ML21076A063

From kanterella
Jump to navigation Jump to search

Final Written Examination and Operating Test Outlines (Folder 3)
ML21076A063
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 03/09/2021
From:
Public Service Enterprise Group
To: Todd Fish
Operations Branch I
Shared Package
ML19353E011 List:
References
EPID L-2021-OLL-0001
Download: ML21076A063 (34)
v • d • e


Text

.

ES-301 Topics Administrative Outline FormES-301-1 Facility: M Date ofExamination: 2/22/21 Examination Level: RO 2 SRO D Operating Test Number: 1 Administrative Topic (see Note) Type Describe activitytobeperformed Code*

Perform a Reactor Recirculation PumpQuick Restart Conduct ofOperations TaskStandard: Operator completes Step G.12 ofHC.OP-AB.RPV-0003 for restart ofReactor D,S Recirculation Pump KA 2.1.18 Ability tomakeaccurate, clear, andconcise logs, records, status boards, and reports.

Perform Steps 5.1 through 5.6.3 ofHC.OP-ST.SH-0001 Conduct ofOperations Task Standard: Operator performs Steps 5.1 through 5.6.3 ofHC.OP-ST.SH-0001(Q) and D,S notifies CRS and/or systemengineering ofany vanance KA 2.1.45 Abilityto identify andinterpret diverse indications tovalidate theresponseof another indication.

ISOLATE ANDDRAINCRDPP "A" toperform the a pumpinternal inspection.Using Equipment Control controlled station drawings (provided):

1.IDENTIFY theMechanical components that arerequired tobetagged, andtheir required N,R positions.

2.IDENTIFY theElectrical component(s) that is/are required tobetagged, andrequired position.

KA 2.2.41 AbilitytoObtain andInterpret Station Electrical & Mechanical Drawin s Determine Liquid Radwaste RadMonitor CTB Weir Flow Radiation Control Task Standard: completes theDay Operator Shift reading for HC.OP-DL.zz-0026, D Attachment 1a,ITEM47,for theRMSCooling Tower Blowdown Weir Flow Rate Monitor and identifies anyvariance.

KA 2.3.11 Ability tocontrol radiation releases.

ES301 Administrative Topics Outline FormES-301-1 EmergencyPlan N/A NOTE:All items total) are required for (five SROs.ROapplicants require only four items they unless areretaking only the administrative topics would (which require all items).

five TypeCodes andCriteria:(C)ontrol room,(S)imulator, orClass(R)oom (5

(D)irect from bank 3for SROsandRO ROs;5 4 for retakes)

(N)ewor (M)odified from bank (21)

(P)revious 2 exams (51,randomlyselected)

ES-301 Administrative Topics Outline FormES-301-1 Facility: M Date ofExamination: 2/22/21 Examination Level: RO O SRO 2 Operating Test Number: 1 ..

Administrative Topic (seeNote) Type Describe activity tobeperformed Code*

PERFORM theShift Manager review ofthe OP-AA-105-102, Attachment 2,foranSROlicense Conduct ofOperations renewal for the Control RoomSupervisor M,R position Task Standard: Determines license reactivation requirements have not been met(and why) in accordance with OP-AA-105-102.

KA 2.1.5 Ability touseprocedures related to shift staffing, such asminimum crew com lement, overtime limitations,etc.

Complete DailySurveillance log Conduct ofOperations Task Standard: Operator implements thelog at the beginning of theday bycompleting Attachment 1, Section A,ofHC.OP-DL.zz-0026 P,R andidentifies attachments requiredIAWthe answer key KA 2.1.18 Abilitytomake accurate, clear, andconcise, logs, records, status boards and reorts Review andapprove WorkClearance Documents (WCDs). Youhave been presented Equipment Control with the WCDfor Independent Review and Pre-N,R Approval inaccordance withOP-AA-109-115, CRDPP"A" Safety Tagging Operations for TaskStandard: Identify discrepancies IAW answer key KA-2.2.41 -

Ability toObtain andInterpret Station Electrical & Mechanical Drawin s PERFORM step 5.1.11 ofHC.OP-GP.zz-0004 todetermine theleakage intotheCore Spray Radiation Control Loop A Injection Header. Determine any D,R required actions andRECORD thembelow Task Standard: Operator completes the -

CRS/SM review ofa completed HC.OP-GP.zz-0004 andnotes actions required.

KA 2.3.11 Ability tocontrol radiation releases.

ES-301 Administrative Topics Outline FormES-301-1 Utilize TheECGTo~ Determine TheEmergency ClassificationAnd/Or ReportabilityOfAnEvent EmergencyPlan And/Or PlantCondition '

D,R TaskStandard: Operatorappropriate declaration inaccordancewith answer key; initiatesa PAR;andmakesnotifications within identifiedCritical Times inaccordance with EP-HC-111-101.

KA2.4.38 -

Ability totake actions for called in the facility emergency plan, including Isupporting oractingasemergency coordinator if reuired.

NOTE:AII items(five total) for SROs. ROapplicants arerequired require four only items unless they areretaking only the topics (which would administrative require five all items).

TypeCodes andCriteria:(C)ontrol room, (S)imulator, orClass(R)oom (D)irect from bank (5 3 for ROs; s4 for SROsandROretakes)

(N)ewor(M)odified frombank (2 1)

(P)revious2 exams (51,randomly selected)

ES-301 Control Room/In-Plant Systems Outline FormES-301-2 Facility: M Date ofExamination: 2/22/21 Exam Level: RO 2 SRO-1 D SRO-U O OperatingTest Number: 1 Control Room Systems:* 8for RO,7for SRO-l,and2 or3for SRO-U System/JPM Title TypeCode* Safety Function a.Respond toRising Drywell Pressure S,D,A,L 5 b.Place HPCIinfull flow Test Operation S,P,A,EN,L 4 c.Place RCICinservice from the RSP S,D,EN 2 d.Perform Non-Emergency Operation oftheEDG S,D 6 e.SwapRACspumps S,N,A 8 f.Enabling Automatic Backup Stability Protection foranAPRM IAW S,N 7 HC.OP-SE-0001 Step 4.10 g.Resetting RPSTrips S,P,A 1 h.SwapControl RoomVent trains IAWHC.OP-SO.GK-0001 S,D 9 In-Plant Systems:* 3for RO,3 for SRO-I, SRO-U and3 or2 for

i. Transfer RPSBusA/BPower from Source Alternate toRPSMGSet D,A 7 D,R 1

", Shift in-service CRDflow control valves D,E 3 k.Resondtoa Failed O enSRV AII ROandSRO-I control room(and in-plant) systemsmustbedifferent andserve safety different functions,all fiveSRO-Usystems mustserve safety different andin-plant functions, and systems functions mayoverlap those testedinthecontrol room.

  • R /SRO-l/SRO-U Type Codes Criteria for (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect frombank s9/s 8/s 4

(E)mergency orabnormal 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)odified from bank including1(A) 2/21 2 2/2 (P)revious 2 exams s3/s3/s2 (randomly selected)

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

ES-301 Control Room/In-Plant Systems Outline FormES301-2 Facility: M Date ofExamiriation: 2/22/21 Exam Level: RO D SRO-I 2 SRO-U D Operating Test Number: 1 Control 8for RO,7 for SRO-I, and2 or3forSRO-U Room Systems:*

System/JPM Title TypeCode* Safety Function a.Respond toRising Drywell Pressure S,D,A,L 5 b.Place HPCIinfull flow Test Operation S,D,A,EN 4 c.Place RCICinservice from the RSP S,D,EN 2 d.Perform Non-Emergency Operation oftheEDG S,D 6 e.SwapRACspumps S,N,A 8 f.Enabling Automatic Backup Stability Protection foranAPRM IAW S,N 7 HC.OP-SE-0001 Step 4.10 g.Resetting RPSTrips S,P,A 1 In-Plant Systems:* 3for RO,3for SRO-I, and3or2for SRO-U D,A. 7

i. Transfer RPSBusA/BPower from Alternate SourcetoRPSMGSet D,R =

1 Shift in-serviceCRDflow control valves D,E 3 k.Resondtoa Failed O enSRV

  • ROandSRO-I room(and AII control in-plant) systems mustbedifferent andserve safety different all functions, fiveSRO-Usystems mustserve safety different andin-plant functions, and systems functionsmayoverlap those testedinthecontrol room.

TypeCodes Criteria forR/SRO-I/SRO-U (A)lternatepath 4-6/4-6

/2-3 (C)ontrol room (D)irect frombank s9/s8/54 (E)mergency orabnormal in-plant 2 1/2 1/21 (EN)gineered safety feature 2 1/2 1/21 (control room system)

(L)ow-Power/Shutdown a1/21/21 (N)ew or(M)odified from bank including1(A) 2/21 2 2/2 (P)revious 2 exams 5 3/s 3/s2 (randomlyselected)

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

ES-301 Simulator Scenario Quality Checklist FormES-301-4 QUALITATIVE ATTRIBUTES Initials ..

a b* c" . .

1. Theinitial conditions are realistic in that someequipment and/or instrumentation maybeout ofservice, butid toes cuethe operators into expected g not events.
2. Thescenarios consist mostly of related events. 5f V V
3. Eachevent description consists of thefollowing:
  • thepoint inthe scenario when it istobeinitiated a themalfunction(s) orconditionsthat areentered toinitiate the event thesymptoms/cues that will bevisible tothecrew a

a a

the the expected event operator termination actions point (if (by shift position) applicable) y?

(

4. Theevents are valid with regard to physics andthermodynamics. f & '
5. Sequencing andtiming ofevents is reasonable andallows theexamination teamtoobtain complete evaluation results commensurate with thescenario objectives. 8-
6. If time compression techniques areused, the scenario summary clearly soindicates.

Operators Cuesare have given.

sufficienttime tocdrry out expected activities without undue time constraints.

r b b(

7. Thesimulator modeling isnot altered. Sf f
8. Thescenarios have been validated. Pursuant to10CFR55.46(d), anyopen simulator performance deficiencies fidelity ordeviations ismaintained while from the running referenced theplanned plant have scenarios.

been evaluated toensure that functional 5'p y g

9. Scenarios areneworsignificantly modified inaccordance with Section D.5ofES-301. 6 #

1.0.AIIindividual operator competencies canbeevaluated, asverified using FormES-301-6 (submit the formalongwith the simulator scenarios). q, 4 11.Thescenario set provides the opportunity for each applicant tobeevaluated ineach ofthe applicable rating factors. (Competency ratingfactors asdescribed onForms ES-303-1and ES-303-3.) d (f 12.Eachapplicant willbesignificantly involved intheminimum number oftransients andevents specified ...

onFormES-301-5 (submit the form with the simulator scenarios). 2 13.Applicantsareevaluated onasimilar number ofpreidentified critical tasks across scenarios, when - -

possible. Sp V l 14.Thelevel ofdifficulty isappropriateto support licensing decisions for eachcrew position. of b TargetQuantitative Attributes perScenario (See Section D.5.d) Actual Attributes - - -

1. Malfunctions after EOPentry (1-2) 2 /2 / 3 d @
2. Abnormal events (2-4) 3 /2 / 3 ff d
3. Majortransients (1-2) 1 /1 /1 y d
4. EOPsentered/requiring substantive actions (1-2) 2 /2 / 3 >

(>

IV V f

5. Entryintoacontingency EOPwith substantive actions 1perscenario 2 /1 / 1 set) (
6. Preidentified criticaltasks (2 2) 2 /2 / 3 JO Thefacility licensee signature isnot applicable for NRC-developed tests.
  1. Anindependent NRCreviewer initials items incolumn "c"; chief examiner concurrence isrequired.

i

ES-301 Transient andEvent Checklist FormES-301-5 A E Scenarios 1 2 3 4 T M L N CREW CREWPOSITION CREWPOSITION CREWPOSITION O I I T POSITION T C S A B S A B S A B S A B A y A T R T O R T O R T O R T O L U p O C P O C P O C P O C P M(*)

E R I U RX 1 2 1 3 1 1 O NOR 1 1 1 1 1 SRO-I 1/C 2-5, 4,5 2,3,5, 13 4 4 2

  1. 1 7,8 6,7 MAJ 6 6 4 3 2 2 1 TS 2,3,4 1,2,3 6 0 2 2 RX 1 2 2 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2,5 3,4,5, 1,3,6 10 4' 4 2
  1. 2 7,8 MAJ 6 6 4 3 2 2 1 TS 1,3,4 3 O 2 2 RX 1 2 1 3 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2-5, 4,5 2,3,5, 13 4 4 2
  1. 3 7,8 6,7 MAJ 6 6 4 3 2 2 1 TS 2,3,4 1,2,3 6 0 2 2 RX .

1 2 . .

2 1 1.0 NOR 1 1 1 1 1 SRO-I I/C 2,5 3,4,5, 1,3,6 10 4 4 2

  1. 4 7,8 MAJ 6 6 4 3 2 2 1 TS 1,3,4 3 0 2 2 Instructions:
1. Checktheapplicant levelandentertheoperating number test andFormES-D-1 event numbersforeach event TS type; arenotapplicableforROapplicants. ROsmust inboth serve theat-the-controls(ATC) (BOP) andbalance-of-plant positions. SROs(SRO-I)

Instant must serve inboth theSROandthe ATCpositions, including atleast twoinstrument or component (I/C) malfunctionsandonemajor inthe transient, ATCposition. anSRO-1 If additionally servesintheBOP oneI/C position, malfunctioncanbecredited toward thetwo1/C malfunctionsrequiredfor ATCposition.

the

2. manipulations Reactivity maybeconducted under normalorcontrolledabnormalconditions(refertoSect D.5.d) but mustbesignificant additional I/C per SectionC.2.aofAppendix ona one-for-one malfunctions basis.

(*)

D. Reactivity andnormal evolutionsmaybereplaced with

3. Whenever practical, both instrument andcomponent malfunctions shouldbeincluded; onlythosethatrequire verifiable actions that provideinsight totheapplicant'scompetence count theminimum toward requirements for specified the license applicant's levelintheright-hand columns.
4. Fornewreactor licensees facility thatusethe ATCoperator primarily formonitoring plant parameters,thechief mayplace examiner SRO-I ineither applicants theATCorBOPposition tobest evaluatetheSRO-I inmanipulating controls.

plant

ES301 Transient andEvent Checklist FormES-301-5 A E Scenarios Pp 1 2 3 4 T O

M I

L N CREW CREW CREWPOSITIONCREWPOSITION I T POSITION POSITION T C S A B S A B S A B S A B A y A T R T O R T O R T O R T O L U p O C P O C P O C P O C P M(*)

E R I U RX 1 2 2 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2-5, 4,5 8 4 4 2

  1. 5 7,8 MAJ 6 6 2 2 2 1 TS 2,3,4 3 0 2 2 RX 1 2 2 1 1 O NOR 1 1 1 1 1 I/C 2,5 3,4, 7 4 4 2 SRO-I 5,7,
  1. 6 8 MAJ 6 6 2 2 2 1 TS 1,3, 3 0 2 2 4

RX 1 1 1 1 0 NOR 1 1 1 1 1 RO#1 1/C 2,3,7 4,5,7 2,5,7 11 4 4 2

,8 ,8 MAJ 6 6 4 3 2 2 1 TS . . - 0 0 2 2 RX 1 1 1 1 0 NOR 1 1 1 1 1 RO#2 I/C 3,7 5,7 2,5,7 11 4 4 2 MAJ 6 6 4 3 2 2 1 TS 0 0 2 2

ES-301 Transient andEvent Checklist FormES'-301-5 Instructions:

1. Check the applicant levelandenter the operating number test andFormES-D-1 numbers event for eacheventtype; TS arenot applicable for ROapplicants. ROsmust serve inboth (ATC) theat-the-controls (BOP) andbalance-of-plant positions. Instant SROs(SRO-l) mustserve inboththeSROandthe ATCpositions, including atleast twoinstrument or component (I/C) malfunctions andonemajor inthe transient, ATCposition. anSRO-I If intheBOP serves additionally position, one I/C malfunction canbecredited toward thetwoI/Cmalfunctions for requiredtheATCposition.
2. Reactivity manipulations maybeconducted under orcontrolled normal conditions abnormal (refer D.5.d) toSection but mustbesignificantper Section C.2.a ofAppendix D.(*) andnormal Reactivity maybereplaced evolutions with additional I/C malfunctions onaone-for-one basis.
3. Whenever practical, bothinstrument andcomponent malfunctions shouldbeincluded; those only that verifiable require actions that provide insight to the applicant's competencecounttowardtheminimum for specified requirements the applicant's license level intheright-hand columns.
4. Fornewreactor facilitylicensees that use theATCoperator for primarily plant monitoring the parameters,chiefexaminer may lace SRO-I applicants ineither the ATC orBOP ositiontobestevaluate the SRO-Iinmanipulating plant controls.

ES-301 Competencies Checklist FormES3016 Facility: HOPECREEK Date ofExam: 2/22/21 Operating Test:

1:

APPLICANTS RO-1 @ RO-2 @ RO Q RO Q SRO-I Q SRO-I Q SRO-I-1 @ SRO-I-2@

SRO-U D SRO-U Q SRO-U Q SRO-U D Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/Diagnose Events2,y,7 1,4,,5,,6 1,g3,4 2,y,7 1,2y3,4 1,4,,5,,6 gy 1,g4,5 AII 1,2,5,6All 1,3,4,6 andConditions Comply with and AII AII All All AII All All AII All All AII All UseProcedures 1 Operate Control 2,3,e,71,4,5,e

,8, ,7,8 ,7 1,2,3,4 2,3,s,7

,8, 1,4,5,e

,7,8 1,2,3,4

,7 1,2,4,5

,6 1,2,5

'6 l'3,4,6 Boards 2 Communicate All All AII AII All All All All All All AII All andInteract Demonstrate .

Supervisory AH AH AH Abili3 Comply with and 2,3,4 1,2,3 1,3,4 UseTS 3 Notes:

(1) Includes TScompliancefor anRO.

(2) Optional foranSRO-U.

(3) Only applicable toSROs.

Instructions:

Check the license applicants' type andenter oneormoreevent numbers thatwill allow the examiners toevaluate everyapplicable competency for every applicant. (This all includes rating factors eachcompetency.)

for (Forms ES-303-1 and ES-303-3 describe the competency rating factors.)

ES-301 Competencies Checklist FormES-3016 Facility: HOPECREEK Date ofExam: 2/15/21 Operating TestNo.1 APPLICANTS RO C RO C RO O RO C SRO-I-3 @ SRO-I-4@ SRO-I-5@ SRO-I-6 @

SRO-U O SRO-U C SRO-U C SRO-U C Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Interpret/DiagnoseEvents AH 1f An 1,2e,5 All 1,3,4,6 AII ,

4 1,2g,5 gig andConditions Comply with and An An AH AH AH AH AH AH AH AH UseProcedures 1 Operate Control 1,jf 1,245 1,3,4,e 1,gg 1,245 Boards 2 Communicate AH AH AH AH AH AH AH AH AH AH andInteract Demonstrate Supervisory AH AH AH AU AH Abili3 Comply with and 2,3,4 1,2,3 1,3,4 2,3,4 1,3,4 UseTS 3 Notes:

(1) Includes TScompliance foranRO.

(2) Optional foranSRO-U.

(3) Onlyapplicable toSROs.

Instructions:

Check theapplicants' license typeandenter oneormoreevent numbers will that allow the examiners toevaluate every applicable competency for everyapplicant.(This includes all rating factors foreachcompetency.) (Forms ES-303-1 and ES-303-3 describe the competency rating factors.)

Appendix D ScenarioOutline FormES-D-1 Facility: Scenario No.: 1 Op-Test No.: 1 Examiners: Operators:

Initial Conditions:=79% power. B RFPTin Recirc Turnover:

Critical Tasks:

3 g p RaisePowerwith Recirculation Pumps 2 PC07A C Ea@uake M TripofSSWPump(TS) 3 QQ09 C MSLRMS A Fails Channel upscale (TS) 4 RM01A I Une&eakin%well Inskument 5 RR31A1 I AM 6 RP06 M IAuo InWaknfaHure 7 HP06E C 8 CU11B C AuplnWahn FaHure (N)ormal, (1)nstrument, (R)eactivity, (C)omponent, (M)ajor

Appendix D Scenario Outline FormES-D-1 Critical Tasks Scenario#1 1.

  • CREWprevents anuncontrolled depressurization during ATWSconditions by preventing ADS ACTUATION, ORif actuated, closes ADSvalves before Reactor Pressure drops below 550psig.

K/A218000 AutomaticDepressurization System A4Ability tomanually operate and/or monitor inthecontrol room:

A4.04 ADSinhibit RO4.1 SRO 4.1 Given thecurrentATWSconditions ofthis scenario, preventing ADSautomatic operation and uncontrolle potential reactor levelfloodupprevents asignificant transient andsubsequent positive reactivity addition tothe EOPs reactor.

directthisactionunder the current conditions. This critical task isonly applicable RPVwater if level goesbelow -

129". Failuretosatisfactorily complete the taskisdemonstrated byanautomatic ACTUATION ofADSsuchthat the ADSSRVsopen andreduce reactorpressure toless than550psig.

2.

s CREWmaintains orrestores adequate core cooling byrestoring/maintaining Compensated Reactor water level to>185" IAWHC.OPEO.zz0101A without Emergency Depressurizing.

K/A295037 SCRAMCondition Present andReactor Power Above APRM DownscaleorUnknown EA2Ability todetermine and/or interpret thefollowing asthey apply toSCRAM Condition PresentandReactor Power Above APRMDownscale orUnknown:

EA2.02 Reactor water level RO4.1 SRO4.2 Maintaining adequate Core cooling under ATWSconditions isaccomplished bymaintaining/restoring level above -185". HPCIandRCICare capable ofmaintaining level underthe current conditions. AB.22-0001provides directionsonmanual initiation ofHPCIwhich will mitigate the automaticinitiation failure.AnEmergency Depressurization is notwarranted andwould resultinalarge injectionofcold water andthe displacement potential of boron from thecore.

Appendix D Scenario Outline FormES-D-1 Facility: E Scenario No.: 2 Op-TestNo.: 1 Examiners: Operators:

Initial Conditions: 100% Power Turnover: RPSMG Set1BG401 has anoisybearing. Transfer RPSBusB Power to itsAlternate Supplyinaccordancewith HC.OP-SO.SB-0001.

CriticalTasks:

Event Malf. Event Event No. No. Type* Description 1 N/A N Transfer

'B'RPStoAlternate Power Supply (TS) 2 N/A R Reduce Powerto95%

3 Rz02A C RRCSPressure Transmitter Failure (TS) 4 CU11A C RWCULeak w/Failure toAutomatically Isolate (TS) 5 TCO2-2 C HighReactorPressure 6 RR31A2 M LOCA 7 PCO4 C Downcomer Failure

8. PC03E I A/CChannel Initiation Failures (N)ormal, (R)eactivity,(1)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline FormES-D-1 Critical TasksScenario #2 1.Crew initiates isolation ofRWCU(e.g., closure ofRWCUHVF001ORHV-F004)

BEFORE differential flow exceeds 65gpm.

K/A223002Primary Containment Isolation System /Nuclear SteamSupply Shut-Off A4Ability tooperate and/or monitor intheControl Room A4.01 Valve Closures RO 3.6 SRO3.5 -

A4.06 Confirm initiation tocompletion RO3.6 SRO3.7 TheRWCUSystem hasfailed toisolate automatically. Failureofthe Crewtomanually isolatethe system will result inabypass oftheReactor Coolant and Primary Containment boundaries and release ofradioactive materials tothe Reactor Building.

2.Crewmaintains Suppression Chamber Pressure below theAction Required region of thePSPcurve.

K/A295024 High Drywell Pressure EA1Ability tooperate and/or monitor the following asthey applytoHIGH DRYWELLPRESSURE:

EA1.11 Drywell Spray RO 4.2 SRO4.2 EA2Ability todetermine and/or interpret thefollowing asthey toHIGHDRYWELLPRESSURE:

apply EA2.04 Suppression chamber pressure RO3.9 SRO3.9 K/A223001 Primary Containment Systems andAuxiliaries A2.Ability AUXILIARIES; (a) to predict and(b) theimpacts based onthose ofthefollowing predictions, onthePRIMARY CONTAINMENT useprocedures tocorrect, control, SYSTEMAND ormitigate the consequences of those abnormal conditions ofoperations:

A2.02 Steam bypass ofthesuppressions pool RO3.9 SRO4.1 Ifsuppression chamber pressure cannot bemaintained below thepressure suppression pressure, EOPsdirect actions to emergency depressurize the reactor. A LOCAcondition whileintheaction required region ofthe Pressure Suppression Pressure curve, could cause design containment limitstobe exceeded. Based upon the rate ofpressure increase inthis scenario,the Crew has over tenminutes toinitiate DrywellSprays and prevent entry into theAction Required region ofthe PSPcurve. This will prevent anunnecessary Emergency Depressurization, which isa significant challenge tothe Suppression Pool andwould causethe Cooldown Limit for the Reactor Coolant system to beunnecessarily exceeded. Reducing reactor pressure withinthecooldown limit may also delay/prevent entryinto the action required region.

Appendix D Scenario Outline FormES-D-1 Facility: Scenario No.: 3 Op-Test No. 1 Examiners: Operators:

Initial Conditions:

Turnover:

Critical Tasks:

1 FW12B R,C 2 SL03A C na en ysmAdua@n M 3 ED11A I ssd mm M 4 EG12 M ssasRe her DG03B Auto Start ofEDGs Failure 5 DG04B C 6 RCO1 C RCICTriponOverspeed SACSPumpTrip 7 QQ15 C

  • (C)omponent,.

(M)ajor (N)ormal, (R)eactivity, (1)nstrument,

Appendix D Scenario Outline FormESD-1 Critical TasksScenario #3 1.Crew restores/maintains APRMPower to<100%within fiveminutesofthe Core Thermal Power5Minute Average exceeding 3910 MWth.

K/A295001 Reactor Feedwater System A2Ability to(a)predict the impacts ofthefollowing onthe ReactorFeedwater System; and(b) basedon those predictions, use procedures tocorrect, control,ormitigate theconsequences ofthose abnormal conditions ofoperations:

A2.04 Loss ofExtraction Steam RO3.3 SRO3.4 K/A2.2 Equipment Control 2.2.22 Knowledge oflimiting conditions for operations andsafety RO.3.4 limits SRO4.1 Theloss ofFeedwater heating due tothe trip of the FWHwill drive power reactor toabove the licensedlimit.

Peak power inthis transient with nooperato ractionis just over102%power. This would constitute aviolationofour Operating License. HC.OP-IO.22-0006 defines a5 minute averageof3904 MWthduring steady operations state as exceeding the Licensed Power Limit. Taking the Immediate Operator ActionsIAWeither AB.BOP-0001 or AB.RPV-0001 will prevent this violation.

2.CREWstarts SACSPumpB toprovide cooling toEDGB,ORcross-connects toSACSLoop A,toprevent anEDGB emergency trip fromcooling related problems.

K/A295003 AA1.03 Systems necessary toassure safe plant shutdown RO 4.4 SRO4.4 Thecontinued availability ofEDGB isrequired tomaintain the capabilityto place the plantinacold shutdown condition. IfEDGB becomes inoperable: EDGA currentlyinoperable), both (with loopsof shutdown cooling will beinoperable andivill:prevent placing andmaintainingthe plant ina cold shutdown condition; and the inability tocool the Suppression Pooltomaintaintemperatures less than 212F.Starting ofthis pump, orcross-connecting toSACSLoopA is duetothe required failure ofSACS Pump D.

This Critical Task isvalid only ifEDGB has.been started.

3.BEFORE Compensated RPVwater level lowers below -185": Crewdetermines entry into EOP-202is required andinitiates actions toEmergency Depressurize thereactor. Thenrestores RPVwater levelto above -185".

K/A295031 Reactor LowWaterLevel EA1.Ability tooperate and/or monitor thefollowing asthey apply toREACTORLOWWATER LEVEL:

EA1.01 LowPressure Coolant Injection RO:4.4 SRO4.4 EA1.06 Automatic depressurization system RO4.4 SRO4.4 EA2Ability todetermine and/or interpret thefollowing astheyapply toREACTORLOWWATER LEVEL:

EA2.04 Adequate core cooling RO4.6 SRO4.8 WhenReactor water levelcannot bemaintained above -185" withinjection tothe RPV,adequate corecooling cannot beassured (MSCRWL). EOPsdirect action toinitiate emergencydepressurization whenRPVwater level reaches this value if there are injection sources available. Torestoreadequatecore cooling, the Crewmust Emergency Depressurize and restores level with lowpressure ECCS.

ES-401 Written Examination Outline FormES-401-1 Facility: HC21-2 Date ofExam: 02/21 . .' -

ROK/ACategory Points SRO-Only Points Tier GroupK K K K K K A A A A G 1 2 3 4 5 6 1 2 3 4

  • Total A2 G* Total 1 3 5 3

, xw ~

agewas 4 4 filWeA 1 20 4 3 7 1.Emergency A dd waAamm t

& 2 1 2 0 jdf@EE 1 2 Agjjjj1!!f jAjj!jjjjj$

1 7 2 1 3 Plant M .. ..

.. TC .:::::

Evolutions Tier 4 7 3 b 5 6 W as 2 27 6 4 10 Totals j@gjjjjo 1 2 2 2 3 2 2 2 2 3 4 2 26 2 3 5 2.

Plant 2 1 1 2 1 1 1 1 1 1 1 1 12 0 1 2 3 Systems .

Totals 3 3 4 4 3 3 3 3 4 5 3 38 3 5 8 3.Generic Knowledge & Abilities 1 2 3 4 10 1 2 3 4 7

Categories 2 3 3 2 2 2 1 2 Note' Ensure 1' SRO-onlythatatleast twotopics from every applicable K/A category are sampled within each tier ofthe ROand outline sections (i.e.,

except foronecategory inTier3oftheSRO-only section, the "Tier Totals" in eachK/Acategory shall notbeless than two). (One Tier 3 radiation control K/Aisallowed ifii tsreplaced bya K/Afromanother Tier3 category.) . .

2. Thepoint total foreachgroup andtier inthe proposed outline must match that specified inthe table. Thefinal point for total each group andtier maydeviate by11from that specified in the table based onNRCrevisions.

ROexammust Thefinal total 75points, andtheSRO-only exammust total 25points. -

3. Systems/evolutions within each group areidentified onthe outline. Systems orevolutions that donot applyat thefacility should bedeleted with justification. Operationally important, site-specific systems/evolutions thatare notincludedonthe outline should beadded. Refer toSection D.1.b ofES-401 for guidance regarding the ofinappropriate elimination K/Astatements.
4. Select topicsfrom asmanysystems andevolutions aspossible. Sample every system or evolution inthe groupbeforeselecting a second topic foranysystem orevolution.
5. Absent a plant-specific priority, only those K/As having animportance rating (IR) of2.5orhigher. Use theRO andSROratings theROandSROonly for portions, respectively. . .
6. Select SROtopics forTiers 1and2from the shaded systems andK/Acategories.
7. Thegeneric (G) K/As inTiers 1and2shall beselected from Section 2 oftheK/Acatalog, but the topicsmust berelevanttothe applicable evolution orsystem. Refer toSection D.1.b ofES-401 for theapplicable K/As.
8. Onthefollowing pages, enter the K/Anumbers, a brief description ofeach topic, the topics' IRs for the license applicable level,andthe point totals (#) for each system andcategory. Enter the group andtier for totals eachcategory inthe table above. If fuel-handling equipment issampled ina category other than Category A2or G*onthe SRO-only exam, enter itontheleft side ofColumn A2for Tier 2,Group 2.(Note 1does notapply.)

Useduplicate pages for ROandSRO-only exams.

9. ForTier3,select topics from Section 2 ofthe K/Acatalog, andenter theK/Anumbers, descriptions, IRs,and totals point (#) onFormES-401-3. LimitSROselections toK/As that arelinked to10CFR55.43.

G* . These systems/evolutions mustbeincluded aspart ofthe (as sample applicable tothe facility) when Generic Revision3 ofthe K/Acatalog isused todevelop the sample plan. Theyarenotrequired tobeincluded when K/As usingearlier revisions ofthe K/Acatalog.

Thesesystems/evolutions oftheK/Acatalog isused maybeeliminated todevelop the sample from the plan.

sample applicable (as tothe facility) whenRevision 3

ES-401 2 FormES-401-1 HC21-2 Written Examination Outline EmergencyandAbnormal Plant Evolutions -

Tier 1Group 1 EAPE#/ Name Safety K1 K2 K3 A1 A2 G K/ATopic(s). Imp Q#

Function mW .wee EA2.01Ability the following todetermine asthey apply to and/or interpret 295026SuppressionPool WaterTemp. /5 High

@ A$@hTEMPERATURE: SUPPRESSION POOLHIGHWATER Suppression pool water 4.2 76 temperature Aljjjjl$ AA2.03Ability-todetermine and/or 295016ControlRoom gjjjjjjjjjljjjjj$ interpret the following asthey apply to 44 77 Abandonment /7 me!!!!!l!!!' CONTROL

[i!!!l5l!!!!jii!!lili: ROOMABANDONMENT  :

Reactor ressure itli$@jidjj EA2.07 -

Ability todetermine and/or interpret

$50% WN

. I I I I I I I I III I I 295037SCRAM Conditions the following asthey apply toSCRAM andReactor Present Power apXA .

CONDITION PRESENT ANDREACTOR 4.2 78 AboveAPRMDownscale or Ap ""

POWER ABOVEAPRMDOWNSCALE OR Unknown /1 jAEA UNKNOWN
Containment NdEil conditions/isolations 295021Loss ofShutdown jjjjjjjjjjjgjjjjjjjjjj 2.2.40Equipment Control: Ability toapply 4.7 79 Coolina/4 ==!!!!!!!l!ij?ilii?l?l!!l==21 Technical Specifications for as stem.

295001Partial orComplete Loss 2.4.50 -

Emergency Procedures /Plan: Ability alarm setpoints andoperate 4.0 80 ofForcedCore FlowCirculation pmet7sy!C to verify system

/l# e as w:m:% controls identified inthe alarm response

$3%) MM manual.

E@d!l@ih 2.4.4 -

Emergency Procedure/Plan: Ability to 295018Partial orTotalLoss of  ! recognhabnonnd inhons fonynent CCW/8 C *## !P operatmg parameters that are entry level 4.7 81

@bgg WAA meW!Wii conditions o erating for emergency rocedures andabnormal 600000PlantFire /8 On-site ll@!

WXA

!D!!! AA2.03 the following Ability todetermine andinterpret asthey apply toPLANT FIRE 3.2 82

!!h@$@iM ONSITE: Fire alarm EK1.01 -

Knowledge ofthe operational 5

295024High Drywell Pressure/ X bb!!Migg s32 kW apply implications toHIGHDRYWELL ofthe following concepts PRESSURE asthey 41

' 39 MF@M Drywell integrity: PlantS ecific EK1.03Knowledge-ofthe operational 295037SCRAM Conditions A AjPC implications ofthe following concepts asthey and Present ReactorPower X as!!!s!!!!!!!!!!  !;!;!s!!s!;!xit apply toSCRAMCONDITION PRESENT C #

Above APRMDownscale or Wl!!l!!!!!!l!!Ak! ANDREACTOR POWER ABOVEAPRM Unknown /1 $@$$@@$

lidij!EW!!!!siillit!!!!!!!!!ili!!?

DOWNSCALE effects onreactor ORUNKNOWN:

owerSBLC)

Boron gaGllEAlEK1.03Knowledge -

ofthe operational 295030LowSuppressionPool X AfA ! e implications ofthe following concepts asthey 3 8 41 WaterLevel/5 M + apply  : toLOWSUPPRESSION POOL WATERLEVEL: Heat caaci odjl! !iie!%A EK2.06 -

Knowledge ofthe interrelations 295038High Off-site Release ilijf!!jjiMWAA!A between HIGHOFF-SITE RELEASE RATE X x===

radiation3.4 42 Rate/9 @g m-"

jjjjpgg andthe monitoring following:

s stem Process liquid mjpijillfl3

..=.

AK2.02Knowledge ofthe interrelations 295003 orComplete Partial X between PARTIAL ORCOMPLETE LOSS 43 LossofAC/6 pii!WGiE OFA.C. POWER andthe following: 41 '

P2lW@!$5 Emergency generators J%!!ji!!f!l!!llljij!!!!!ll!iti AK2.03Knowledge-ofthe interrelations 600000PlantFireOn-site

/8 X  !$!@!)i!!!$!!!$!ll!j[ between PLANTFIREONSITE andthe 2.5 44 WiPll!ljEEi$l?l?il followin :Motors WW AK3.02 -

Knowledge ofthe reasons forthe 295004Partial orTotal Loss of X /# !A!;!!!!!5!d j[ following PARTIALORCOMPLETE responses asthey apply to LOSSOFD.C. 2.9 45 DCPwr/6 WTA 4!Ai;j? POWER :Ground isolation/fault

j^..

ES-401 2 FormES-401-1 HC21-2 Written Examination Outline Emergency andAbnormal Plant Evolutions -

Tier 1Group1 EAPE# /Name Safety Imp Function K1 K2 K3 A1 A2 G K/ATopic(s)

Q#

lifib!!!!!jl)!jjl?!j AK3.03Knowledge-ofthereasons for 295001 Partial orComplete ATW)BlitijAilt the following responses asthey apply to LossofForcedCoreFlow X EWW A PARTIAL ORCOMPLETE LOSSOF 2.8 46

/1& 4 Circulation GMlWiW FORCED COREFLOWCIRCULATION  :

WiWlNlA Idle looflow ec ,4 AK3.02Knowledge-ofthe reasons for iids the M GENERATOR following responses VOLTAGE asthey AND apply to 700000 Electric Grid Voltage Generator Disturbances and X E0 W ELECTRIC Actions GRIDDISTURBANCES: 3.6 47 contained inabnormal operating iiiilikhis ld!lAiAillJ procedure for voltage andgrid "li@ disturbances.

fiifl!!iililiiiliiilliiiisiit

$%jNEA1.03Ability -

tooperate and/or monitor 295026 Pool Suppression High the following asthey apply to WaterTemp./5 X xn . . . A SUPPRESSION POOLHIGHWATER 3.9 48 TEMPERATURE: Temperature Niid monitorin

$!pAifjji;j AA1.07 -

Ability tooperate and/or monitor 295023 Cooling Refueling Mode/8 Accidents X T" "iflil0 M P &!W thefollowing REFUELING as they a pply ACCIDENTS:Fuel to pool 29

' 49 coolin andcleanu s stem EA1.05 -

Ability tooperate and/or monitor 295025 HighReactorPressure/ X the following asthey apply toHIGH 3 Egy$g3 REACTOR PRESSURE: RCIC:Plant- 3.7 50 NMAlliLiEb S ecific CAiBW1AA2.04 -

Ability to determine and/or 295006SCRAM /1 $$j(j

'" " $$ SCRAM interpret the following

Reactor ressure asthey apply to 4.1 51 AA2.03Ability -

todetermine and/or 295005MainTurbineGenerator grAA!iajjjik interpret the following asthey apply to Trip/3 d@ $@l3 WAiP Turbine MAINTURBINE valve GENERATOR osition TRIP :

3.1 52 AA2.01Ability -

todetermine and/or 295019 InstAir Partial

/8 orTotal Loss 'of W AP interpret

PARTIAL the following ORCOMPLETE asthey apply to LOSSOF 3.5 53 A NA INSTRUMENT AIR:Instrument air s stem ressure AK2.02Knowledge -

ofthe interrelations 295018Partial orTotal Loss of between PARTIAL ORCOMI5LETE CCW/8 X m W + LOSSOFCOMPONENT COOLING 3.4 54 WATERandthe following: Plant a erations AA1.06Ability -

tooperate and/or monitor 295016 Room Control X ?jk j@j

[llllbl the following asthey apply toCONTROL 4 0 55 Abandonment/7 $!ifTM ROOMABANDONMENT: Reactor water '

level EK2.12- Knowledge ofthe interrelations 295031Reactor LowWater between REACTOR LOWWATER X N A jpdNLEVELandthefollowing: 4.5 56 Level/2 WMidili$ij5y Primary containment isolation s stem/NS4 AA2.02Ability -

todetermine and/or 295021 Cooling Loss

/4 ofShutdown @Qi dh AE VM interpret LOSSOFSHUTDOWN the following asthey apply COOLING to

34' 57 RHR/shutdown coolin s stemflow 295028HighDrywell -- . 2.4.18 -

Emergency Procedures /Plan:

/5 Temperature @l!jjlj!l@b

=*-

Knowledge EOPs ofthe specificbases for 3.3 58 K/ACategoryTotals: 3 5 3 4 dl@p jillpi Group Point Total: 20/7

ES-401 3 FormES-401-1 HC21-2 Written Examination Outline EmergencyandAbnormal Plant Evolutions -

Tier 1Group2 EAPE# /Name Safety Ki K2 K3 A1 A2 G K/ATopic(s) Imp. Q#

Function 295015 SCRAM /1 Incomplete bt dj[AA2.01 -

Ability todetermine and/or d@h em MM pe interpret INCOMPLETE the following asthey SCRAM:Reactor apply to power 4.3 83 295012 HighDrywell Temperature AmW PA& QAs 2.1.25 ag .

mterpret Conduct reference ofOperations:

materials, such Ability to asgraphs, 4.2 84

/5 kjE curves, tables, etc.

jjjj@jj $!Gi

@fj??

AA2.02Ability -

todetermine and/or 295010 HighDrywell /5 Pressure jj$lj lEs&

interpret fid HIGHDRYWELLPRESSURE the following asthey apply to

Drywell 3.9 85

?$@M ressure 295008 High Reactor Water Level X AM$23 implications AK1.03 -

Knowledge ofthe ofthe following operational concepts as Ndpj% 32 59

/2 they apply toHIGHREACTOR WATER '

pphE q# LEVEL:Feed flow/steam flow mismatch

$Wi $@fk AK2.04 -

Knowledge ofthe interrelations 295022 Loss ofCRDPumps /1 X --E NEW between LOSSOFCRDPUMPS and the 2.5 60 followine: Reactor water level

$5lM E@!jR AA2.01 -

Ability todetermine and/or 295009 LowReactorWaterLevel @@

gg::: ;::.<

$@lj[ interpret the gj@ LOW REACTOR following asthey WATERLEVEL:

apply to 4.2 61 Reactor water level w= Ability tooperate and/or monitor j@

=

295034 Containment Secondary j@@@ ttoEA1.03 hefollowing asthey apply Ventilation HighRadiation

/9 X 7 SECONDARY CONTAINMENT 4.0 62

$!j$ E@@A M!bW VENTILATION Secondary HIGH Containment RADIATION Ventilation

, EA2.01 -

Ability to determine and/or High 295032 Secondary Containment Area /5 Temperature j@ jll@jjlljlj interpret AC NiMihHIGHSECONDARY the following as they CONTAINMENT apply to 38' 63 AREATEMPERATURE :Area tem erature

$$@@iMR 2.1.31 -

Conduct ofOperations: Ability to 295020 Inadvertent Cont. M@Pi locate control roomswitches, controls, and

/5& 7 Isolation @b@6 WR indications, correctly andtodetermine reflect thedesired that lant they lineu -

4.6 64 m EK2.03 -

Knowledge ofthe interrelations High 500000 CTMTHydrogen j@b a between HIGHCONTAINMENT Cone.

/5 X kW HYDROGEN CONCENTRATIONS and 3.3 65 fm y4; the following: Containment Atmosphere NdbWWE Control S stem we am 1 0 agam WE 1 22% Group Total.:

K/ACategory Totals: 2 Point 7/3 was

ES-401 4 FormES-401-1 HC21-2 Written Examination Outline SystemsTier Plant -

2 Group1 System#/ Name K K K K K K A A2 A A G Imp Q#

1 2 3 4 5 6 1 3 4 T W@ A2.08Ability to(a) predict the jjj$ impacts ofthe following onthe do MGM AVERAGE POWER RANGE d M MONITOR/LOCAL POWER APRM/LPRM 215005 /$e A + j$:RANGEMONITOR SYSTEM '

&J and(b) based onthose predictions, 3.4 86 p5 useprocedures tocorrect, control, j:g wgf ormitigate the consequences of gg "

AQA orerratic those abnom1al conditions: Faulty A operation of detectors/systems A A2.01Ability (a) to predict the j@

AM impacts D.C.

ofthe ELECTRICAL following onthe DCElectrical 263000 w -

and based Distribution APW DISTRIBUTION (b) on 3.2 87 ye w x

Wy those predictions, useprocedures to correct, control,ormitigate the consequences of those abnormal

! conditions oro erations: Grounds 2.4.49 Emergency Procedures /

5 Plan: Ability toperform without 223002 PCIS/NuclearSteam #4 reference toprocedures those Shutoff Supply xWbe actions that require immediate 4.4 88

operation ofsystemcomponents E andcontrols.

300000 Instrument Air m 2.4.11 -

Emergency Procedures /

EA Plan: ofabnormal 4.2 89 Knowledge 72069 Aw condition rocedures.

A 2.2.44 -

Equipment Control: Ability 3$bl$ tointerpret control room indications ADS 218000 :g AjXbPW toverify we asystem, the status and andunderstand operation how of 4.4 90 m,

operator actions anddirectives j:.

M WW effect lant ands stemconditions.

sAe GP Kl.01Knowledge ofthe physical T$ Wh connections and/or cause- effect relationships between ADS 218000 X WT Aj@W AUTOMATIC 4.0 1 DEPRESSURIzATION SYSTEM and the following: RHR/LPCI:

$1 M$2Plant-S ecific q;gs 2MTP K1.06Knowledge ofthe a&M -.J physical connections and/or Ed WWcause- effect relationships SRVs X m W- EMil between RELIEF/SAFETY 239002 following: 3.4 2 M:::' fjm my VALVESandthe Drywell instrument air/ drywell pneumatics: Plant-WW A$5 S ecific 203000 RHR/LPCI: .

Injection X xam - = K2.01Knowledge ofelectrical Mode mys aa powersupplies tothe following: 3.5 3 Pums K2.01Knowledge ofelectrical X MA power following:

215003 IRM supplies tothe 2.5 4 IRMchannels/detectors

ES-401 4 FormES-401-1 HC212 Written Examination Outline SystemsTier Plant -

2 Group1 System# /Name K K K K K K A A2 A A G Imp Q#

1 2 3 4 5 6 1 3 4 -

Rg@

eC QM that K3.01Knowledge a loss oftheeffect ormalfunction ofthe ACElectrical 262001 X w GAA A.C. ELECTRICAL 3.5 5 Distribution DISTRIBUTION willhave m@if on

$!!$ dedfollowin :Ma'or s stemloads oftheeffect K3.02Knowledge f that a loss ormalfunction ofthe w UNINTERRUPTABLE POWER 2.9 UPS(AC/DC) 262002 X g!Gw SUPPLY 6 (A.C./D.C.) will have gp Ted W

om onfollowing:

s eed:

Recirculation Plant-S ecific pump Wh WA K4.09Knowledge -

of

  • W AW REACTOR WATERLEVEL 259002 Reactor Level Water X A "

CW CONTROL SYSTEM design interlocks 31 7 Control feature(s) and/or '

which provide forthe following:

Sinleelement control AAjjAK4.05Knowledge of EU SHUTDOWN COOLING SYSTEM(RHR SHUTDOWN 205000ShutdownCooling X AT W COOLING MODE) design 3.6 8 feature(s) and/or interlocks which provide forthe following:

Reactor cooldown rate

@ik AM K5.01 Knowledge ofthe "T QAPoperational implications ofthe DCElectrical 263000 following concepts asthey apply Distribution X @x T W toD.C. ELECTRICAL 2.6 9 ad4g% DISTRIBUTION:

s!p generation Al@I Hydrogen during battery f char in

@!S K5.05Knowledgeof the f operational implications of the 1 following concepts asthey apply EDGs 264000 X pg Sit toEMERGENCY 3.4 10

@ @@ GENERATORS 20 Parallelin (DIESEL/JET) :

A.C.ower sources K6.04Knowledge oftheeffect F that a loss ormalfunction ofthe RPS 212000 X mm followin haveonthe 9 will 28 11 EE MA REACTOR PROTECTION '

SYSTEM:D.C. electrical dia l2EAif distribution

@@k l@$

n . ...

K6.03Knowledge W that a loss oftheeffect ormalfunction ofthe SLC 211000 X A%in 1 following willhave onthe 3.2 12

(@b STANDBY EA SYSTEM LIQUID

A.C.ower CONTROL A1.05 -Ability topredict and/or An siSjMis monitor changes inparameters associated with operating the 217000 RCIC X Aieikiilh WiM REACTOR COREISOLATION 3.7 13 Q COOLING SYSTEM(RCIC)

Q@@j$$

WE AV controls s eed including: RCICturbine gaM A1.04Ability topredict and/or Component 400000 Coolmg $$T y monitor changes inparameters Water X 938 $@ s A associated with operating the 2.8 14 CCWScontrols including: Surge TankLevel

ES-401 4 FOrmES-401-1 HC21-2 Written Examination Outline SystemsTier Plant -

2 Group1 System#/Name K K K K K K A A2 A A G Imp Q#

1 2 3 4 5 6 1 3 4 to(a)

I@@

A2.11Ability predict the w A WWEimpacts ofthe following onthe STANDBY GASTREATMENT SYSTEMand(b) , based on SGTS 261000 /WV pjg pp those predictions, procedures use tocorrect, control, or 3.2 15 A AiE mitigate the consequences of those abnormal conditions or operations: High containment aw ressure Gj0 A2.01Ability Migbt: impacts ofthe (a) to predict following the onthe hspA $jl)AVERAGEPOWERRANGE f MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ,

APRM/LPRM 215005 m

Ai&&

.. we

= and(b) based onthose 2.7 16 m!!m predictions, useprocedures to d!E %S correct, control, or mitigate the consequences of those A abnormalconditions or Ap operations: Power supply W$1 ;jWip de raded A3.02 -

Ability tomonitor automatic operations ofthe PRIMARY CONTAINMENT 223002 PCIS/NuclearSteam Supply Shutoff at X

"'^ EiM ISOLATION 3.5 17 SYSTEM/NUCLEAR STEAM SUPPLYSHUT-OFF including:

Valve closures A3.01Abilityto monitor automatic operations ofthe 206000 HPCI M X EW HIGHPRESSURECOOLANT 3.6 18 INJECTION SYSTEMincluding:

Turbine s eed:BWR-2,3,4

$ A4.01Ability tomanually 300000 Air Instrument ATAE X MA operate and/or monitor inthe 2.6 19

!i5iEi$ control room: Pressure aues A4.06Ability tomanually 215004 Source Range Monitor 421 X ha?g operate and/or monitor inthe 3.2 20 EA control room: Alarms andlihts gj@j @ A4.11Ability -

tomanually LPCS 209001 ' =

X WEEioperate and/or monitor inthe 3.7 21 control room: S stem flow 2.1.30 -

Conduct ofOperations:

SLC 211000 fi@g jlj@plj Ability tolocate andoperate local 4.4 22 sp,

$4 qpy components, AP controls.

including was Egg $3 design re" K4.01Knowledge feature(s) ofCCWS andor 400000 Component Cooling X interlocks which provide forthe 3.4 23 System Water (CCWS) following: Automatic start of standbum A4.01Ability tomanually 259002 Reactor Level Water operate and/or monitor inthe

,..., X WE control room: All i ndividual 3.8 24 Control MEG component controllers inthe Migg el ...

ME manual mode.

ACElectrical 262001 Distribution

@[

AM

$jg 2.1.20 TXL Ability Conduct tointerpret ofOperations:

andexecute 4.6 25 L

a ..

$jD!Fib ren racedure stes.

ES-401 4 FormES-401-1 HC21-2 Written Examination Outline SystemsTier Plant -

2 Group1 System

  1. /Name K K K K K K A A2 A A a Imp ag 1 2 3 4 5 6 1 3 4 ME) A3.02Ability tomonitor SGTS 261000 -

? X automatic ofthe operations 32 26

!A STANDBY GASTREATMENT '

Em SYSTEM includin il;i!$!s!!l!!!A :Fanstart K/ACategory Totals: 2 2 2 3 2 2 2 j3@j@@3 4 GroupPoint Total: 26/5

ES-401 5 FormES-401-1 HC21-2 Written Examination Outline SystemsTier Plant -

2 Group2 System#/Name K K K K K K A A2 A A G Imp Q 1 2 3 4 5 6 1 3 4 , #

ns:x pW A2.03Ability -

to(a) predict the app impacts 2%lM RODBLOCKMONITOR ofthe following onthe 17 g@ SYSTEM ;and(b) based on pgg ggygy those predictions, use RBM 215002 p$2 Qj@ procedures to correct, control, 3.3 91

~7 .

tAM ormitigate theconsequences of m $R2 those abnormal conditions or

@D T AA operations:

RAA reference Loss ofassociated APRMchannel:

E BWR-3,4,5 2.4.31 -

Emergency Procedures 290003 RoomHVAC Control W !iiAlliex p, /Plan: Knowled e of 3.3.7.1

/A E TA annunciator alarms, indications, 4 1 92 i orresonseprocedures.

A1% MitiA 2.4.30 -

Emergency Procedures

/Plan; Knowledge ofevents related tosystem operation /

Qjiki W% status that mustbereported to 272000 Monitonng A5ga Radiation WXL 4.1 93 q internal organizationsor m

external agencies, suchasthe

/ :

state, the NRC,orthe i$M transmission s stemo erator.

K1.07 Knowledge ofthe jj physical connections and/or 256000 ReactorCondensate X cause- effect relationships 2.9 27 between REACTOR L. Rihil CONDENSATE SYSTEM and MA @hjkthefollowin :SJAE condenser Primary 223001 CTMTand K2.10Knowledge of electrical Aux' X ,ga Aa gy power

%@ D ell supplies chillers:

tothefollowing:

Plant-S ecific 2.7 28 l$FiAA K3.04Knowledge oftheeffect Agi that a loss or malfunction ofthe 234000 FuelHandling X gi Ai:FUELHANDLING EQUIPMENT Reactor 2 9 29 Equipment K3.03 a " will have onfollowing: '

@@ manual control system: Plant-S ecific K4.01Knowledge ofOFFGAS Off-gas 271000 E SYSTEM design feature(s)

X gga g$EiCand/or interlocks which provide2.9 30

%$ ElyAfor the following:

h droen asconcentration Dilution of y@ K5.04Knowledge -

ofthe g" operational implications ofthe 230000 RHR/LPCI e ag gpEAfollowing concepts asthey apply Spray Torus/Pool Mode X 6@/+U NA toRHR/LPCI: 2.5 31 TORUS/SUPPRESSION POOL SPRAYMODE:Evaporative coolin p M K6.01Knowledge oftheeffect

$1 that a loss ormalfunction ofthe 216000 Nuclear Boiler Inst. X W = AW followin will have onthe 3.1 32 oA NUCLEAR BOILER

%33 22 @W INSTRUMENTATION

"$M electrical distribution

A.C.

ES-401 5 FormES-401-1 HC21-2 Written Examination Outline Plant SystemsTier-2 Group2 System# / Name K K K K K K A A2 A A g Imp Q 1 2 3 4 5 6 1 3 4 #

QW3 PWPA1.13Ability -

topredict and/or monitor changes inparameters associated with operating the 202001 Recirculation X Ap em mde RECIRCULATION SYSTEM 3.1 33 controls including: Recirculation loop temperatures: Plant-S ecific A2.05Ability impacts ofthe (a) to predict following on the the CONTROL RODAND 201003 Control Rodand WW mm .DRIVE MECHANISM ;and(b)

Drive Mechanism based onthose predictions, use 4.1 34 procedures tocorrect, control, 4 A: ormitigate the consequences of those abnormal conditions or C : o erations: Reactor Scram

,,g p,, automatic A3.01 -

Ability tomonitor operations ofthe 219000 RHR/LPCI: X RHR/LPCI: 3.3 35 Cooling Torus/Pool Mode TORUS/SUPPRESSION POOL COOLING MODEincluding:

Valve o eration fs A A4.03 -

Ability tomonitor Qj ',

AWl automatic operations of the ROD WORTH MINIMIzER RWM 201006 AiW X
SYSTEM (RWM) (PLANT 3.0 36 wijb egg j@M group SPECIFIC) including:

indication:

Latched P-Spec(Not-BWR6 fif!hii 2.4.9 -

Emergency Procedures /

RWCU 204000

@!Vil WA shutdown Plan: Knowledgeof low power /

implications in A!0accident (e.g., loss ofcoolant "

accident orloss ofresidual heat removal) miti ation strate ies.

K3.01Knowledge oftheeffect 4 AT + that a loss ormalfunction ofthe RMCS 201002 X REACTOR MANUAL 3.4 38 CONTROL SYSTEM willhave onfollowing: Ability tomove control rods we K/ACategory Totals: 1 1 2 1 1 1 1 11!/11 1 1 A172!A Group Point Total: 12/3

ES-401 Generic Knowledge andAbilities Outline(Tier 3) FormES-401-3 Facility: HC21-2 Date: 02/01/21 RO SRO-Only Category K/A# Topic IR Q# IR Q#

Ability toidentify andinterpret diverse 2.1.45 indications tovalidate theresponse of 4.3 94 another indicator.

Ability toperform specific system and 2.1.23 integrated plant procedures during aII modes 4.4 98 of lant o eration.

1.

Conduct Ability to evaluate plant performance and ofOperations makeoperational judgements based on 2 17 operating characteristics, reactorbehavior, 4.4 66 andinstrument inter retation.

Ability toexplainand apply all 2.1.32 and recautions. system limits 3.8 67 Subtotal WEW2 MD 2 2.2M tem Knowledge ofthe process forcontrolling 3.3 95 ora desinchanes.

2.2.7 sKnowledge oftheprocess forconducting 3.6 99 ecial orinfre uent tests.

2 2.2.12 Knowledge ofsurveillance procedures. 3.7 68 Equipment Ability todetermine theexpected plant Control configuration using design and configuration 2.2.15 control documentation, such asdrawings, 3.9 69 line-u s,ta-outs, etc.

Ability torecognize system parameters that 2.2.42 areentry-level conditions forTechnical 3.9 74 S ecifications.

Subtotal $$ 3 [jph2 2.3.6 Ability toapprove release permits. 3.8 96 3 Ability tocomply with radiation work permit R'adiationconditions.

2.3.7 requirements during normalorabnormal 3.5 70 Control Knowledge ofRadiological Safety Procedures pertaining tolicensed operator duties, 2.3.13alarms, such a s response toradiation monitor3.4 71 containment entryrequirements, fuel handling responsibilities, access tolocked hihradiation areas, alininfilters, etc.

ES-401 GenericKnowledge Outline(Tier andAbilities 3) FormES-401-3 Knowledge ofradiationorcontainment hazards 2.3.14 abnormal, that may arise during normal, 3.4 75 oremergency conditions or activities.

Subtotal Ed 3 /@k[ 1 2.4.40 Knowledge ofSRO.responsibilities in .

4.5 97 emerenc lan imlementation.

2.4.6 Knowledge ofEOPmitigationstrategies. 4.7 100 4' Knowledge oflocal auxiliary tasks operator Emergency 2.4.35during emergency andtheresultant 3.8 72 P ocedures

/ o erational effects.

Knowledge of procedures 2.4.28securi relating toa 3.2 73 event.

Subtotal WA 2 ..

j$ 2 Tier3Point Total $AA 10 JRj[7

ES-401 Record ofRejected K/A's FormES-401-4 Tier / Group RandomSelected Reason for Rejection K1.02Knowledge ofthephysical connections and/or cause-

, effect relationships between RELIEF/SAFETY VALVES andthe following: SPDS/ERIS/CRIDS/GDS: Plant-Specific There isnospecific physical connection to 2/1 (#2) 239002/K1.06 SPDS/ERIS/CRIDS/GDS with a cause-effect relationship for SRVs.Nolicense level question canbewritten for this specific K/Afor SRVs.

Randomly reselected: Drywell instrument air/drywell pneumatics:

Plant-Specific (PCIG)

A1.03 -

Ability topredict and/ormonitor changes inparameters associated with operating theCCWScontrols including: CCW Pressure 2/1 (#14) 400000/A1.04There isnopressure setpoint orvalue forthe CCWsystems that isspecifically monitored. Flows, Temperatures, andSurge Tank levels arecontinuously monitored along with setpoints.

Randomly reselected: Surge Tank Level 2.1.23 -

Conduct ofOperations: Ability toperform specific system andintegrated plant procedures during all modes of plant operation.

2/1 (#21) 209001/A4.11There isnoreference totheCore Spray system inthe integrated procedures ata level for a license examquestion.

Randomly reselected: Abilitytomanually operate and/or monitor inthecontrol room: System flow.

2.2.38 -

Equipment Control: Knowledge ofconditions and limitations inthe facility license.

2/1(#22) 211000/ 2.1.30 This K/Areferences TechSpecs which isattheSROlevel.

Randomly reselected: Conduct ofOperations: Abilitytolocate andoperate components, including localcontrols.

A4.09Ability tomanually operate and/or monitor inthe control room: TDRFPlockout reset: TDRFP 2/1 (#24) 259002/A4.01 There isnolockout parameter for theRFP's atHopeCreek.

~

Randomly reselected: AII individual component controllers inthe manual mode.

ES-401 Record ofRejected K/A's FormES-401-4 2.1.27 -

Conduct ofOperations: Knowledge ofsystem purpose and/orfunction.

2/1

(#25) 262001/ 2.1.20 Cannot write a license level question with a purpose ofasystem.

Toolowofa cognitive level question.

Randomly reselected: Ability tointerpret andexecute procedure stes.

A1.05Ability topredict and/or monitor changes inparameters associated with operating the STANDBY GASTREATMENT SYSTEM controls including: Primary containment oxygen level:

Mark-l&II 2/1(#26) 261000/ A3.02 There isnoOxygen parameter thatdirectly interfaces with the FRVS system.

Randomly reselected: A3.02Ability tomonitor automatic operations of the STANDBY GASTREATMENT SYSTEM including: Fan start K3.02Knowledgeof the effect that a loss ormalfunction ofthe REACTOR MANUAL CONTROL SYSTEMwill have onfollowing:

Rodblock monitor: Plant-Specific 2/2(#38) 201002/ K3.01 Anymalfunction orinoperability of the RMCSwould not recognize anyinput from theRBM. Cannot write a license level question without plausible distractors.

Randomly selected: K3.01- Ability tomove control rods.

EK1.06Knowledge oftheoperational implications ofthe following concepts asthey apply toSCRAMCONDITION PRESENT ANDREACTOR POWER ABOVEAPRM DOWNSCALE ORUNKNOWN: Cooldown effects onreactor power.

1/1(#40) 295037/ EK1.03 A cooldown oftheRPVprior tobeing shutdown under all conditions would notbeallowed IAWemergency operating procedures.

Randomly reselected: Boron effects onreactor power (SBLC).

EK2.12 Knowledge oftheinterrelations between HIGHOFF-SITERELEASE RATEandthe following: Feedwater leakage control: BWR-6 1/1(#42) 295038/ EK2.06 There arenoHopeCreek procedures that reference Feedwater leakage control with Offsite Release. Cannot write a license level question for this K/A.

Randomly reselected: Process liquid radiation monitoring system

ES-401 Record ofRejected K/A's FormES-401-4 AK3.01Knowledge ofthereasons forthe following responses asthey apply toPARTIAL ORCOMPLETE LOSSOFD.C.

POWERLoad shedding 1/1

(#45) 295004/ AK3.02 There isnoautomatic "load shedding" duetoa loss ofD.C.Load shedding occurs froma lossofA.C.

Randomly reselected:

Ground isolation/fault determination AA1.07 Ability tooperateand/or monitorthe following asthey applytoREFUELING ACCIDENTS :Standby gas treatment/FRVS 1/1(#49) 295023/ AA1.02 The above concept (K/A)issimilar toQuestion #26which would cause "Double Jeopardy"onthe exam.

Randomly reselected: Fuel pool cooling andcleanup system AA2.01Abilityto determine and/or interpretthe following as they apply toSCRAM :Reactor power 1/1

(#51) 295006/ AA2.04 L.O.D for a questiononwhat happens toreactor power ona scram (power lowers,APRMs downscale) would be1.

Randomly reselected:Reactor pressure 2.4.6Emergency Procedures /Plan: Knowledge ofEOP mitigation strategies.

1/1 2.4.18 ofEOPmitigation strategiesareatthe SROleveldue toselection

(#58) 295028 EOPprocedures andactions within thelegs ofthe EOP procedures tosatisfy themitigation strategy.

Randomly Knowledge selected: ofthespecific bases for EOPs.

2.4.41- Emergency Procedures /Plan: Knowledge ofthe emergency actionlevelthresholds andclassifications.

There arenoECG/classifications for theInstrument AirSystem IAWtheHopeCreek EALsandRALs.

2/1(#89) 300000 2.4.11 Randomly reselected:Knowledge ofabnormal condition procedures.

ES-401 Record ofRejected K/A's FormES-401-4 A2.01-RODBLOCK Ability (a) to predict MONITOR theimpacts SYSTEM;and(b) ofthefollowing based onthe onthose predictions, useprocedures tocorrect, ormitigate control, the consequences ofthose abnormal conditions oroperations:

Withdrawal ofcontrol rod inhigh power ofcore:

region BWR-3,4,5 2/2(#91) 215002/ A2.03 There isnoprocedure that directly ormitigates addresses the consequences ofa control rodwithdrawal inthe higher power region ofthe core. This ismoreofa GFEStype K/A.

Randomly reselected: Loss ofassociated APRM reference channel: BWR-3,4,5 Loss ofassociated reference APRMchannel: BWR-3,4,5 Loss of associated reference APRMchannel: BWR-3,4,5 Loss of associated reference APRMchannel: BWR-3,4,5 2.4.26 Knowledge offacility protection requirements, including fire brigade and portable firefighting equipment usage.

There isnofire brigade (separate fire department)atHope 3/4(#97) 2.4.40 Creek. Cannot write a SRO license level questiontothis K/A.

Randomly reselected: Knowledge ofSROresponsibilities in emergency plan implementation.

. .

Retrieved from "https://kanterella.com/w/index.php?title=ML21076A063&oldid=3534049"