergency Blowdown.

Thescenario maybeterminated following theEmergency Blowdown.

Initial IC-71 Appro'ximately 3%power Conditions Turnover . Unit 2 startupisinprogress.

a Reactor Power isapproximately 3%with direction tocontinue toraise Reactor power with control rod withdrawalusing GP-2-2.

• Nitrogen inerting ofthePrimary Containment istobe commenced. The PROwill begin inerting thePrimary Containment following shiftturnover.

Critical Critical Task1:Manually Scram thereactor before Torus level lowers to10.5 Tasks feet.

Critical Task2:Perform anEmergency Blowdown whenWater Torus level cannot bemaintained above10.5 feet andbefore SRVsareuncovered at7 feet.

Critical Task3:Openonenon-ADS SRVtocompensate for thefailure ofan ADSvalve toopenduring anEmergency Depressurization.

2020NRCScenario #1D-1Rev0

Appendix D Scenario Outline ES-D-1 Event Malfunction Event Event No. No. Type* Description 1 SeeScenario Guide N PRO Initiate Primary Containment nitrogeninerting.

CRS 2 SeeScenario Guide R URO Raise reactor power bywithdrawing control rods.

CRS 3 SeeScenario Guide C URO Mispositioned control rod.

CRS 4 SeeScenario Guide C PRO Inadvertent opening ofanADSSRV.CRSenters Tech TS CRS Specs.

5 SeeScenario Guide C URO Startup level control valve fails open /ROcontrols by level CRS manual operation of'C' RFPspeed anddischarge valve.

6 SeeScenario Guide C PRO "A" Core Spray loopspuriously /PROsecures starts pumps TS CRS andCRSenters Tech Specs.

7 SeeScenario Guide M ALL Unisolable water leak inthe Torus.

8 SeeScenario Guide C ALL ADSSRVfails toopenonEmergency Blowdown.

(N)ormal,(R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)TechSpec 2020NRCScenario #1D-1Rev0

Appendix D Scenario Outline ES-D-1 Simulation Peach Facility Bottom Scenario No.#2 OpTest No. 2020NRC Examiners Operator CRS(SRO)

URO(ATC)

PRO(BOP)

ScenarioThescenario begins with thereactor at100%power with the'B'Electrohydraulic Summary Control (EHC) pump and the E-332 b reaker are blocked outof servicefor scheduled maintenance.

Aftertaking theshift, the PROwill start High Pressure Service Water (HPSW)

Pump"A" inaccordance with RT-O-032-300-2, "HPSWPump, Valve andFlow FunctionalTest".

Next,theUROwill withdraw a fully-inserted control rod following scram timing.

Duringthe evolution, thein-service Control RodDrive (CRD) Pumpwill experience high ampsrequiring the URO tosecure theCRDPumpandto enter/execute ON-107, "Loss ofCRD Regulating Function". Afterplacing theCRD flow control valve inMANUAL,theURO will startthe standby CRDPumpand transfertheCRDflow contro! valve backto AUTO. TheUROwill then successfullywithdraw the control rod toposition 48.

Shortlyafterthis, theE-4Diesel Generator will inadvertently start andoneminute later 005F-1"E-4 Diesel GenDifferential andGround" alarm will annunciate.The crewwilltake action inthe alarm response toshutdown the E-4diesel generator andplace inPull-to-Lock. TheCRSwill apply TechnicalSpecifications for an inoperableDiesel Generator.

Followingthediesel generator event, thePROwill enter andexecute ARC 222 A-5for a loss of125VDCtotheReactor Core isolation Cooling (RCIC) System.

ThePROwill close MO-2-13-18, "Condensate TankSuction" valve toprevent drainingtheCondensate Storage Tank(CST) tothe Torus. ThePROwill also recognizethat theRCICSteam Supply valve isalso isolated. TheCRSwill declareRCICinstrumentation andtheRCICPumpinoperable andwill enter/apply TechnicalSpecifications 3.3.5.2 and3.5.3.

FollowingtheRCICevent, a high vibration condition for themain turbine will occur.TheUROwill lower reactor power with recirculation flowbylowering pumpspeed recirculation ofboth recirculation pumps, andbyinserting control rodsIAWGP-9-2.

The30RPMDOWNpushbutton for 1recirculation pumpwill not functionandthe ROmustlower speed using either the5 RPMor1RPMdownbutton.

Turbine vibrations will continue torise, requiring theCrew toscram thereactor andtripthemain turbine. AnRPSmalfunction will occur, resultinginanelectric ATWS,requiring the Crew toenter/execute T-101 "RPVControl" andT-117 "Level/Power Control."

2020NRCScenario #2D-1Rev0

Appendix D Scenario Outline ES-D-1 A failure ofthe onlyavailableElectrohydraulic Control (EHC) pumpwill causethe turbine bypass valvestoclose, requiring theCrew toutilize SRVsfor reactor pressure control.

The Crewwill performT-213 "Scram Solenoid Deenergization ",T-214 "Isolating and Venting the Scram AirH eader", andT-220 "Driving Control RodsDuring a Failure toScram", toinsert control rods.

TheCrewwill also injectSBLCbefore Torus Temperature reaches 1100F.

Thescenario may beterminated whentheCrewhascontrol ofRPVpower and water levelusing T-240 "Termination andPrevention ofInjection into theRPV" andtheCrewisinserting control rods.

Initial IC-14, 100%power Conditions Turnover . Reactor power is100%power.

a 'B'ElectrohydraulicControl (EHC) pump blocked out ofservice for scheduled maintenance.

a E-332 breakerisblocked outofservice for scheduled maintenance.

a Perform RT-O-032-300-2, "HPSWPump, Valve and FlowFunctionalTest" forHPSWPump"A".

CriticalCritical Task #1:Attempt toshutdown thereactor byperforming oneor Tasks moreofthe following: T213"Scram Solenoid Deenergization", T-214 "Isolating andVenting theScram AirHeader", T-220 "Driving Control Rods During a Failure toScram", and"Initiating Standby Liquid Controlbefore Torus temperature exceeds 1100F.

Critical Task#2:Before violating theHeatCapacity Temperature Limit (HCTL) curve, perform T240 "Terminating and Preventing Injection Into the RPV"toprotect Primary Containment until:Reactor power isbelow 4%or RPVlevel reaches -172 inches orAll SRVsremain closed andDrywell pressure isbelow 2 psig.

2020NRCScenario #2D-1Rev0

Appendix D Scenario Outline ES-D-1 Event Malfunction Event Event No. No. Type* Description 1 SeeScenario Guide N PRO Perform RT-O-032-300-2, "HPSW Pump, Valve andFlow CRS Functional Test".

2 SeeScenario Guide C URO Withdraw a single control rodandrespond toCRDPumphi CRS amps.

3 SeeScenario Guide C PRO Shutdown E-4diesel generator following inadvertent CRS start.

enters Tech Specs.

TS CRS 4 SeeScenario Guide I PRO Loss ofRCIClogic power. CRSenters Tech Specs.

TS CRS 5 SeeScenario Guide R URO Main turbine high vibrations require lowering power toaddress CRS the vibrations 6 SeeScenario Guide C URO The30RPMDOWN (recirculation pumpcontrols) pushbutton CRS fails.

7 SeeScenario Guide C ALL Main turbine high vibrations continue torise requiringturbine trip andreactor scram.

8 SeeScenario Guide M ALL TheCrewresponds toanelectric ATWS.

g SeeScenario Guide C ALL EHCfailure leads totheloss ofmain turbine bypass valves.

(N)ormal,(R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) TechSpec 2020NRCScenario #2D-1Rev0

Appendix D Scenario Outline ES-D-1 Simulation Peach Facility Bottom Scenario No.#3 OpTest No. 2020NRC Examiners Operator CRS(SRO)

URO(ATC)

PRO(BOP)

ScenarioThescenario begins with thereactor at100%power.

Summary Shortlyaftertaking the shift thePROwill swapElectrohydraulic Control (EHC)

PumpsIAWprocedure SO1D.6.A-2 "Placing theEHCOil System Standby Pump inService".

Followingthenormal evolution thein-service Steam Jet Air Ejector (SJAE) steam supply willclose. Thisresults ina lowering main condenser vacuum. TheURO willlower reactor power with recirculation flow IAWOT-106, "Condenser Vacuum Low".ThePRO place will the standby SJAE intoservice IAW SO 8A.6.A-2, "Placing theStandby SJAEinService andPlacing theInService SJAEin Standby".

NexttheUROwill respond torising vibrations onreactorfeedwater pump"B"The UROwill lower reactorpower if required, then the UROwill secure the feedwater pumpIAWSO6D.2.A-2, "Reactor FeedwaterPump Shutdown".

Next,thePROwill respond toa spurious startofthe High Pressure Coolant (HPCI)

Injection Pump. T heCrew will enter OT-104, "Positive Reactivity ThePROwill Insertion". secure thepumpIAWSO 23.2.A-2, "HPCI System Shutdown". TheCRSwill declare HPCIinoperable andenter/apply Technical Specifications3.5.1.

Thenext event provides annunciated indication ofa potential breakin one ofthe core spray spargers. TheCRSwill declare the instrumentation inoperable and will enter/applyTechnical Resources Manual (TRM) 3.3.

TheUROwill then respond toindications oflowoil level onthe"A"recirculation pump, followed byrisingbearing temperatures. TheUROwill secure the"A" pumpIAWSO2A.2.A-2, recirculation "Recirculation PumpShutdown".

A rapidlydeveloping steam leak into thePrimary Containment will then begin.

Thecrewwill enter OT-101, "High Drywell Pressure", but duetothe aggressive steam leakaGP-4will bedirected toScram thereactor.

Directly following thescram, theScramDischarge Volume vent/drain will fail to which isolate, willbemanually isolated bythe URO.

A Torus toDrywell vacuum breaker willfail openduring theScram causing a loss ofthe Torus Pressure Suppression function.

2020NRCScenario #3D-1Rev0

Appendix D ScenarioOutline ES-D-1 Following thescram, thecrewwillenter/execute T-101"RPVControl"andT-102 "PrimaryContainment TheCrewwill Control", spraytheprimarycontainment using procedure T-204"Initiation ofContainment Sprays UsingRHR".

The scenario maybeterminated whenthereactor isshut RPVlevel downwith under control, PrimaryContainment sprays arein andtheSDVhasbeen service, manually isolated.

Initial IC-14, 100%power Conditions Turnover a Unit 2 isat100%power.

a "B" RWCUpumpistagged outofservice.

a Following thePRO will bedirected turnover, toplace the EHCpump "B"

in-service andsecurethe"A" EHC pump.

CriticalCritical Task#1:Spray theDrywell before thePressure SuppressionLimit Tasks curve isexceeded.

Critical Task#2:Manually isolatetheScramDischarge Volumefollowing an isolation failure within30minutes.

2020NRCScenario #3D-1RevO

Appendix D Scenario Outline ES-D-1 Event Malfunction Event Event No. No. Type* Description 1 SeeScenario Guide N PRO SwapEHCPumps CRS 2 SeeScenario Guide C PRO Failure ofin-serviceSJAE.

R URO CRS 3 SeeScenario Guide C URO Rising vibrationsonfeedwater pump"B" CRS 4 SeeScenario Guide C PRO Spurious startoftheHigh Pressure Coolant (HPCI)

Injection TS CRS Pump. CRS enters TechSpecs.

5 SeeScenario Guide TS CRS Core spraysparger leak/break detection CRSenters fails.

TechSpecs/TRM.

6 SeeScenario Guide C URO Loss ofoilandrisingbearing temperatures on"A" CRS recirculation pump.

7 SeeScenario Guide M ALL Steam leakinPrimary Containment.

8 SeeScenario Guide C URO SDVfails toisolate.

CRS 9 SeeScenario Guide C ALL Torus toDrywell Vacuumbreaker fails open (N)ormal,(R)eactivity, (C)omponent, (I)nstrument, (M)ajor,(TS) TechSpec 2020NRCScenario #3D-1Rev0

Appendix D Scenario Outline ES-D-1 Simulation FacilityPeach Bottom Scenario No.#4 OpTest No. 2020NRC Examiners Operator CRS(SRO)

URO(ATC)

PRO(BOP)

ScenarioThescenario begins with thereactor atapproximately 97%power.

Summary After takingthe shift, the UROwill withdraw control rod58-31 toposition 48.

Whenverifyingcontrol rodcoupling,thecontrol rod willover-travel. TheUROwill enterON-105, "Control RodUncoupled" and willre-couple the control rod.

Followingthecontrol rod movement, theUROwill raise reactor power with recirculation flow back to100% power.

Withthe reactor atfull power, the PRO will then continue ininST-O-014-301-2, "Core Spray Loop A Pump, Valve, Flow, andCooler Functional andInservice Test".Thein-field operator will report the "C"pumproom cooler fan willnot start.

TheCRSwill declare thecore spray pump inoperable andwill enter/apply Technical Resources Manual 3.11 andTechnical Specifications 3.5.1.

Next,a loss ofDCpower tooneoftwo(in series) 'B' RPSMGset output breakers will A occur.subsequent operability concern the other (in with series) 'B'RPSMG setoutput breaker will require theCrew totransfer the 'B' RPS bus tothe alternatepower supply IAWSO60F.6.A-2 "Transferring Reactor Protection System Power Supplies" . Theresultant halfscram andcontainment isolationswill have tobereset bythe PRO,IAWGP-11.E "Reset RPS Scram Reset" andGP 8.D"Group 1,2,3 Outboard Half isolation".TheCRSwill declare one electric power monitoring assembly inoperable andwill enter/apply Technical Specifications3.3.8.2.

Following the transfer ofRPSB toalternate, Standby GasTreatment System (SBGT) B train will re-align but t heS BGT Fan "B"w illnot auto s tart. The PRO will SBGTFan"B".

start TheCRSwill declare SBGTFan"B" inoperable and enter/applyTechnical Specifications 3.6.4.3.

Afterthe Technical Specification entry, rising radiation levels inoffgas andmain steam are noted, andON-103, "Main Steam Line High Radiation" isentered. The UROwill reduce power toreduce these radiation levels.

Afterthereduction inpower theMainSteam Line Radiation levels continue torise andAlarm 218D-1"Main Steam Line Hi-Hi Radiation" will bereceived. TheCRS direct will a GP-4"Manual Reactor Scram".

A steam line break inthe Turbine Building willthen occur. Thesteam leak gets worse, asdoes the amount offuel failures, requiring the Crewtomanually close theMSIVs.

2020NRCScenario #4D-1Rev1

Appendix D Scenario Outline ES-D-1 Whenattempting toclose theMSIVs, The"D" main steamlinewill notbeable to beisolated.

The Crew will enterT-104 "Radioactive Release" toevaluate andcontrol the radiation release.Whenthe release exceeds the General Emergency level,the Crew willberequired toperform T-112, "Emergency Blowdown" Thescenario will beterminated whenthe emergency blowdown isinitiated and RPVlevel is restored above thetopofactive fuel (-172 inches).

Initial IC-14, 100%power (Reactor power is lowered to97%power)

Conditions Turnover . Reactorpower isapproximately 97%.Reactor powerwaslowered to allowscram valve repairs on control rod 58-31. Therepairs arecomplete, thecontrolrodhasbeen scram-timed, andisatposition 00. TheUROmay withdrawthe control back toit'starget position of48.

• Followingthecontrol rod withdrawal, the URO mayraise reactor power back to100%with recirculation flow.

• In-plant operators arestanding-by forthe URO tocontinue inST-O-014-301-2,"Core Spray LoopA Pump, Valve, Flow, and CoolerFunctional and Inservice Test".

CriticalCritical Task #1:Whena primary system isdischarging through an Tasks unisolable leak,scram thereactor prior toperforming anEmergency Blowdown.

Critical Task #2:Perform anEmergency Blowdown whentheradioactive release cannot bemaintained below theGeneral Emergency threshold.

2020NRCScenario #4D-1Rev1

Appendix D Scenario Outline ES-D-1 Event Malfunction Event Event No. No. Type* Description 1 SeeScenario Guide C URO Control rodbecomes uncoupled /recouple using ON-105 CRS 2 SeeScenario Guide R URO Raise reactor power withrecirculation flow.

CRS 3 SeeScenario Guide N PRO Start ST-O-014-301-2, "Core Spray Loop A Pump, Valve, TS CRS Flow,andCooler Functional andInservice Test".CRS enter/apply Technical Specifications.

4 C PRO Loss ofpower toRPSbreaker andtransfer ofRPSto SeeScenario Guide TS CRS alternate supply. CRSenter/apply Technical Specifications.

5 C PRO Standby Gas Treatment System (SGTS) B fail tostart.CRS SeeScenario Guide TS CRS enter/apply Technical Specifications.

6 SeeScenario Guide C URO Lower reactor power due torising process radiation, CRS followed bya manualscram.

7 SeeScenario Guide M ALL Steam leak intheTurbine Building 8 SeeScenario Guide C ALL Failure ofthe 'D' MSLtomanually isolate.

9 SeeScenario Guide M ALL Fuel damage with release tothe environment requires Emergency Depressurization.

• (N)ormal,(R)eactivity, (C)omponent, (1)nstrument, (M)ajor, (TS)

TechSpec 2020NRCScenario #4D-1Rev1

ES401 BWRExamination Outline FORMES-401-1 Name:Peach Facility Bottom Date ofExam: 6/1/2020 ROK/ACategory Points SRO-Only 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 3 3 4 3 4 20 3 4 7 Emergency&

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

Plant 2 1 1 1 1 1 2 1 1 1 1 1 12 0 2 1 3 Systems Tier Totals 4 3 3 3 4 4 4 3 4 3 3 38 5 3 8 3.Generic Knowledge andAbilities 1 2 3 4 1 2 3 4 Categones 2 3 3 2 1 2 2 2 Note:1. Ensure thatatleast twotopics fromevery applicableK/Acategory aresampled within each tieroftheROandSRO only (i.e.,

outlines exceptforonecategory inTier3oftheSRO-only outline, the"Tier Totals" ineach K/Acategory shallnotbeless thantwo).(One Tier 3 Radiation ControlK/Ais allowed if theK/Aisreplaced bya K/Afrom another Tier3 Category).

2. Thepoint for total eachgroup andtier intheproposed outlinemustmatch that specified inthe table. Thefinal pointtotalforeach groupandtier maydeviate by11from thatspecifiedin the table based onNRCrevisions. The finalROexammusttotal 75points andthe SRO-only exammusttotal 25points.

3. Systems/evolutions withineach group are identified onthe associated outline;systems or evolutions thatdonot apply atthefacilityshouldbedeleted andjustified; operationallyimportant, site-specific systems thatarenot included ontheoutline should beadded. RefertoSection D.1.b ofES-401 for guidance regarding theelimination ofinappropriate K/Astatements.

4. Select from topics asmanysystems andevolutions aspossible; sample every system orevolution inthegroup before selectingasecond topicforanysystem orevolution.

5. Absent a plant-specific only priority, those K/Ashaving animportance rating (IR) of2.5 orhighershall beselected.

UsetheROandSROratings fortheROandSRO-only portions,respectively.

6. Select SROtopics forTiers1 and2 from theshaded systems andK/Acategories.

7.* Thegeneric (G) K/As inTiers1and2 shall beselectedfrom Section 2 oftheK/ACatalog, butthe topicsmust be relevanttothe applicableevolutionorsystem. RefertoSection D.1.b ofES-401 for theapplicable K/As.

8. Onthefollowing pages,entertheK/Anumbers, a brief description ofeachtopic, thetopics' importance ratings (IRs)fortheapplicable licenselevel, andthepoint totals(#)for eachsystem andcategory. Enter thegroup and totals tier foreachcategory inthetable above;ifuel handling equipment issampled inother than Category A2 or G*ontheSRO-only exam,enter onthe it left side ofColumn A2for Tier 2,Group 2 (Note #1doesnotapply). Use duplicatepages forROandSRO-only exams.

9. ForTier 3,select topicsfromSection 2 oftheK/Acatalog, andenter theK/Anumbers, descriptions, IRs, andpoint totals(#) onFormES-401-3. LimitSROselections toK/As thatarelinked to10CFR55.43.

G* Generic K/As

ES401 2 FormES-401-1 ES-401 BWRExamination Outline FormES-401-1 andAbnormal Emergency Plant Evolutions -

Tier 1/Group 1 (RO)

E/APE # /Name /SafetyFunction K K K A #

/fp K/ATopic(s) IR #

1 2 3 1 , f

/

295001 orComplete LossofForced Partial 0 Vg Knowledge ofthereasons for thefollowing responses asthey apply toPartial or 2.9 1 Core Flow /1& 4 Circulation 6 T Complete Loss ofForced CoreFlow Circulation: Coreflow indication 295003 PW a CWW W of E /6 0 Knowledge ofthe operational implications ofthe followingconcepts asthey applyto 3 4 5 g Partial orComplete Loss ofAC:Failsafe component design 0 Ability tooperate and/or monitor thefollowing asthey apply toPartial orTotal Lossof p j ofDCPwr/ 6

@/

295004 Partial orTotal Loss 3 DCPwr: A.C. electrical distribution "r

0 Ability tooperate and/or monitor thefollowing asthey apply toMain Turbine Generator g 3 295005 MainTurbine Generator Trip /3 2 Sa Trip: RPS 295006 SCRAM /1 /@,Knowledge oftheinterrelations between SCRAM andthe following: Reactor power 4.2 1 Ability todetermine and/or interpret the following asthey apply toControl Room 295016 ControlRoomAbandonment /7 Abandonment: Suppression pooltemperature 3.9 1 todetermine and/or interpret thefollowing asthey apply toPartial orTotal Loss 295018 orTotal Partial LossofCCW/8 Ability of CCW: Cause forpartial orcomplete loss n 3 A

Ability to determine and rnterpret the fonowing asthey apply toPartial orTotal Loss 295019 orTotal Partial Lossofinst. Air/8 3.5 1 o

295021 LossofShutdown Cooling /4 0 4

p/ 4, Knowledge Loss ofthe operational implicationsofthefollowing ofShutdownCooling: Naturalcirculation concepts asthey applyto 3.6 1 0 Knowledge oftheinterrelations between Refueling Accidents andthe following: y 295023 Refueling Acc/8 4 .A/ RMCS/Rod control andinformation system 4 295024 HighDrywellPressure /5 0

1

/b Ability tooperate HPCI(FWCI):

and/or monitor Plant-Specific thefollowing as theyapply toHigh Drywell Pressure:p 3

A./

Ability torecognize abnormal indicationsfor system operating parametersthat are 295025 HighReactor Pressure/3 ,

entry-level conditions for emergency andabnormaloperating procedures.

3 3 295026 SuppressionPool High Water W./ Ability tointerpret control roomindications toverify thestatus and operation ofa

/5 system, andunderstand howoperator actions anddirectivesaffect plantandsystem 4.2 1 Temp.  ! conditions.

295027 HighContainment Temperature /5 0 295028 HighDrywellTemperature /5 0 Ability tooperate and/or monitor thefollowing asthey apply toHigh Drywell 4 f Temperature: Drywell pressure 3.9 1 295030 LowSuppression PoolWtrLvI /5 0 7 //4 g Know!edge following:

oftheinterrelations Downcomer/

between honzontal vent LowSuppression submergence Pool WtrLvl andthe 3.5 1 295031 ReactorLowWater Level/2 Ability tolocate andoperate components, including localcontrols. 4,4 1

/

295037 SCRAM Condition Presentand 4/

't Ability to evaluate plant performance andmakeoperational judgments basedon q Reactor Power Above APRMDownscale or '// operating characteristics, behavior, reactor andinstrument interpretation. 4 Unknown/1 #

/

295038 HighOff-site Release Rate /9 0 p A4 Knowledge oftheoperational implications ofthe following concepts asthey applyto 3 3 3 , High Off-site Release Rate: Meteorological effects onoff-site release 0 #' Knowledge ofthereasons for thefollowing responses asthey apply toPlant On Fire 600000 Fire Plant OnSite /8 Site: Actions onsite 3 3 4 .

. contained intheabnormal procedure plant for fire 700000 GeneratorVoltage andElectric Grid 0 / / Knowledge Voltage ofthereasons andElectric Grid thefollowing for Disturbances:

responses Actions asthey contained apply toGenerator inabnormal operating 36 1 Disturbances/6 2 f procedure for voltage andgrid disturbances

^

K/ACategory Totals: 3 3 3 4 A Group Point Total: 20 A .

ES-401, Page 34of50

ES-401 3 FormES-4011 ES-401 BWRExamination Outline FormES-401-1 Emergency andAbnormalPlant Evolutions -

Tier 1/Group 2 (RO)

E/APE# /Name /Safety Function 1 2 3 1 4p //

K/ATopic(s) IR #

295002LossofMain Condenser Vac/3

'y 295007HighReactor Pressure /3 0 e

"f

@,f ofthe

/ operationKnowledge Pressure:

reasons following Reactor/turbine for the pressure regulating responses system asthey apply toHigh Reactor 3.7 1 x

/ /

295008HighReactor Water Level /2 / 0

///f/

295009LowReactor Water Level /2 / 0 295010HighDrywellPressure /5 0 295011HighContainment Temp/5 0 295012HighDrywellTemperature /5 0 295013HighSuppression Pool Temp. /5 0 4 (/ '

Knowledge of the operational HighSuppression Pool Temp.:

implications Complete ofthe following condensation concepts asthey apply to p9 3 295014 Reactivity Inadvertent Addition/1 //*i 0 295015IncompleteSCRAM /1 0 Knowle geoftheinterrelationsbetween incomplete SCRAM andthe CRD following: p q 1 Ability tooperate and/or monitor thefollowing as theyapply toHigh Off-siteRelease 295017HighOff-site Release Rate /9 2 Rate:Meteorological data 2.5 1

/J w

295020 Cont.

inadvertent isolation/5 & 7 0

// Knowledge oftheparameters andlogic used toassess thestatus of safety functions, 295022LossofCRDPumps /1 4 suchasreactivity control, core cooling andheat removal,reactor coolant system 4.0 1 integrity, containment conditions, radioactivityrelease control,etc.

295029HighSuppression Pool WtrLvI /5

!/

295032HighSecondary Containment Area #Rg Ability todetermine and/or interpret thefollowing astheyapply toHigh Secondary 3

Temperature

/5 A, Containment AreaTemperature: Equipment operability 4

295033HighSecondary Containment Area 0

Radiation Levels/9 295034Secondary Containment Ventilation @ / 0 High /9 Radiation J 295035Secondary Containment High 4*

Differential Pressure /5

@ 0 295036Secondary Containment High /'d g Sump/Area Water Level /5 g

1. '/V

//

500000HighCTMTHydrogen Conc. /5 0 Knowledge ofthereasons for thefollowing responses asthey apply toHigh CTMT y 3 4 gHydrogen Conc.: Emergency depressurization K/ACategory Totals: 1 1 2 1 $', / ~

Group Point Total: 7

% //

ES-401, Page35of50

ES-401 4 FormES4011 ES-401 BWRExamination Outline FormES-401-1 Systems Plant -

Tier 2/Group 1(RO)

K K K K K K A# A A K/ATopic(s) IR #

System #/Name 1 2 3 4 5 6 1 e> 3 4 ,/>

g g Ability tomonitor automatic operations oftheRHR/LPCl: Injection Mode gj 203000 RHR/LPCl: Injection Mode includng@eMnhn muem AMWnanuaHy ophnnhondor 2 8 2 inthecontrol room: System valves 43 205000 Shutdown Cooling 0 /d &cKnowledge ofthe effect thata loss ormalfunction oftheShutdown Cooling win p 4 / have onfollowing: Recirculation loop temperatures 206000 HPCI 0 Knowledge ofthephysical connections and/or cause-effect relationships 4g j 2 A betweenHPCIandthefollowing: Reactor water level: BWR-2, 3,4 207000 Isolation (Emergency)

Condenser pp /// 0 V, thmepredans, useprocedures tocorrect, control, ormitigate the 209001 LPCS consequences ofthose abnormal conditions oroperations: Inadequate system 3.2 1

• 1. 4 J 209002 HPCS 0 WJ 211000 SLC 0

3 rg F9

@ "9 Knowledge toSLC:

oftheoperational Shutdown margin implications ofthefollowing concepts asthey applyy 4

g 1, Knowledge ofthe effect thata loss ormalfunction ofthe RPSwill haveon 3.8 212000 RPS 7 / '4following:Reactor strategies.

power (thermal heat flux);

Knowledge ofEOPmitigation 3.7 2 0 Ability topredict and/or monitor changes inparamete rsassociated with y N003 M 3 the IRMcontrols including: Lightsandalarms 6 < , operating 215004 Source Range Monitor g 0 0 0 Knowledge ofelectrical powersupplies tothe following: APRMchannels" 2g.'

215005 APRM/LPRM 2 1 Knowledge oftheoperational implications ofthe following concepts asthey apply 2.8 2

,. toAPRM /LPRM: LPRM detector operation 217000 RCIC 4 0 $

f @

V/ between Knowledge ofthe physicalconnections RCICandthefollowing:

and/or Main condenser cause-effect relationships y 3

218000 ADS 0

1

1. , @ Knowledge A toADS:ADSlogic oftheoperational operation implications ofthe following concepts asthey applyy 223002 PCIS/Nuclear Steam Supply 1 0 between PCIS/Nuclear Steam Supply Shutoffand the following: Standby gas 3.1; 2

Shutoff 2 ,

2 j treatment system; Ability tomonitor automatic operations ofthe PCIS/Nuclear 3.5 0 '/ KnowledgnMhuffecMhat a losonnaWunchon oMhefodowing wiHhaven 239002 SRVs , 3.0 1 5 ,

g the SRVs: Discharge linevacuum breaker 0 0 2.9; y/ level operating theReactor Water Level Control controls including:FWRV/startup 259002 ReactorWater LevelControl 5 #a,, 4 control position: Plant-Specific; Abilitytomonitor automatic operations of 3.2 2 261000 SGTS 0 Knowledge ofSGTSdesign feature(s) and/or interlocks which provide for the p 1 following: Automatic system initiation g Ability topredict and/or monitor changes inparameters associated with 262001 ACElectrical Distribution operating theACElectrical Distribution controlsincluding: Effectsofloads when 3.1 1 2 ..

energizing a bus F ' '

Ability (a) to predict theimpacts ofthefollowing ontheUPS(AC/DC); and(b) 262002 UPS(AC/DC) d // based onthose consequences predictions, ofthose useprocedures abnormal conditions tocorrect, control, oroperations: Over ormitigate voltage the 2.5 1 263000 DCElectrical Distribution 0 provide forthefollowing: Breaker interlocks, permissives, bypasses andcross 31; 2

&, ties:

2 /

1. Plant-Specific; Knowledge ofthedesign, procedural, andoperational 3.8 264000 EDGs 0 Ability tomanually operate and/or monitor inthe control room: Transfer of p j 3 xg emergency control between manual andautomatic 300000 InstrumentAir 0 y4 Knowledge ofthe effect thataloss ormalfunction ofthe following willhave on 2.5 1 7 y theInstrument Air: Valves 00000 Component Cooling Water Knowledge ofelectrical power supplies tothe following: CCWpumps 2.9 1 K/ACategory Totals: 3 2 2 2 3 2 3

@ fg 3 2 Group Point Total: 26 ES-401, Page36of50

ES-401-1 5 FormES401-1 ES-401 BWRExamination Outline FormES-401-1 Systems Plant -

Tier 2/Group 2 (RO)

K K K K K K A "^ A A y";

System # / Name 1 2 3 4 5 6 1 3 3 4 M K/ATOpic(s) IR #

201001 CRDHydraulic re P O 01002 RMCS @, , 0 01003 Control RodandDrive Mechanism interlocks which provide forthe following: Limitingcontrol rodspeed intheevent 2.9 1 01004 RSCS  % "Ji,j 0 201005 RCIS 0 201006 RWM 0

4 gg y,/j

//#,

Knowledge RWM:Process ofthe effect computer:

thata loss ormalfunction P-Spec(Not-BWR6) ofthefollowing willhaveonthe p7 3

0 '# Knowledge ofthe physical connections and/orcause-effect relationships between 02001 Recirculation p 3 7 '/fff Recrculation andthefollowing: Component cooHng water systems 202002 RecirculationFlow Control O 04000 RWCU * W O

214000 RPIS O

// w 15001 Traversing In-coreProbe O

215002 RBM "".,, '

, those predictions, useprocedures tocorrect, control, ormitigate the 3.0 1 16000 Nuclear BoilerInst. Relationship between readings meter/recorder andactual parameter values: 3.4 1 19000 RHR/LPCI: Torus/PoolCooling 0 ,,/v ljV/

, p (fg, Knowledge of electrical power supplies tothe following: Valves 2.5 1 223001 Primary CTMTandAux. O z

26001 RHR/LPCl: CTMTSpray Mode 5'// .

O 30000 RHR/LPCl: Torus/PoolSpray Mode 0 33000 Fuel Pool Cooling/Cleanup ~'

"4'Ability tomanually operate and/or monitor inthecontrol room: Tank levels 2.5 1 34000 Fuel HandlingEquipment

't( @ O 39001 Main andReheat Steam '~^. Ability torecognize Technical system specifications.

parameters thatare entry-level conditions for 3.9 1 239003 MSlVLeakage Control 0 41000 Reactor/Turbine Regulator Pressure 0 245000 Main TurbineGen. /Aux. 0 56000Reactor Condensate O fg'/ Knowledge ofthe operational implications ofthefollowing concepts astheyapply 3 3 3 f 7ffe toReactor Condensate: Heatexchanger level operation 59001 Reactor Feedwater 7/ m a

0 Knowledge oftheeffect thata loss ormalfunction oftheRadwaste haveon p7 will 268000 Radwaste 3 4 4'A following: Drain sumps 271000 Offgas 1 ,, Ability topredict and/or monitorchanges inparameters associated withoperatingp 4 theOffgas controls including:Oxygen gasconcentration 3

/f 72000 Radiation Monitoring O 1 /b y f Knowledge 9 Radiation oftheeffect Monitoring:

thataloss Reactor ormalfunction protection system ofthe following willhaveonthe 30

' 1 286000 Fire Protection bd' O 88000 Plant Ventilation

// O 90001 Secondary CTMT

0 90003 Control RoomHVAC , 0 90002 Reactor Vessel internals fj (o/

0 7

ray/ .

/ W/A K/ACategory Totals: 1 1 1 1 1 2 1 , J1 1 ,

~

Group Point Total: 12 ES-401, Page37of50

^

ES-401 2 FormES-401-1 ES-401 BWRExamination Outline FormES-401-1 Emergency andAbnormal Plant Evolutions -

Tier1/Group1 (SRO)

E/APE # /Name /SafetyFunction K/ATopic(s) IR #

295001 Core Flow orComplete LossofForced Partial

/1 & 4 Circulation g #'f6 0 295003 orComplete Partial Loss of AC/6 fpfA r#A L/

295004 orTotal Paiiial Loss ofDCPwr/ 6 @' ' "'

Knowledge ofannunciator alarms,indications, procedures.

orresponse 4.1 1 295005 MainTurbineGenerator Trip/3 0 Ability todetermineand/or interpret thefollowingasthey apply to 295006 SCRAM /1 4.2 1

/

g

/ SCRAM: Reactor level water 295016 ControlRoomAbandonment /7 7 0 Ability todetermineand/or thefollowing interpret asthey apply toPartial 295018 Partial orTotalLoss ofCCW/8 or Total Loss ofCCW:System pressure 2.9 1 295019 orTotal Partial Loss ofInst.Air/8 0 295021 LossofShutdown Cooling /4 0 A

/ '

295023 Refueling Acc/8 0 v ##

295024 HighDrywellPressure /5 Knowledge condition ofabnormal procedures. 4.2 1 295025 HighReactorPressure /3 A 0 W@

fg 295026 SuppressionPool High Water g Temp. /5

~

295027 HighContainment Temperature l5 . 0 295028 HighDrywellTemperature /5 Ability toexplainandapply system limits andprecautions. 4.0 1 Knowledge oftheprocess formanaging maintenance activities during 295030 LowSuppression Pool WtrLvI /5

shutdown such operations, asriskassessments, workprioritization, etc.

Ability todetermineand/or the interpret following asthey apply toReactor 295031 ReactorLowWater Level /2 LowWater Level:

Adequatecorecooling 4.8 1 SCRAMCondition 5 '

295037 Present andReactor Power Above APRM 0 Downscale orUnknown /1 295038 HighOff-site Release Rate /9 0 600000 PlantFireOnSite /8 0 700000 GeneratorVoltage andElectric Grid '/ g g Disturbances/6 K fg K/ACategory Totals: 0 0 0 0 y Group Point Total: 7 ES-401, Page34of50

ES401 3 FormES401-1 ES-401 BWRExamination Outline FormES-401-1 Emergency andAbnormalPlant Evolutions -

Tier1/Group 2 (SRO)

K K K A <

K/ATopic(s) IR #

E/APE# /Name /Safety Function 1 2 3 1 #( o 295002LossofMain Condenser Vac/3 '

0 295007HighReactorPressure /3 "

0 295008HighReactorWater Level /2 0 A

295009LowReactor Water Level /2 A7 0 295010HighDrywellPressure /5 A 0

/##u 295011HighContainment Temp/5

~ todiagnose andrecognize inanaccurate trends andtimely manner utilizing 295012HighDrywellTemperature /5 '

Ability the appropriate roomreference control material.

q 4 295013HighSuppression Pool Temp. /5 0

/A 295014 Reactivity Inadvertent Addition/1 *f O 295015IncompleteSCRAM /1 f 0 295017HighOff-site Release Rate /9 / 0 n ,

Ability todetermine and/or interpret the asthey following apply toInadvertent Cont.

295020 Cont.

Inadvertent Isolation/5 & 7 isolation: Reactorpressure 3.9 1 295022LossofCRDPumps/1 x 0 295029HighSuppression Pool WtrLvl /5 ,f ) a 295032HighS condary Containment Area A g 295033HighSecondary Containment Area g/ /;ff') g Radiation Levels/9 'c /'/

295034SecondaryContainment Ventilation ,g, HighRadiation

/9 @, 0 295035SecondaryContainment High Y Ability todetermine interpret and/or asthey thefollowing apply toSecondary Con nmentHigh Differential Secondary Pressure: containment pressure:Plant- 3.9 1 Differential Pressure/5 ,

1. f 295036SecondaryContainment High Sump/Area Level 0 Water /5 vp 500000HighCTMTHydrogen Conc. /5 Y 0 K/ACategory Totals: 0 0 0 0 Group Point Total: 3 ES-401, Page35of50

ES401 4 FormES-4011 ES-401 BWRExamination Outline FormES-401-1 SystemsTier Plant -

2/Group 1 (SRO)

System # /Name K K K K K K A 1 2 3 4 5 6 1

(

by /

A A 3 4 4, K/ATopic(s) IR #

203000 RHR/LPCl: Injection ,,

0

/'

/

205000 Shutdown CoolingMode 0

//

206000 HPCI *#' Ability tointerpret andexecute procedure steps. 4.6 1 207000 isolation(Emergency) g Condenser d 209001 LPCS V/

d'A /#,g Ability andinterpret toprioritize thesignificance ofeach oralarm. 4.3 annunciator 1 209002 HPCS 0 A

211000 SLC 0 212000 RPS A 0

'/

215003 IRM 215004 Source Range Monitor N

/#

4$$

"16 0

215005 APRM/LPRM 0 3 ,.,

217000 RCIC

'7/

/ /

0 ADS those use predictions, tocorrect, control, ormitigate procedures the 218000 3.6 1 aj consequences abnormal ofthose conditions oroperations: Lossofairsupplyto 223002 Shutoff PCIS/Nuclear Steam Supply dfj g

/

239002 SRVs 4 0

1. 2 259002 Reactor Water LevelControl @b /3'//

0 (a)

Ability to predict theimpacts ofthe followingontheSGTS;and(b) based on 261000 SGTS useprocedures predictions, those tocorrect, control ormitigate the 3.1 1

,f consequences ofthose abnormal conditions oroperations: Fantrips 262001 ACElectrical Distribution 0 ff y

262002 UPS(AC/DC) Tg 0 263000 DCElectrical Distribution "< , 0

///' *4' (a)

Ability theimpacts to predict ofthe followingontheEDGs;and(b) based on 264000 EDGs f/ useprocedures predictions, those tocorrect, control, ormitigate the 4.1 1 A consequences ofthose conditions abnormal oroperations: Loss power ofA.C.

300000 instrumentAir 0 00000 Component Cooling Water 7//// 0 f

K/ACategory Totals: 0 0 0 0 0 0 0d z 0 0 //'Group PointTotal: 5

'or's ES-401, Page36of50

ES401 5 FormES-401-1 ES-401 BWRExamination Outline FormES-401-1 Systems Plant -

Tier 2/Group 2 (SRO)

K K K K K K A T.4A A System # / Name 1 2 3 4 5 6 1 @ 3 4 K/ATopic(s) IR #

01001CRDHydraulic a O 01002 RMCS

1. 2 01003 ControlRodandDrive Mechanism ~. O 01004 RSCS 2 0 01005 RCIS 7 0 01006RWM  ;

Wad 0

02001 Recirculation O 02002 Recirculation FlowControl 'p 0 04000 RWCU O 214000 RPiS 0 n

215001 Traversing Probe In-core yf Knowledgeofabnormal condition procedures. 4.2 1 215002 RBM d 0 A FAff 16000Nuclear BoilerInst.  ; 0 19000RHR/LPCl: Cooling Torus/Pool fgg Mode V2 @ O 23001Primary CTMTandAux. 0 f,g 26001 RHR/LPCI: CTMTSpray Mode '

Mode;and(b)based on those predictions, useprocedures tocorrect, or 2.6 control, 1 30000 RHR/LPCl: Spray Torus/Pool Mode "f da

~'

0 233000 FuelPool Cooling/Cleanup 0 34000 FuelHandlingEquipment

/ ,a me

1. , p o 39001 Main andReheat Steam ,,,, O 39003 MSIVLeakage Control 0 "a

241000 Reactor/Turbine PressureRegulator up 0 45000MainTurbine Gen./Aux. g O 56000Reactor Condensate

@ 0 59001 ReactorFeedwater 0 68000 Radwaste O 71000 Offgas  ! 0 72000Radiation Monitoring '

, O 86000 FireProtection f,/ 0 88000 PlantVentilation basedonthose useprocedures predictions, ormitigate control, tocorrect, the 3.7 1

'#/

90001 Secondary CTMT 0 90003 ControlRoomHVAC 0 90002 ReactorVessel internals #

@ 0

/ #

K/ACategory Totals: 0 O 0 O 0 0 0 6,; 0 0 ,g,4Group PointTotal: 3 ES-401, Page37of50

Facility Name:Peach Bottom Date ofExam:6/1/2020 n

Category K/A# Topic IR # IR #

p Knowledge ofprocedures, guidelines, orlimitations associated with reactivity j management.

2.1.

3 2.1. personnel 08 Ability tocoordinate activities outside thecontrol room. 3.4 1 4.1 Conduct of 2.1. 01 Knowledge ofconductofoperations requirements. 3.8 1 4.2 Operations 2.1.

2.1 Subtotal 2 1 2.2. 21Knowledge ofpre-and post-maintenance operability requirements. 2.9 4.1 1 Ability toanalyzetheeffect ofmaintenance activities, such asdegraded power sources, 22 % onthestatus oflimiting conditions for operations.

31 42 1

2. 2.2.

2.2. 22 Knowledge oflimiting conditions for operations andsafety limits. 4.0 j 4.7 Control 22' ' WAbility shutdown tomanipulate theconsole anddesignated power controls levels asrequired tooperate the facility between 43 j 4j 2.2. 13Knowledge oftaggingandclearance procedures. 4.1 1 4.3 Subtotal 3 2 Ability touseradiation monitoring systems, such asfixed radiation monitors andalarms, 23 M portable survey instruments, personnel monitonng equipment, etc. 29' 29 1 2.3. 11Ability tocontrol radiationreleases 3.8 4.3 1 3 2.3.

Radiation 2.3. 07Ability tocomplywithradiation work permit requirements during normal orabnormal p

ggl conditions.

Knowledge ofradiologicalsafety procedures pertaining tolicensed operator duties,such 2.3. 13 asresponse toradiationmonitor alarms, containment entryrequirements, handling fuel 3.4 1 3.8 resonsibilitiesaccess tolocked hih-radiation areas allninfilters etc.

Knowledge monitoring ofradiation systems, suchasfixed radiation monitors andalarms, 2 3 15 portable survey instruments, personnel monitoring equipment, etc. 29 1 31' Subtotal 3 2 2.4. 44 Knowledge ofemergency plan protective action recommendations. 4.4 j 2.4. 08Knowledge ofhowabnormal operating procedures areusedinconjunction EOPs.

with 3.8 4.5 1

4. 2.4.

Emergency Procedures 2.4. 18Knowledge ofthespecificbases for EOPs 3.3 1 4.0

/Plan Knowledge auxiliary oflocal tasks during anemergency andtheresultant y operational effects.

operator j 2.4.

Subtotal 2 2 Tier 3PointTotal 10 7 ES-401, Page43of50

ES-401 Record ofRejected K/As FormES-401-4 Tier / Rejected K/A Reason for Rejection Grou RO Question 13 Unable towriteaquestion for selected K/A.Peach Bottom Tier2/ 215003 Intermediate Range has Wide Range Neutron Monitor (WRNM) System. This iscomparable tothe IRMsystem inmostways, however Monitor ORM) Systena mostofthe WRNMsystem isautomatic. This includes Group 1 A1.05Abilityto predict and/or

- auto-ranging forthe t rip and rod b lock setpoints. Since the monitor changes in parameters system isautomatic, thereisnotsufficient operator associated withoperating the manipulations onthe WRNMtodevelop aquestion.

Intermediate Range Monitor (IRM) Randomly resampled K/A215003Intermediate Range System controls including:SCRAM Monitor (IRM) System androd block trip setpoints Al.06 Ability topredict and/or monitor changes in parameters associatedwith operating the Intermediate Range Monitor (IRM) System controls including: Lights and alarms RO Question 64 Unable to develop 3creditable distractors asthe auxiliary operatortasks during a loss ofCRDpumpsislimited to Tier1/ 295022Loss -

ofCRDpumps performingchecks and manipulate onevalve during a Group 2 2.4.35 -

Knowledge oflocal standby auxiliary pumpstart, orbypassthe suction strainer if thatis operator tasksduring emergency and clogged.

theresultant operational effects. Randomly resampledK/A 295022 -

Loss ofCRDpumps 2.4.21 -

Knowledge oftheparameters andlogic used to assess the ofsafety status functions, suchasreactivity control, corecooling andheat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

SRO Question 79 Unable todevelop a question for selected System and K/A combination asthere arenoROtasks performed outside Tier1/ 295028High -

Drywell Temperature the main controlroomduring aHigh Drywell Temperature Group 1 2.4.34 -

Knowledge ofROtasks event.

performed outside the maincontrolRandomly resampled K/A295028High -

Drywell roomduring anemergency andthe Temperature resultant operational effects.

2.1.32 -

ability toexplain andapply system limits and precautions.

SRO Question 81 Unable towriteanSROonly level question based onK/A asthe ability tolocate switches, controls andindications to Tier1/ 295030LowSuppression Pool determine plant lineup isaROjob.

Water Level Group 1 Randomly resampled K/A295030LowSuppression Pool 2.1.31 -

Abilitytolocate control Water L evel roomswitches, controls, and indications, andtodetermine that 2.2.18 -

knowledge ofthe process for managing theycorrectly reflect the desired plantmaintenance activitiesduring shutdown operations, suchas lineup. risk assessments, work prioritization, etc.

ES-401 Record ofRejected K/As FormES-401-4 SRO Question 84 System overlap with Tier 1-Group 2 ROquestion number 63(295032). This would bethe second time system Tier1/ 295032 -

High Secondary 295032 hadbeen selected onthe SROexamandIAW ES-Containment Area Temperature 401, all systems inagroup mustbeselected beforedouble 2.4.20 Knowledge ofthe operation selecting a system in a group.

implications of EOP warnings, Randomly resampled Tier 1-Group 2 SROsystem cautions, andnotes (295032) andK/A 295012High-Drywell Temperature 2.4.47 -

Ability todiagnose and recognize trendsinan accurate andtimely manner utilizing the appropriate control roomreference material.

SRO Question 86 System overlap with Tier 2-Group 1ROquestion numbers 3and 24(215005). This would bethe third timesystem Tier2/ 215005APRM/LPRM 215005 had been selected onthe SROexam.IAW ES-401 Group 1 A2.06Ability impacts ofthe (a) to predict following the onthe allsystems selecting a in a group system.

must Although be selected not once explicitly before stated in double ES-APRM/LPRM;and (b)basedon 401 we carry this logic forward in that allsystems in a those predictions, useprocedures to group must be double selected before being selected a third correct, control,ormitigatethe t1me.

consequences ofthose abnormal Randomly resampled Tier 2-Group 1SROsystem conditions oroperations:

Recirculation flow channels upscale (215005) andK/A 264000Emergency Generators (Diesel/Jet)

A2.09Ability onthe Emergency (a) to predict Generators theimpacts of thefollowing (Diesel/Jet); and (b) based onthose predictions, useprocedures tocorrect, control, or mitigate the consequences ofthose abnormal conditions or operations: Loss ofA.C. power SRO Question 87 System overlap with Tier 2-Group 1ROquestion numbers 5and 21(212000). This w ould be the t hirdtimesystem Tier2/ 212000Reactor Protection System 212000 hadbeen selected onthe SROexam.IAW ES-401 Group 1 A2.01Ability impacts ofthe (a) to predict following on the the allsystems selecting a in a group system.

must Although be selected not oncebefore explicitly stated in double ES-Reactor Protection System;and(b) 401we carry this logic forward inthat allsystems ina based onthose predictions, use group mustbedouble selected before being selected athird procedures tocorrect, control, or time.

mitigate theconsequences ofthose Randomly resampled Tier 2-Group ISROsystem abnormal conditions oroperations:

(212000) andK/A RPSmotor-generator setfailure 218000Automatic Depressurization System A2.03Ability onthe Automatic (a) to predict the Depressurization impacts System; ofthe following and(b) based onthose predictions, use procedures tocorrect, control, or mitigate the consequences ofthose abnormal conditionsor operations: Loss ofair supply toADSvalves

ES-401 Record ofRejected K/As FormES-401-4 SRO Question 88 Unable towrite anSROonly level about question system purpose andfunction ofmajorsystem asthis components Tier 2/ 206000 -

High Pressure Coolant is also ROnecessary knowledge.

Injection Group 1 Randomly resampled K/A206000 -

High Coolant Pressure 2.1.28 -

Knowledge of the purpose andfunctionof major system 2.1.20-Abilitytointerpretandexecute procedure steps components and jcontrols.

SRO Question 89 Unable towrite aquestion fortheselectedSystemandK/A combinationasthere nolocal are auxiliary tasks operator Tier 2/ 209001LowPressure Core Spray associatedwith Core during Spray anemergency.

System Group 1 Randomly resampled K/A209001LowPressure Core 2.4.35 -

Knowledge oflocal auxiliary Spray System operator tasks during emergency and the resultant operational effects. 2.4.45 Ability toprioritize andinterpret thesignificance ofeach annunciator oralarm Random selection wasusing anonline random number generator. www.random.org