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
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Download: ML20260H165 (32)

Text

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

W Jo e # 20 DateofExamination:

Initials Item TaskDescription a

b* c**

1.

a.Verify that theoutline(s)fit(s) theappropriate modelinaccordance withES-401 orES-401N.L4 Q'C W

b.Assesswhether theoutline wassystematically andrandomly prepared inaccordance with

. 4 7

R section D.1 of ES-401 orES-401N andwhether all K/Acategories areappropriately sampled.

I[

c.Assess whetherthe outline overemphasizes anysystems, evolutions, orgeneric topics.

M f7C

[

d.Assess whether thejustifications for deselected orrejected K/Astatements areappropriate.g g 4 2.

a.Using FormES-3015, verify that theproposedscenario setscover therequired numberof normal evolutions, instrument and component

failures, technical specifications, andmajor 4

TT$

S transients.

I M

b.Assess whether there areenough scenario sets(and spares) totest theprojected number and U

mixofapplicants inaccordance with the expected crewcomposition androtation schedule L

without compromising examintegrity, and ensure that eachapplicant canbetested using at f-f)"@

A least oneneworsignificantly modified

scenario, thatnoscenariosareduplicated fromthe T

applicants' audit test(s),

andthat scenarios will not berepeated onsubsequent days.

c.Totheextent

possible, assess whether the outline(s) conforms with thequalitative and quantitative criteria specified onFormES-301-4 anddescribed inAppendixDandin C*

Section D.5,"Specific Instructions forthe'Simulator Operating Test,'" ofES-301 (including overlap).

3.

a.Verify that thesystems walkthrough outline meetsthecriteria specified onFormES-301-2:

(1)Theoutline(s) contains therequired numberofcontrol room and in-plant tasks distributed W

amongthesafety functions asspecified ontheform.

A (2)Taskrepetition from thelast twoNRCexaminations iswithin thelimitsspecified ontheform.(A g L

(3)Notasks areduplicated fromtheapplicant's audit test(s).

K (4)Thenumber ofnewormodified tasks meets orexceeds theminimums speclied on theform.

T (5)Thenumber ofalternate-path, low-power, emergency, andradiologically controlled area H

tasks meetsthecriteria ontheform.

R O

b.Verify that theadministrative outline meetsthecriteria specified onFormES-301-1:

U (1)Thetasks aredistributed amongthetopics asspecified ontheform.

G (2)Atleast onetask isneworsignificantly modified.

L&

(

H (3)Nomorethanonetaskisrepeated fromthelast twoNRClicensing examinations.

c. Determine whether there areenoughdifferent outlines totest theprojected numberandmixof applicants andensure thatnoitems areduplicated onsubsequent days.

Ct l

4.

a.Assess whether plant-specific priorities (including probabilistic risk assessment andindividual

<V 7 7 plant examination insights) arecovered intheappropriate examsections.

G E

b.Assesswhether the10CFR55.41, 55.43, and55.45sampling isappropriate.

c// 7 c.Ensure thatK/Aimportance ratings (except forplant-specific priorities) areatleast 2.5.

c//-7 R

d Check forduplication andoverlap amongexamsections andthelast twoNRCexams 4' Q'@

A L

e.Checktheentire examforbalance ofcoverage.

d' (

~'

f.Assess whether theexamfits theappropriate joblevel (ROorSRO).

C // ff Printed Namg/Sighatwe

/

Date

a. Author dfd2tr eve 2M 2c

b. Facility Reviewer

(*)

• c

~

c. NRCChief Examiner

(#)

d. NRCSupervisor m f

• Notapplicable forNRC-prepared examination outlines.

1. Theindependent NRCreviewer initials items incolumn"c";

thechief examiner's concurrence isrequired.

ES-301 Administrative TopicsOutline FormES-301-1 Facility:

PeachBottom DateofExamination:6/1/2020 ExaminationLevel:

RO 2 SRO Q Operating TestNumber: 2020NRC AdministrativeTopic (seeNote)

Type Describe activity tobeperformed Code*

G2.1.5 (2.9)

Application ofWorkHourRules Conduct ofOperations N,R (PLOR-391C)

G2.1.31(4.6)

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

G2.2.41 (3.5) isolate the3BRBCCWHeat Equipment Control D,R ExchangerDue toaLeak(PLOR-274C)

Radiation Control NA G2.4.39 (3.9)

- Perform State/Local Emergency Plan D,S Notifications foraDeclared Emergency (PLOR-246C)

NOTE:Allitems(five total) arerequired forSROs.ROapplicants require only four items unless they areretaking only theadministrative topics (which wouldrequire allfive items).

• TypeCodesandCriteria:(C)ontrol room,(S)imulator, orClass(R)oom (D)irect frombank(53forROs;s4forSROsandROretakes)

(N)ew or(M)odified frombank(21)

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

ES-301 Administrative Topics Outline FormES-301-1 Facility:

PeachBottom DateofExamination:6/1/2020 ExaminationLevel:

RO O SRO 2 Operating TestNumber: 2020NRC 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/VentIsolation ValveCumulative Log (PLOR-256C)

G2.4.41 (4.6)

Classification ofEmergenciesand Emergency Plan M,S PARS NOTE:Allitems(five total) arerequired forSROs.ROapplicants require onlyfour items unless they areretaking only theadministrative topics (which wouldrequire all fiveitems).

• TypeCodesandCriteria:(C)ontrol room,(S)imulator, orClass(R)oom (D)irect frombank(53forROs;54forSROsandROretakes)

(N)ew or(M)odified frombank(21)

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

ES-301 Control Room/In-Plant Systems Outline FormES-301-2 Facility:

PeachBottom DateofExamination: 6/1/2020 ExamLevel:

RO 2 SRO-ID SRO-U D Operating TestNumber: 2020NRC Control RoomSystems:* 8forRO,7forSRO-I, and2or3forSRO-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.217000A4.033.4/3.3

- Manually initiate RCIC(Alternate Path)

A,D,S,EN 4

(PLOR-332CA) e.295029 EA1.03 2.9/3.0 LowerTorusWaterLevel IAWAO10.1-2 N,S 5

(PLOR-398C) f.264000 A4.043.7/3.7

- LoadDiesel Generator (Alternate Path A, D, S 6

Differential/Ground)

(PLOR-373CA) g.201006 A3.013.2/3.1

- Initialize theRWM(PLOR-366C) D,S,L 7

h.400000 A4.013.1/3.0

- HPSWInjection into theReactor Vessel in A,D,S 8

accordance withON-124(Alternate Path)

(PLOR-382CA)

In-Plant Systems:*

3forRO,3forSRO-l, and3or2forSRO-U i.295037 EA1.05 3.9/4.0

- Isolate andVenttheScram AirHeader D,E,R 1

Unit3(PLOR-074P) j.264000 K4.07 3.3/3.4

- Diesel Generator AirStart Solenoid D,E 6

Override (PLOR-049P) k.295031 EA1.08 3.8/3.8

- Fire System Injection Into TheRPV D,R 2

(PLOR-104P)

AllROandSRO-lcontrol room(and in-plant) systems mustbedifferent andserve different safety functions, allfive SRO-Usystems mustserve different safety functions, andin-plant systems and functions mayoverlap those tested inthecontrol room.

ES301 Control Room/in-Plant Systems 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 a1/21/21 (EN)gineered safety feature a1/21/21(control roomsystem)

(L)ow-Power/Shutdown 2 1/21/21 (N)ew or(M)odifiedfrom bank including1(A) 2 2/22/21 (P)revious 2exams 53/s3/s2(randomly selected)

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

ES-301 Control Room/In-Plant Systems Outline FormES-301-2 Facility:

PeachBottom DateofExamination:6/1/2020 ExamLevel:

RO D

SRO-I2 SRO-U D Operating TestNumber: 2020NRC Control RoomSystems:* 8forRO,7forSRO-I, and2or3forSRO-U System/JPM Title TypeCode*

Safety Function a.202002 A4.043.8/3.9

- Raise Reactor Powerwith RecirculationA,N,S 1

Flow(Alternate Path)

(PLOR-396CA) b.223002 A4.033.6/3.5

- ResetHPCIIsolation (PLOR-019C)

D,S,EN 2

c.218000 A4.03 4.2/4.2

- ADSReset FollowingBlowdown (PLOR-D,S,EN,L 3

023C) d.217000 A4.03 3.4/3.3

- Manually Initiate RCIC(Alternate Path)

A,D,S,EN 4

(PLOR-332CA) e.295029 EA1.03 2.9/3.0 LowerTorus WaterLevel IAWAO10.1-2 N,S 5

(PLOR-398C) f.264000 A4.043.7/3.7

- LoadDiesel Generator (Alternate Path A, D, S 6

Differential/Ground)

(PLOR-373CA) 9 h.400000 A4.013.1/3.0

- HPSWInjection into theReactor Vessel in A,D,S 8

accordance with ON-124(Alternate Path)

(PLOR-382CA)

In-Plant Systems:*

3forRO,3forSRO-l, and3or2forSRO-U i.295037 EA1.05 3.9/4.0

- Isolate andVenttheScramAirHeader D,E,R 1

Unit3(PLOR-074P) j.

264000K4.073.3/3.4

- Diesel Generator AirStart Solenoid D,E 6

Override (PLOR-049P) k.295031 EA1.08 3.8/3.8

- Fire System Injection Into TheRPV D,R 2

(PLOR-104P)

AllROandSRO-Icontrol room(and in-plant) systems mustbedifferent andserve different safety functions, allfive SRO-Usystems mustserve different safety functions, andin-plant systems and functions mayoverlap those tested inthecontrol room.

ES-301 Control Room/In-Plant Systems 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 1/21/21 (EN)gineered safety feature 2 1/21/21(control roomsystem)

(L)ow-Power/Shutdown 2 1/21/21 (N)ew or(M)odifiedfrom bank including1(A) a2/22/21 (P)revious 2exams s3/s3/s2(randomly selected)

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

Appendix D

Scenario Outline ES-D-1 Simulation FacilityPeachBottomScenario No.#1 OpTestNo. M Examiners Operator CRS(SRO)

URO(ATC)

PRO(BOP)

ScenarioThescenario begins withthereactor atapproximately 3%power during areactor Summary startup.

Following shift

turnover, thePROwill commence Drywell nitrogen inerting using procedure SO7B.1.A-2, "Containment Atmosphere Inerting".

ThePROwill start theStandby GasTreatment System, andthenalign nitrogen gasflow tothe Primary Containment.

TheUROwill continue the startup byraisingreactor powerto> 4%bywithdrawing control rodsinaccordance withthe approved startup sequence until 2mainturbine bypass valves areopenwith reactor pressure at910psig using procedure GP-2-2, "Normal Plant Startup".

Acontrol rodwill becomemispositioned due to aReactor Manual Control System timer

failure, requiring theUROtoexecute ON-122, "Mispositioned Control Rod"to return thecontrol rodtothecorrect target position.

ThePROwill thenrespond toaninadvertent opening of an Automatic Depressurization System(ADS) safety relief valve (SRV). The crewwill respond in accordance with procedure OT-114, "lnadvertent Openingof aRelief Valve".

The PROwill initiate Torus cooling.

ThePROwill besuccessfulin closing thesafety relief valve with its control switch.

Onceclosed, theADSvalvewill remain closed andwill nolonger function.

TheSROwill declare theADSvalve inoperable andwill enter/apply Technical Specifications 3.5.1.E.

Next, thestartup level control valve will experience aloss ofair resulting in the startup level control valve failing full open.

Thevalve failing openwill cause the RPVlevel torise.

Thecrewwill recognize therising RPVwaterlevel andenter procedure OT-110, "Reactor HighLevel".

TheUROwill recognize that placing the failed startup level control valve controller fromAUTOtoMANUALwill notreturn control ofthelevel control valve.

TheUROwill re-establish RPVwaterlevel control byeither throttling theMO-8090"CFeedPumpDishBypass" tocontrol level orclosing theMO-8090 "CFeedPumpDishBypass" andmanipulating the "C"Reactor FeedPump(RFP) discharge valve and"C"RFPspeedtocontrol level.

ThePROwill thenrespond totheinadvertent start ofacorespray subsystem.

The PROwill secure thecorespray system andtheSROwill declare thecorespray subsystem inoperable.

TheSROwill enter/apply Technical Specifications 3.5.1.F.

(This TechSpecwill apply duetothealready INOPADSvalve) 2020NRCScenario

1. 1D-1Rev0

Appendix D

Scenario Outline ES-D-1 Awaterleak will develop intheTorus, resulting inalowering ofTorus waterlevel.

Thecrewwill enter T-102, "Primary Containment Control".

Thecrewwill begin making uptotheTorususing oneofseveral available systems (Condensate Transfer using SO14A.1.A, HighPressure Coolant Injection (HPCI) using T-233, or High PressureService Water(HPSW) using T-231).

The crew willscramthereactor before Torus waterlevel lowers to10.5feet and enterT-101 WhenTorus water levelcannot bemaintained above10.5feet, anEmergency Depressurization, IAW T-112,will bedirected.

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

Thescenario maybeterminated following theEmergency Blowdown.

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

a Reactor Powerisapproximately 3%with direction tocontinue toraise Reactor powerwith control rodwithdrawal usingGP-2-2.

Nitrogen inerting ofthePrimary Containment istobe commenced.

The PROwill begin inerting thePrimary Containment following shiftturnover.

CriticalCritical Task1:Manually Scramthereactor before Toruslevel lowers to10.5 Tasks feet.

Critical Task2:Perform anEmergency Blowdown whenWaterTorus level cannotbemaintained above10.5feetandbefore SRVsareuncovered at7 feet.

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

2020NRCScenario

1. 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 nitrogen inerting.

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 valvefails open/ROcontrols level by CRS manual operation of'C'RFPspeedanddischarge valve.

6 SeeScenario Guide C PRO "A"CoreSpray loopspuriously starts

/PROsecures pumps TS CRS andCRSenters Tech Specs.

7 SeeScenario Guide M ALL Unisolable water leakinthe Torus.

8 SeeScenario Guide C ALL ADSSRVfails toopenonEmergency Blowdown.

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

TechSpec 2020NRCScenario

1. 1D-1Rev0

Appendix D

Scenario Outline ES-D-1 Simulation FacilityPeachBottom Scenario No.#2 OpTestNo.

2020NRC Examiners Operator CRS(SRO)

URO(ATC)

PRO(BOP)

ScenarioThescenario begins with thereactor at100%powerwiththe'B'Electrohydraulic Summary Control (EHC) pump andtheE-332breaker areblocked outofservice for scheduled maintenance.

After taking the

shift, the PROwill start HighPressure Service Water(HPSW)

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

Next, theUROwill withdrawa fully-inserted control rodfollowing scramtiming.

During theevolution, the in-service Control RodDrive (CRD)

Pumpwill experience high ampsrequiring the URO tosecure theCRDPumpandto enter/execute ON-107, "Loss ofCRD Regulating Function".

After placing theCRD flow control valve inMANUAL,theURO will startthestandby CRDPumpand transfer theCRDflowcontro!

valve backto AUTO.

TheUROwill then successfully withdraw thecontrol rodtoposition 48.

Shortly after

this, theE-4Diesel Generator will inadvertently start andoneminute later 005F-1"E-4Diesel GenDifferential andGround" alarm will annunciate.The crewwill takeaction inthealarm response toshutdown the E-4diesel generator andplace inPull-to-Lock.

TheCRSwill apply TechnicalSpecifications foran inoperable Diesel Generator.

Following thediesel generator

event, thePROwill enter andexecute ARC 222 A-5foraloss of125VDCtotheReactor Coreisolation Cooling (RCIC) System.

ThePROwill close MO-2-13-18, "Condensate TankSuction" valve toprevent draining theCondensate Storage Tank(CST) totheTorus.

ThePROwill also recognize that theRCICSteamSupply valve isalsoisolated.

TheCRSwill declare RCICinstrumentation andtheRCICPumpinoperable andwill enter/apply Technical Specifications 3.3.5.2 and3.5.3.

Following theRCICevent, ahighvibration condition forthemainturbine will occur.

TheUROwill lower reactor power withrecirculation flow bylowering recirculation pumpspeedofbothrecirculation

pumps, andbyinserting control rods IAWGP-9-2.

The30RPMDOWNpushbutton for1recirculation pumpwill notfunction andthe ROmustlower speedusing either the5RPMor1RPMdownbutton.

Turbine vibrations will continue

torise, requiring theCrewtoscramthereactor andtrip themainturbine.

AnRPSmalfunction will

occur, resulting inanelectric ATWS,requiring theCrewtoenter/execute T-101 "RPVControl" andT-117 "Level/Power Control."

2020NRCScenario

1. 2D-1Rev0

Appendix D

Scenario Outline ES-D-1 Afailure oftheonlyavailable Electrohydraulic Control (EHC) pumpwill cause the turbinebypass valves

toclose, requiring theCrewtoutilize SRVsforreactor pressure control.

The Crewwill perform T-213 "Scram Solenoid Deenergization

",T-214"Isolating and Venting theScramAirHeader",

andT-220 "Driving Control RodsDuring a

Failure toScram", toinsert control rods.

TheCrewwill also inject SBLCbefore Torus Temperature reaches 1100F.

Thescenario may beterminated whentheCrewhascontrol ofRPVpower and water level using T-240 "Termination andPrevention ofInjection into theRPV" andtheCrewisinserting controlrods.

Initial IC-14, 100%power Conditions Turnover Reactor poweris100%power.

a

'B'Electrohydraulic Control (EHC) pump blockedoutofservice for scheduled maintenance.

a E-332 breaker isblocked 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 moreofthefollowing:

T213"ScramSolenoid Deenergization", T-214 "Isolating andVenting theScramAirHeader",

T-220 "Driving Control Rods During aFailure toScram",and"Initiating Standby Liquid Controlbefore Torustemperature exceeds1100F.

Critical Task#2:Before violating theHeatCapacity Temperature Limit (HCTL)

curve, perform T240"Terminating andPreventing Injection Into the RPV"toprotect Primary Containment until:

Reactor powerisbelow4%or RPVlevel reaches

-172inches orAllSRVsremain closed andDrywell pressure isbelow2psig.

2020NRCScenario

1. 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, "HPSWPump,Valve andFlow CRS Functional Test".

2 SeeScenario Guide C

URO Withdraw asingle control rodandrespond toCRDPumphi CRS amps.

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

CRS TS CRS entersTechSpecs.

4 SeeScenario Guide I PRO Loss ofRCIClogic power.

CRSenters TechSpecs.

TS CRS 5

SeeScenario Guide R URO Main turbine high vibrations require lowering power toaddress CRS thevibrations 6

SeeScenario Guide C URO The30RPMDOWN (recirculation pumpcontrols) pushbutton CRS fails.

7 SeeScenario Guide C ALL Mainturbine high vibrations continue torise requiring turbine 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

1. 2D-1Rev0

Appendix D

Scenario Outline ES-D-1 Simulation FacilityPeachBottom Scenario No.#3 OpTestNo. 2020NRC Examiners Operator CRS(SRO)

URO(ATC)

PRO(BOP)

ScenarioThescenario begins with thereactor at100%power.

Summary Shortly aftertaking theshift thePROwill swapElectrohydraulic Control (EHC)

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

Following thenormal evolution thein-serviceSteamJetAirEjector (SJAE) steam supply will close.

This results inalowering maincondenser vacuum.

TheURO will lower reactor power with recirculation flowIAWOT-106, "Condenser Vacuum Low".

ThePROwill place thestandby SJAEinto service IAWSO8A.6.A-2, "Placing theStandby SJAEinService andPlacingtheInService SJAEin Standby".

NexttheUROwill respond torising vibrations onreactorfeedwater pump"B"The UROwill lower reactor powerif

required, then the UROwill secure thefeedwater pumpIAWSO6D.2.A-2, "Reactor FeedwaterPump Shutdown".

Next, thePROwill respond toaspurious start ofthe High Pressure Coolant Injection (HPCI)

Pump.TheCrewwill enter OT-104, "Positive Reactivity Insertion".

ThePROwill secure thepumpIAWSO23.2.A-2, "HPCI System Shutdown".

TheCRSwill declare HPCIinoperable andenter/apply Technical Specifications 3.5.1.

Thenexteventprovides annunciated indication ofapotential breakin one ofthe corespray spargers.

TheCRSwill declare theinstrumentation inoperable and will enter/apply Technical Resources Manual(TRM) 3.3.

TheUROwill thenrespond toindications oflowoil level onthe"A"recirculation pump,followed byrising bearing temperatures.

TheUROwill secure the"A" recirculation pumpIAWSO2A.2.A-2, "Recirculation PumpShutdown".

A rapidly developing steamleak into thePrimary Containment will thenbegin.

Thecrewwill enter OT-101, "High Drywell Pressure",

butduetotheaggressive steamleak aGP-4will bedirected toScramthereactor.

Directly following

thescram, theScramDischarge Volumevent/drain will fail to

isolate, which will bemanually isolated bytheURO.

ATorus toDrywell vacuumbreaker will fail openduring theScramcausing aloss oftheTorus Pressure Suppression function.

2020NRCScenario

1. 3D-1Rev0

Appendix D

Scenario Outline ES-D-1 Following thescram,thecrewwill enter/execute T-101"RPVControl" andT-102 "PrimaryContainment Control",

TheCrewwill spray theprimary containment usingprocedure T-204"Initiation ofContainment Sprays Using RHR".

The scenario maybeterminated whenthereactor isshutdownwithRPVlevel under control, Primary Containment sprays areinservice, andtheSDVhasbeen manually isolated.

Initial IC-14, 100%power Conditions Turnover a

Unit 2isat100%power.

a "B"RWCUpumpis tagged outofservice.

a Following

turnover, thePRO willbedirected toplace the"B"EHCpump in-service andsecure the "A"

EHC pump.

CriticalCritical Task#1:SpraytheDrywell before thePressure Suppression Limit Tasks curveisexceeded.

Critical Task#2:Manually isolate theScramDischarge Volumefollowing an isolation failure within 30minutes.

2020NRCScenario

1. 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-service SJAE.

R URO CRS 3

SeeScenario Guide C URO Rising vibrationsonfeedwater pump"B" CRS 4

SeeScenario Guide C PRO Spurious startoftheHighPressure Coolant Injection (HPCI)

TS CRS Pump.CRS enters TechSpecs.

5 SeeScenario Guide TS CRS Corespraysparger leak/break detection fails.

CRSenters TechSpecs/TRM.

6 SeeScenario Guide C URO Lossofoil andrisingbearing temperatures on"A" CRS recirculation pump.

7 SeeScenario Guide M ALL SteamleakinPrimary Containment.

8 SeeScenario Guide C URO SDVfails toisolate.

CRS 9

SeeScenario Guide C ALL Torus toDrywell Vacuumbreaker fails open

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

TechSpec 2020NRCScenario

1. 3D-1Rev0

Appendix D

Scenario Outline ES-D-1 Simulation FacilityPeachBottom Scenario No.#4 OpTestNo. 2020NRC Examiners Operator CRS(SRO)

URO(ATC)

PRO(BOP)

ScenarioThescenario begins withthereactor atapproximately 97%power.

Summary After taking the shift, theUROwill withdraw control rod58-31 toposition 48.

Whenverifyingcontrol rodcoupling,thecontrol rodwill over-travel.

TheUROwill enter ON-105, "Control RodUncoupled" andwill re-couple thecontrol rod.

Following thecontrol rod

movement, theUROwill raise reactor power with recirculation flow backto100%

power.

Withthereactor atfull

power, the PRO will thencontinue ininST-O-014-301-2, "Core Spray LoopA Pump,Valve,Flow, andCooler Functional andInservice Test".

Thein-field operator will reportthe "C"pumproomcooler fanwill notstart.

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

Next, aloss ofDCpower tooneoftwo(in series) 'B' RPSMGsetoutput breakers will occur.

Asubsequent operability concern withthe other (in series)

'B'RPSMG setoutput breaker will require theCrewtotransfer the

'B' RPS bustothe alternate powersupply IAWSO60F.6.A-2 "Transferring Reactor Protection System PowerSupplies"

. Theresultant half scramandcontainment isolationswill havetobereset bythePRO,IAWGP-11.E "Reset RPS Scram Reset" andGP 8.D"Group 1,2,3 Outboard Half isolation".

TheCRSwill declare one electric powermonitoring assembly inoperable andwill enter/apply Technical Specifications 3.3.8.2.

Following thetransfer ofRPSBtoalternate, Standby GasTreatment System (SBGT)

Btrain will re-align buttheSBGTFan"B"will notautostart.

ThePRO will start SBGTFan"B".

TheCRSwill declare SBGTFan"B"inoperable and enter/apply Technical Specifications 3.6.4.3.

After theTechnical Specification

entry, rising radiation levels inoffgas andmain steamarenoted, andON-103, "Main SteamLineHighRadiation" isentered.

The UROwill reduce powertoreduce theseradiation levels.

After thereduction inpowertheMainSteamLineRadiation levels continue torise andAlarm218D-1"MainSteamLineHi-Hi Radiation" will bereceived.

TheCRS will direct aGP-4"Manual Reactor Scram".

A steamline break intheTurbine Building will thenoccur.

Thesteamleak gets

worse, asdoestheamountoffuel

failures, requiring theCrewtomanually close theMSIVs.

2020NRCScenario

1. 4D-1Rev1

Appendix D

Scenario Outline ES-D-1 Whenattempting toclose theMSIVs,The"D"mainsteamline will notbeable to beisolated.

TheCrewwill enter T-104"Radioactive Release" toevaluate andcontrol the radiation release.Whentherelease exceeds theGeneral Emergency

level, the Crew willberequired toperform T-112, "Emergency Blowdown" Thescenario will beterminated whentheemergency blowdown isinitiated and RPVlevel is restored abovethetopofactive fuel(-172 inches).

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

Conditions Turnover Reactor powerisapproximately 97%.Reactor powerwaslowered to allow scramvalve repairs on control rod58-31.

Therepairs arecomplete, thecontrol rodhasbeen scram-timed, andisatposition 00.TheUROmay withdraw thecontrol backtoit'starget position of48.

Following thecontrol rod withdrawal, the UROmayraise reactor power backto100%with recirculation flow.

In-plant operators arestanding-by for the URO tocontinue inST-O-014-301-2, "Core Spray LoopA Pump,Valve,

Flow, and CoolerFunctional and Inservice Test".

CriticalCritical Task#1:Whenaprimary systemisdischarging through an Tasks unisolable

leak, scramthereactor prior toperforming anEmergency Blowdown.

Critical Task#2:Perform anEmergency Blowdown whentheradioactive release cannotbemaintained belowtheGeneral Emergency threshold.

2020NRCScenario

1. 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 usingON-105 CRS 2

SeeScenario Guide R

URO Raise reactor powerwithrecirculation flow.

CRS 3

SeeScenario Guide N PRO Start ST-O-014-301-2, "Core Spray LoopAPump,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)

Bfail tostart.

CRS SeeScenario Guide TS CRS enter/apply Technical Specifications.

6 SeeScenario Guide C

URO Lowerreactor power due torising process radiation, CRS followed byamanualscram.

7 SeeScenario Guide M ALL SteamleakintheTurbine Building 8

SeeScenario Guide C ALL Failure ofthe'D'MSLtomanually isolate.

9 SeeScenario Guide M ALL Fueldamagewithrelease tothe environment requires Emergency Depressurization.

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

TechSpec 2020NRCScenario

1. 4D-1Rev1

ES401 BWRExamination Outline FORMES-401-1 Facility Name:Peach Bottom DateofExam:6/1/2020 ROK/ACategory Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G,

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 TierTotals 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 SystemsTierTotals 4

3 3 3 4 4 4

3 4 3 3 38 5

3 8

1 2

3 4

1 2

3 4

3.Generic Knowledge andAbilities Categones 2

3 3

2 1

2 2

2 Note:1.

Ensure that atleast twotopics fromevery applicable K/Acategory aresampled within eachtier oftheROandSRO only outlines (i.e.,

except foronecategory inTier 3ofthe SRO-only outline, the"Tier Totals" ineachK/Acategory shall notbelessthantwo).

(One Tier3Radiation Control K/Ais allowed iftheK/Aisreplaced byaK/Afrom another Tier 3Category).

2.

Thepoint total foreachgroup andtier intheproposed outline mustmatch that specified inthetable.

Thefinal point total foreachgroup andtier maydeviate by11fromthat specifiedin the table based onNRCrevisions.

The final ROexammusttotal 75points andtheSRO-only exammusttotal 25points.

3.

Systems/evolutions within eachgroup areidentified ontheassociated outline;systems orevolutionsthat donot apply atthefacility should bedeleted andjustified; operationally important, site-specific systems that arenot included ontheoutline should beadded.

Refer toSection D.1.b ofES-401 for guidance regarding theelimination ofinappropriate K/Astatements.

4.

Select topics fromasmanysystems andevolutions aspossible; sample every systemorevolution inthegroup before selecting asecond topic foranysystem orevolution.

5.

Absent aplant-specific

priority, only those K/Ashaving animportance rating (IR) of2.5orhighershall beselected.

UsetheROandSROratings fortheROandSRO-only

portions, respectively.

6.

Select SROtopics forTiers 1and2fromtheshaded systems andK/Acategories.

7.*

Thegeneric (G)

K/AsinTiers 1and2shall beselected fromSection 2oftheK/ACatalog, butthetopicsmust be relevant totheapplicable evolution orsystem.

Refer toSection D.1.b ofES-401 fortheapplicable K/As.

8.

Onthefollowing

pages, enter theK/Anumbers, abrief description ofeachtopic, thetopics' importance ratings (IRs) fortheapplicable license

level, andthepoint totals

(#)

foreachsystem andcategory.

Enter thegroup and tier totals foreachcategory inthetable above;iffuel handling equipment issampled inother thanCategory A2or G*ontheSRO-only exam,enteritontheleft sideofColumnA2forTier 2,Group2(Note

1. 1doesnotapply).

Use duplicate pagesforROandSRO-only exams.

9.

ForTier 3,select topics fromSection 2oftheK/Acatalog, andenter theK/Anumbers, descriptions,

IRs, andpoint totals

(#)

onFormES-401-3.

Limit SROselections toK/Asthat arelinked to10CFR55.43.

G*

Generic K/As

ES401 2

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

- Tier1/Group 1(RO)

E/APE#/Name

/SafetyFunction K

K K

A

"/fp K/ATopic(s)

IR 1

2 3

1 f

/

295001 Partial orComplete LossofForced 0

VgKnowledge ofthereasons forthefollowing responses astheyapply toPartial or 2.9 1

CoreFlowCirculation

/1& 4 6

T Complete LossofForced CoreFlowCirculation:

Coreflow indication 0

Knowledge oftheoperational implications ofthefollowing concepts astheyapply to 295003 PW a CWW W of E /6 3

4 5

g Partial orComplete LossofAC:Failsafe component design 0

, Ability tooperate and/or monitor thefollowing astheyapply toPartial orTotal Lossof 295004 Partial orTotal LossofDCPwr/ 6 3 @/

DCPwr:

A.C.electrical distribution p

j "r

0 Ability tooperate and/or monitor thefollowing astheyapply toMainTurbine Generatorg 3

295005 MainTurbine Generator Trip

/3 2

S Trip:

RPS a

295006 SCRAM/1

/@,Knowledge oftheinterrelations between SCRAMandthefollowing:

Reactor power 4.2 1

Ability todetermine and/or interpret thefollowing astheyapply toControl Room 295016 Control RoomAbandonment

/7 3.9 1

Abandonment:

Suppression pool temperature 295018 Partial orTotal LossofCCW/8 Ability todetermine and/or interpret thefollowing asthey apply toPartial orTotal Loss n 3

of CCW: Causeforpartial orcomplete loss A

295019 Partial orTotal Lossofinst.

Air/8 Ability to determine and rnterpret thefonowing asthey apply toPartial orTotal Loss 3.5 1

o 0

295021 LossofShutdown Cooling

/4 p /

Knowledge ofthe operational implicationsofthefollowing concepts astheyapply to 3.6 1

4 LossofShutdownCooling:

Naturalcirculation 4,

0 Knowledge oftheinterrelations between Refueling Accidents andthefollowing:

295023Refueling Acc/8

.A/

RMCS/Rod control andinformation system y

4 4

295024 HighDrywell Pressure

/5 0 / b Ability tooperate and/or monitor the following astheyapply toHighDrywell Pressure:p 3

1 HPCI(FWCI):

Plant-Specific A./

295025 HighReactor Pressure

/3 Ability torecognize abnormal indications for system operating parametersthat are 3

3 entry-level conditions foremergency andabnormaloperating procedures.

W./

Ability tointerpret control roomindications toverify thestatus and operation ofa 295026 Suppression PoolHighWater

system, andunderstand howoperator actions anddirectivesaffect plantandsystem 4.2 1

Temp./5 conditions.

295027 HighContainment Temperature

/5 0

0 Ability tooperate and/or monitor thefollowing asthey apply toHighDrywell 295028HighDrywell Temperature

/5 f Temperature:

Drywell pressure 3.9 1

4 295030 LowSuppression PoolWtrLvI/5

//4 Know!edge oftheinterrelations between LowSuppression Pool WtrLvlandthe 3.5 1

0 7

g following:

Downcomer/

honzontal ventsubmergence 295031Reactor LowWaterLevel

/2

/

Ability tolocate andoperate components, including local controls.

4,4 1

295037SCRAMCondition Presentand

't Reactor Power AboveAPRMDownscale or 4/

Ability toevaluate plant performance andmakeoperational judgments based on q

4

'//

operating characteristics, reactor

behavior, andinstrument interpretation.

Unknown/1

/

0 A4Knowledge oftheoperational implications ofthefollowing concepts astheyapply to 295038 HighOff-site Release Rate/9 p

HighOff-site Release Rate:

Meteorological effects onoff-site release 3

3 3

0 600000 Plant Fire OnSite

/8 Knowledge ofthereasons forthefollowing responses astheyapply toPlant Fire On 3

3 4

. Site:

Actions contained intheabnormal procedure forplant fire onsite 700000 Generator Voltage andElectric Grid 0

/

Knowledge ofthereasons forthefollowing responses astheyapply toGenerator

/

Voltage andElectric Grid Disturbances:

Actions contained inabnormal operating 36 1

Disturbances

/6 2

f procedure forvoltage andgrid disturbances

^

K/ACategory Totals:

3 3

3 4

A Group Point Total:

20 A

ES-401, Page34of50

ES-401 3

FormES-4011 ES-401 BWRExamination Outline FormES-401-1 Emergency andAbnormal Plant Evolutions

- Tier1/Group 2(RO)

E/APE#/Name /Safety Function 4

K/ATopic(s)

IR 1

2 3

1 p //

'y 295002 LossofMain Condenser Vac/3 "f

3.7 1

0e

@,f

/ Pressure:

Reactor/turbine pressure regulating system operationKnowledge ofthereasons forthefollowing responses asthey apply toHighReactor 295007 HighReactor Pressure

/3 x

/ /

295008 HighReactor WaterLevel

/2

/

0

///

> f/

295009 LowReactor WaterLevel

/2

/

0 295010 HighDrywell Pressure

/5 0

295011 HighContainment Temp/5 0

295012 HighDrywell Temperature

/5 0

295013 HighSuppression Pool Temp./5

(

Knowledge of the operational implications ofthefollowing concepts asthey apply to p9 3

0 4

/ High Suppression Pool Temp.:Complete condensation

//*i 295014 Inadvertent Reactivity Addition

/1 0

0 295015Incomplete SCRAM/1 Knowle geoftheinterrelationsbetween incomplete SCRAMandthefollowing:

CRD p

q 1

295017 HighOff-site Release Rate/9 Ability tooperate and/or monitor thefollowing as theyapply toHighOff-site Release 2.5 1

2 /J Rate:

Meteorological data w

295020 inadvertent Cont.

isolation

/5&7 0

//

Knowledge oftheparameters andlogic usedtoassess the status of safety functions, 295022 LossofCRDPumps/1 4

suchasreactivity

control, corecooling andheatremoval, reactor coolant system 4.0 1

integrity, containment conditions, radioactivity release

control, etc.

295029 HighSuppression Pool WtrLvI/5

!/

295032 HighSecondary Containment Area

1. Rg Ability todetermine and/or interpret thefollowing astheyapply toHighSecondary 3

Temperature

/5 A, Containment AreaTemperature:

Equipment operability 4

295033 HighSecondary Containment Area 0

Radiation Levels

/9 295034 Secondary Containment Ventilation

@ /

HighRadiation

/9 J

0 295035 Secondary Containment High

" 4 Differential Pressure

/5 0

295036 Secondary Containment High

/'d g

Sump/Area WaterLevel

/5 g //

1. '/V 0

500000 HighCTMTHydrogen Conc.

/5 Knowledge ofthereasons forthefollowing responses astheyapply toHighCTMT y

3 4

gHydrogen Conc.:

Emergency depressurization K/ACategory Totals:

1 1

2 1 $',/

~ GroupPoint Total:

7

%//

ES-401, Page35of50

ES-401 4

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

- Tier 2/Group 1(RO)

K K K K K K A #

A A System

1. /Name 1 2 3 4 5 6 1 3 4 />

K/ATopic(s)

IR e

g g Ability tomonitor automatic operations oftheRHR/LPCl:

Injection Mode gj 203000 RHR/LPCl: Injection Mode includng@eMnhn muemAMWnanuaHyophnnhondor 4 3 2

8 2 inthecontrol room:

System valves 0

/d &cKnowledge oftheeffect that aloss ormalfunction oftheShutdown Cooling win 205000 Shutdown Cooling p

4

/ haveonfollowing:

Recirculation looptemperatures 0

Knowledge ofthephysical connections and/or cause-effect relationships 206000 HPCI 4g j

2 A between HPCIandthefollowing:

Reactor waterlevel:

BWR-2,3,4 207000 Isolation (Emergency)

Condenser pp

///

0 209001 LPCS V,

thmepredans, useprocedures tocorrect,

control, ormitigate the 3.2 1

consequences ofthose abnormal conditions oroperations:

Inadequate system

• 1. 4 J

209002 HPCS 0

WJ 211000 SLC rg

@Knowledge oftheoperational implications ofthefollowing concepts astheyapplyy 4

0 3

F9 "9 toSLC:Shutdown margin 1,

Knowledge oftheeffect that aloss ormalfunction oftheRPSwill haveon 3.8 g

212000 RPS

/

'4following:Reactor power(thermal heatflux);

Knowledge ofEOPmitigation 2

7 3.7 strategies.

0 Ability topredict and/or monitor changes inparamete rsassociated with N003 M y

3 6

, operating theIRMcontrols including:

Lights andalarms 215004 Source RangeMonitor g

0 0

0 Knowledge ofelectrical powersupplies tothefollowing:

APRMchannels" 2g.' 2 215005 APRM/LPRM Knowledge oftheoperational implications ofthefollowing concepts astheyapply 2

1 2.8 toAPRM/LPRM:

LPRM detector operation 0

Knowledge ofthephysicalconnections and/or cause-effect relationships y 3

217000 RCIC 4

f V/ between RCICandthe following:

Main condenser 0

@Knowledge oftheoperational implications ofthefollowingconcepts astheyapplyy 218000 ADS 1

A toADS:ADSlogic operation 223002 PCIS/Nuclear SteamSupply 1 0

between PCIS/Nuclear SteamSupply Shutoff and the following: Standby gas 3.1; 2 Shutoff 2

2 j treatment system; Ability tomonitor automatic operations ofthe PCIS/Nuclear 3.5

'/

0 239002 SRVs KnowledgnMhuffecMhat alosonnaWunchon oMhefodowing wiHhaven 3.0 1

5 g

theSRVs:Discharge line vacuum breaker 259002 Reactor WaterLevel Control

/

operating theReactor WaterLevel Control controls including:

FWRV/startup 2.9; 0

0 2

5 #a,,4 y

level control position:

Plant-Specific; Ability tomonitor automatic operations of 3.2 0

Knowledge ofSGTSdesign feature(s) and/or interlocks which provide forthe 261000SGTS p

1 following:

Automatic system initiation g

Ability topredict and/or monitor changes inparameters associated with 262001 ACElectrical Distribution operating theACElectrical Distribution controls including:

Effects ofloads when 3.1 1

2

.. energizing abus F

Ability to(a) predict theimpacts ofthefollowing ontheUPS(AC/DC);

and(b) 262002 UPS(AC/DC) d

//

basedonthosepredictions, useprocedures tocorrect,

control, ormitigate the 2.5 1

consequences ofthose abnormal conditions oroperations:

Overvoltage 263000 DCElectrical Distribution provide forthefollowing:

Breaker interlocks, permissives, bypasses andcross 31; 0

2 2

1. ties:

Plant-Specific; Knowledge ofthedesign, procedural, andoperational 3.8

/

0 Ability tomanually operate and/or monitor inthecontrol room:

Transfer of 264000 EDGs p

j 3

emergency control between manual andautomatic xg 300000 Instrument Air y4 Knowledge oftheeffect that alossormalfunction ofthefollowing will haveon 0

2.5 1

7 y

theInstrument Air:

Valves 00000 Component Cooling Water Knowledge ofelectrical power supplies tothefollowing:

CCWpumps 2.9 1

K/ACategory Totals:

3 2 2 2 3 2 3@

3 2fg GroupPoint Total:

26 ES-401, Page36of50

ES-401-1 5

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

- Tier2/Group 2(RO)

System

1. / Name

"^ A A y";

K K K K K K A K/ATOpic(s)

IR 1

2 3

4 5

6 1

3 3 4

M 201001CRDHydraulic re P

O 01002RMCS 0

01003Control RodandDrive Mechanism

1. 1. interlocks which provide forthefollowing:

Limiting control rodspeedintheevent 2.9 1

01004RSCS "Ji,j 0

201005RCIS 0

0 201006RWM y,/j Knowledge oftheeffect that aloss ormalfunction ofthefollowing will haveonthe p7 3

4 gg

//#,

RWM:Process computer:

P-Spec(Not-BWR6) 02001Recirculation Knowledge ofthephysical connections and/or cause-effect relationships betweenp 3

0 7

'/fff Recrculation andthefollowing:

Component cooHng watersystems 202002 Recirculation FlowControl O

04000RWCU W

O 214000RPIS O

'//

w 15001Traversing In-core Probe O

215002 RBM

, those predictions, useprocedures tocorrect,

control, ormitigate the 3.0 1

16000Nuclear Boiler Inst.

Relationship betweenmeter/recorder readings andactual parameter values: 3.4 1

19000RHR/LPCI:

Torus/Pool Cooling 0

,,/v ljV/

p (fg, Knowledge of electrical power supplies tothefollowing:

Valves 2.5 1

223001Primary CTMTandAux.

O z

5'//

O 26001RHR/LPCl:

CTMTSpray Mode 30000RHR/LPCl:

Torus/Pool Spray Mode 0

33000FuelPoolCooling/Cleanup

~'

"4'Ability tomanually operate and/or monitor inthecontrolroom:

Tanklevels 2.5 1

34000FuelHandling Equipment 't(

O 39001MainandReheat Steam

'~^. Ability torecognize system parameters that are entry-level conditions for 3.9 1

Technical specifications.

239003 MSlVLeakage Control 0

41000Reactor/Turbine Pressure Regulator 0

245000 MainTurbine Gen./Aux.

0 O

fg'/

Knowledge oftheoperational implications ofthefollowing concepts asthey apply 3

3 56000Reactor Condensate 3

f 7ffe toReactor Condensate:

Heatexchanger level operation 59001Reactor Feedwater 7/

m a

0 268000Radwaste Knowledge oftheeffect that aloss ormalfunction oftheRadwaste will haveon p7 3

4 4'Afollowing:

Drain sumps 1 " "'

271000 Offgas Ability topredict and/or monitor changes inparameters associated withoperatingp 3

4

/f theOffgas controls including:

Oxygengasconcentration y

f Knowledge oftheeffect thataloss ormalfunction ofthefollowing will haveonthe 30 1

O 72000Radiation Monitoring 1

/b 9 Radiation Monitoring:

Reactor protection system 286000Fire Protection bd' O

88000Plant Ventilation

//

O 90001Secondary CTMT 0

90003Control RoomHVAC 0

90002Reactor Vessel internals fj 0

7 (o/

ray/

/

W/A K/ACategory Totals:

1 1

1 1 1 2 1

, J 1 1

~ GroupPoint Total:

12 ES-401, Page37of50

^

ES-401 2

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

- Tier 1/Group 1(SRO)

E/APE#/Name

/SafetyFunction K/ATopic(s)

IR 295001 Partial orComplete LossofForced g #'f6 0

CoreFlow Circulation

/1& 4 295003 Partial orComplete Loss of AC/6 fpfA r#A L/

295004 Paiiial orTotal LossofDCPwr/ 6

' "'Knowledge ofannunciator

alarms, indications, orresponse procedures.4.1 1

295005 MainTurbine Generator Trip

/3 0

Ability todetermine and/or interpret thefollowing astheyapply to 295006 SCRAM/1 4.2 1

/ /SCRAM:Reactor waterlevel g 7 295016 Control RoomAbandonment

/7 0

Ability todetermineand/or interpret thefollowing astheyapply toPartial 295018 Partial orTotal LossofCCW/8 2.9 1

or Total LossofCCW:System pressure 295019 Partial orTotal LossofInst.

Air/8 0

295021 LossofShutdown Cooling

/4 0

A

/

295023 Refueling Acc/8 0

v ##

295024 HighDrywell Pressure

/5 Knowledge ofabnormal condition procedures.

4.2 1

295025 HighReactor Pressure

/3 A

0 295026 Suppression PoolHighWater fg@

g Temp./5 W

295027 HighContainment Temperature l5

~

0 295028HighDrywell Temperature

/5 Ability toexplain andapply systemlimits andprecautions.

4.0 1

Knowledge oftheprocess formanaging maintenance activities during 295030 LowSuppression PoolWtrLvI/5 shutdown operations, suchasrisk assessments, workprioritization, etc.

Ability todetermine and/or interpret thefollowing astheyapply toReactor 295031Reactor LowWaterLevel

/2 4.8 1

LowWaterLevel:

Adequate corecooling 295037 SCRAMCondition Present

5 andReactor PowerAboveAPRM 0

Downscale orUnknown

/1 295038 HighOff-site Release Rate/9 0

600000 Plant Fire OnSite

/8 0

700000 Generator Voltage andElectric Grid

'/ g g

Disturbances

/6 K fg K/ACategory Totals:

0 0

0 0 y GroupPoint Total:

7 ES-401, Page34of50

ES401 3

FormES401-1 ES-401 BWRExamination Outline FormES-401-1 Emergency andAbnormal Plant Evolutions

- Tier1/Group 2(SRO)

K K

K A <

1 2

3 1 #(

o K/ATopic(s)

IR E/APE#/Name /Safety Function 295002 LossofMain Condenser Vac/3 0

295007 HighReactor Pressure

/3 0

295008 HighReactor WaterLevel

/2 0

A 295009 LowReactor WaterLevel

/2 A7 0

295010 HighDrywell Pressure

/5 A

0

/##u 295011 HighContainment Temp/5

~

Ability todiagnose andrecognize trends inanaccurate andtimely manner utilizingq 4

295012HighDrywell Temperature

/5 the appropriate control roomreference material.

295013 HighSuppression PoolTemp./5 0

/A 295014 Inadvertent Reactivity Addition

/1

• f O

295015 Incomplete SCRAM/1 f

0 295017 HighOff-site Release Rate/9

/

0 n

295020 Inadvertent Cont.

Isolation

/5&7 Ability todetermine and/or interpret thefollowing asthey apply toInadvertent Cont.

3.9 1

isolation:

Reactor pressure 295022 LossofCRDPumps/1 x

0 295029 HighSuppression PoolWtrLvl/5

,f

)

a 295032HighS condary Containment Area A

g 295033HighSecondary Containment Area g//;ff')

g Radiation Levels

/9

'c /'/

295034 Secondary Containment Ventilation

,g, HighRadiation

/9 0

Y Ability todetermine and/or interpret thefollowing astheyapply toSecondary 295035 Secondary Containment High Differential Pressure

/5

,#f Con nmentHighDifferential Pressure:

Secondary containment pressure:

Plant-3.9 1

295036Secondary Containment High 0

Sump/Area WaterLevel

/5 vp 500000 HighCTMTHydrogen Conc.

/5 Y

0 K/ACategory Totals:

0 0

0 0

GroupPoint Total:

3 ES-401, Page35of50

ES401 4

FormES-4011 ES-401 BWRExamination Outline FormES-401-1 Plant Systems

- Tier2/Group 1(SRO)

K K K K K K A(

' A A /

K/ATopic(s)

IR 1 2 3 4 5 6 1by3 4 4, System

1. /Name 203000 RHR/LPCl: Injection 0

/'

205000 Shutdown CoolingMode

/

0

//

206000 HPCI Ability tointerpret andexecute procedure steps.

4.6 1

207000 isolation (Emergency) g Condenser dV/

/#,g Ability toprioritize andinterpret thesignificance ofeachannunciator oralarm. 4.3 1

209001LPCS d'A 209002 HPCS 0

A 211000 SLC 0

212000 RPS A

0

'/

215003 IRM 215004 Source RangeMonitor N

4$$

0

/#

'"16 215005 APRM/LPRM 0

3 217000 RCIC

/

0

'7/

/

218000 ADS those predictions, useprocedures tocorrect, control,ormitigate the 3.6 1

aj consequences ofthose abnormal conditions oroperations:

Lossofairsupply to 223002PCIS/Nuclear SteamSupply fj g

Shutoff d

/

239002 SRVs 4

0

1. 2 259002 Reactor WaterLevel Control

@ /

0 b

3'//

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

,f consequences ofthoseabnormal conditions oroperations:

Fantrips 262001 ACElectrical Distribution 0

ff y

262002 UPS(AC/DC)

Tg 0

263000 DCElectrical Distribution 0

///' *4' Ability to(a) predict theimpacts ofthefollowing ontheEDGs;and(b) based on 264000 EDGs f/

those predictions, useprocedures tocorrect,

control, ormitigate the 4.1 1

A consequences ofthose abnormal conditions oroperations:

LossofA.C.power 300000 instrument Air 0

00000Component Cooling Water 7////

0 f

K/ACategory Totals:

0 0 0 0 0 0 0 d 0 0 //'GroupPoint Total:

5 z

'or's ES-401, Page36of50

ES401 5

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

- Tier 2/Group 2(SRO)

K K

K K

K K A T.4A A

System

1. / Name 1

2 3

4 5 6 1 @3 4

K/ATopic(s)

IR 01001CRDHydraulic a

O 01002RMCS

1. 2 01003Control RodandDrive Mechanism

~.

O 01004RSCS 2

0 01005RCIS 7

0 Wad 0

01006RWM 02001Recirculation O

02002Recirculation FlowControl

'p 0

04000RWCU O

214000RPiS 0

n 215001Traversing In-core Probe yf Knowledgeofabnormal condition procedures.

4.2 1

215002 RBM d

0 A

FAff 16000Nuclear Boiler Inst.

0 19000RHR/LPCl:

Torus/Pool Cooling fgg Mode V2 O

23001Primary CTMTandAux.

0 f,g 26001RHR/LPCI:

CTMTSpray Mode Mode;and(b) based on those predictions, useprocedures tocorrect,

control, or 2.6 1

30000RHR/LPCl:

Torus/Pool Spray Mode "f da 0

233000FuelPoolCooling/Cleanup

~'

0 34000FuelHandling Equipment

/

1. , p o

,a me 39001MainandReheat Steam O

39003MSIVLeakage Control 0

"a 241000Reactor/Turbine Pressure Regulator up 0

45000MainTurbine Gen./Aux.

g O

56000Reactor Condensate 0

59001Reactor Feedwater 0

68000Radwaste O

71000Offgas 0

72000Radiation Monitoring O

86000Fire Protection f,/

0 88000Plant Ventilation basedonthose predictions, useprocedures tocorrect,

control, ormitigate the 3.7 1

90001Secondary CTMT

'#/

0 90003Control RoomHVAC 0

90002Reactor Vessel internals 0

/

K/ACategory Totals:

0 O 0 O 0 0 0 6,;

0 0,g,4GroupPoint Total:

3 ES-401, Page37of50

Facility Name:Peach Bottom DateofExam:6/1/2020 n

Category K/A#

Topic IR IR p

Knowledge ofprocedures, guidelines, orlimitations associated withreactivity j

management.

2.1.

2.1. 08 Abilitytocoordinate personnel activities outside thecontrol room.

3.4 1

4.1 3

Conduct of2.1.01Knowledge ofconduct ofoperations requirements.

3.8 1

4.2 Operations 2.1.

2.1 Subtotal 2

1 2.2.

21Knowledge ofpre-andpost-maintenance operability requirements.

2.9 4.1 1

22 % Ability toanalyze theeffect ofmaintenance activities, suchasdegraded powersources, 31 42 1

onthestatus oflimiting conditions for operations.

2.2.

2.

2.2.22Knowledge oflimiting conditions foroperations andsafety limits.

4.0 j

4.7 Control 22 WAbility tomanipulate theconsole controls asrequired tooperatethe facility between 43 j

4 j shutdown anddesignated powerlevels 2.2.13Knowledge oftagging andclearance procedures.

4.1 1

4.3 Subtotal 3

2 23 M Ability touseradiation monitoring

systems, suchasfixed radiation monitors andalarms, 29 29 1

portable survey instruments, personnel monitonng equipment, etc.

2.3.11Ability tocontrol radiation releases 3.8 4.3 1

2.3.

3 Radiation 2.3.07Ability tocomply withradiation workpermit requirements during normal orabnormal p

ggl conditions.

Knowledge ofradiological safety procedures pertaining tolicensed operator

duties, such 2.3.13asresponse toradiation monitor

alarms, containment entry requirements, fuel handling 3.4 1

3.8 resonsibilities accesstolocked hih-radiation areasallninfilters etc.

23 15Knowledge ofradiation monitoring

systems, suchasfixed radiation monitors andalarms, 29 1

31 portable survey instruments, personnel monitoring equipment, etc.

Subtotal 3

2 2.4.44Knowledge ofemergency planprotective action recommendations.

4.4 j

2.4.08Knowledge ofhowabnormal operating procedures areusedinconjunction withEOPs.

3.8 4.5 1

4.

2.4.

Emergency Procedures 2.4.18Knowledge ofthespecific basesforEOPs 3.3 1

4.0

/Plan y

Knowledge oflocal auxiliary operator tasks during anemergency andtheresultant j

operational effects.

2.4.

Subtotal 2

2 Tier 3Point Total 10 7

ES-401, Page43of50

ES-401 Record ofRejected K/As FormES-401-4 Tier

/

Rejected K/A ReasonforRejection Grou RO Question 13 Unable towrite aquestion forselected K/A.Peach Bottom hasWideRangeNeutron Monitor (WRNM)

System.

This Tier 2/

215003 Intermediate Range iscomparable totheIRMsystem inmostways, however Monitor ORM)

Systena Group1 mostoftheWRNMsystem isautomatic.

This includes A1.05

- Abilityto predict and/or auto-ranging forthetrip androdblock setpoints.

Since the monitor changes in parameters systemisautomatic, there isnotsufficient operator associated with operating the manipulations ontheWRNMtodevelop aquestion.

Intermediate Range Monitor (IRM)

Randomly resampled K/A215003

- Intermediate Range System controls including:SCRAM Monitor(IRM)

System androdblock trip setpoints Al.06

- Ability topredict and/or monitor changes in parameters associated withoperating theIntermediate Range Monitor (IRM)

System controls including:

Lights and alarms RO Question 64 Unable to develop 3creditable distractors astheauxiliary operatortasks during aloss ofCRDpumpsislimited to Tier 1/

295022

- LossofCRDpumps performingchecks andmanipulate onevalve during a

Group 2

2.4.35

- Knowledge oflocal auxiliary standby pump start, orbypassthesuction strainer ifthat is operator tasks during emergency and clogged.

theresultant operational effects. Randomly resampledK/A 295022

- LossofCRDpumps 2.4.21

- Knowledge oftheparameters andlogic used to assess thestatus ofsafety functions, suchasreactivity

control, corecooling andheat

removal, reactor coolant systemintegrity, containment conditions, radioactivity release

control, etc.

SRO Question 79 Unable todevelop aquestion forselected System andK/A combination asthere arenoROtasks performed outside Tier 1/

295028

- HighDrywell Temperature themaincontrol roomduring aHighDrywell Temperature Group1 2.4.34

- Knowledge ofROtasks event.

performed outside themaincontrolRandomly resampled K/A295028

- HighDrywell roomduring anemergency andthe Temperature resultant operational effects.

2.1.32

- ability toexplain andapply system limits and precautions.

SRO Question 81 Unable towrite anSROonlylevel question based onK/A astheability tolocate

switches, controls andindications to Tier 1/

295030

- LowSuppression Pool determine plant lineup isaROjob.

WaterLevel Group 1

Randomly resampled K/A295030

- LowSuppression Pool 2.1.31

- Ability tolocate control WaterLevel roomswitches,

controls, and indications, andtodetermine that 2.2.18

- knowledge oftheprocess formanaging they correctly reflect thedesired plantmaintenance activities during shutdown operations, such as lineup.

risk assessments, workprioritization, etc.

ES-401 RecordofRejected K/As FormES-401-4 SRO Question 84 System overlap withTier1-Group 2ROquestion number 63(295032).

Thiswould bethesecond time system Tier1/

295032

- HighSecondary 295032 hadbeenselected ontheSROexamandIAWES-Containment AreaTemperature 401,all systems inagroup mustbeselected before double 2.4.20 Knowledge oftheoperation selecting asystem inagroup.

implications of EOP warnings, Randomly resampled Tier 1-Group 2SROsystem

cautions, andnotes (295032) andK/A 295012

- HighDrywell Temperature 2.4.47

- Ability todiagnose andrecognize trends inan accurate andtimely mannerutilizing theappropriate control roomreference material.

SRO Question 86 System overlapwithTier2-Group 1ROquestion numbers 3and 24(215005). Thiswouldbethethird time system Tier 2/

215005

- APRM/LPRM 215005 had beenselected ontheSROexam.IAWES-401 Group 1

A2.06

- Ability to(a) predict the all systems inagroupmustbeselected oncebefore double impacts ofthefollowing onthe selectingasystem.

Although notexplicitly stated inES-APRM/LPRM;and(b) based on 401wecarrythis logic forwardinthat all systems ina those predictions, useprocedures to group mustbedouble selected before being selected athird

correct, control, ormitigate the t1me.

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

(215005) andK/A Recirculation flowchannels upscale 264000

- Emergency Generators (Diesel/Jet)

A2.09

- Ability to(a) predict the impacts ofthe following ontheEmergency Generators (Diesel/Jet);

and (b) based onthose predictions, useprocedures tocorrect,

control, or mitigate theconsequences ofthose abnormalconditions or operations:

LossofA.C.power SRO Question 87 System overlap with Tier 2-Group 1ROquestion numbers 5and21(212000).

Thiswould bethethird time system Tier2/

212000

- Reactor Protection System212000 hadbeenselected ontheSROexam.IAWES-401 Group1 A2.01

- Ability to(a) predict the all systems inagroup mustbeselected oncebefore double impacts ofthefollowing onthe selecting asystem.

Although notexplicitly stated inES-Reactor Protection System; and(b) 401wecarry 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-GroupISROsystem abnormal conditions oroperations:

(212000) andK/A RPSmotor-generator setfailure 218000

- Automatic Depressurization System A2.03

- Ability to(a) predict theimpacts ofthefollowing ontheAutomatic Depressurization System; and(b) based onthose predictions, useprocedures tocorrect,

control, or mitigate theconsequences ofthose abnormal conditions or operations:

Lossofairsupply toADSvalves

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

206000

- HighPressure Coolant isalso ROnecessary knowledge.

Injection Group1 Randomly resampled K/A206000

- HighPressure Coolant 2.1.28

- Knowledge ofthepurpose andfunctionof major system 2.1.20

- Ability tointerpret andexecute procedure steps components andjcontrols.

SRO Question 89 Unable towrite aquestion fortheselected System andK/A combinationasthere arenolocal auxiliary operator tasks Tier 2/

209001

- LowPressure Core Spray associatedwithCoreSpray during anemergency.

System Group1 Randomly resampled K/A209001

- LowPressure Core 2.4.35

- Knowledge oflocal auxiliary Spray System operator tasks during emergency and theresultant operational effects. 2.4.45

- Abilitytoprioritize andinterpret thesignificance ofeach annunciator oralarm Randomselection wasusing anonline randomnumber generator.

www.random.org