ML21076A063

Final Written Examination and Operating Test Outlines (Folder 3)

ML21076A063
Person / Time
Site:	Hope Creek
Issue date:	03/09/2021
From:	Public Service Enterprise Group
To:	Todd Fish Operations Branch I
Shared Package
ML19353E011	List: IR 05000354/2021301 ML20132A155 ML21032A102 ML21075A102 ML21075A103 ML21075A105 ML21076A062 ML21076A063 ML21076A064 ML21076A066 ML21117A083 ML21117A084
References
EPID L-2021-OLL-0001
Download: ML21076A063 (34)

Text

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

M DateofExamination:

2/22/21 Examination Level:

RO 2 SRO D Operating TestNumber:

1 Administrative Topic (seeNote)

Type Describe activity tobeperformed Code*

Perform aReactor Recirculation PumpQuick Restart Conduct ofOperations TaskStandard:

Operator completes StepG.12 ofHC.OP-AB.RPV-0003 forrestart ofReactor D,S Recirculation Pump KA-2.1.18

- Ability tomakeaccurate,

clear, andconcise

logs, records, status

boards, and reports.

Perform Steps 5.1through 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 theapumpinternal inspection.Using controlled station drawings (provided):

Equipment Control 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

- Ability toObtain andInterpret Station Electrical

&Mechanical Drawin s

Determine Liquid Radwaste RadMonitor CTB WeirFlow Radiation Control TaskStandard:

Operator completes theDay Shift reading forHC.OP-DL.zz-0026, D

Attachment 1a,ITEM47,fortheRMSCooling TowerBlowdown WeirFlowRateMonitor and identifies anyvariance.

KA

- 2.3.11

- Ability tocontrol radiation releases.

ES301 Administrative Topics Outline FormES-301-1 EmergencyPlan N/A NOTE:Allitems (five total) are required forSROs.ROapplicants require only four items unless they areretaking only the administrative topics (which wouldrequire allfiveitems).

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

(N)ewor (M)odified frombank(21)

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

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

2/22/21 Examination Level:

RO O SRO 2 Operating TestNumber:

1 AdministrativeTopic (seeNote)

Type Describe activity tobeperformed Code*

PERFORM theShift Manager review oftheOP-AA-105-102, Attachment 2,foranSROlicense Conduct ofOperations renewal fortheControl RoomSupervisor M,R position TaskStandard:

Determines license reactivation requirements havenotbeenmet(and why)in accordance with OP-AA-105-102.

KA 2.1.5Ability touseprocedures related to shift

staffing, suchasminimum crew com

lement, overtime limitations, etc.

Complete DailySurveillance log Conduct ofOperations Task Standard:

Operator implements thelogat the beginning ofthedaybycompleting Attachment 1,Section A,ofHC.OP-DL.zz-0026 P,R andidentifies attachments requiredIAWthe answer key KA-2.1.18

- Ability tomake

accurate, clear, andconcise,

logs, records,status boards and reorts Reviewandapprove WorkClearance Documents (WCDs).

Youhave been presented withtheWCDforIndependent Review and Pre-Equipment Control N,R Approval inaccordance with OP-AA-109-115,

'Safety Tagging Operations forCRDPP"A" TaskStandard:

Identify discrepancies IAW answer key KA-2.2.41

- Ability toObtain andInterpret Station Electrical

&Mechanical Drawin s

PERFORM step5.1.11 ofHC.OP-GP.zz-0004 todetermine theleakage into theCoreSpray Radiation Control LoopA Injection Header.

Determine any D,R required actions andRECORDthembelow TaskStandard:

Operator completes the CRS/SMreview ofacompleted HC.OP-GP.zz-0004andnotes actions required.

KA-2.3.11 Ability tocontrol radiation releases.

ES-301 Administrative Topics Outline FormES-301-1 Utilize TheECGTo~Determine TheEmergency Classification And/Or Reportability OfAnEvent And/Or Plant Condition EmergencyPlan D,R TaskStandard:

Operator appropriate declaration inaccordance with answer key; initiates aPAR;andmakesnotifications within identified Critical Timesinaccordance with EP-HC-111-101.

KA2.4.38

- Ability totakeactions called forin thefacility emergency

plan, including Isupporting oracting asemergency coordinator ifreuired.

NOTE:AIIitems(five total) arerequired for SROs.

ROapplicantsrequire only four items unless they areretaking only theadministrative topics (which would require all five items).

• TypeCodesandCriteria:(C)ontrol

room, (S)imulator, orClass(R)oom (D)irect frombank(53for ROs; s4forSROsandROretakes)

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

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

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

M DateofExamination:2/22/21 Exam Level:

RO 2 SRO-1D SRO-U O Operating TestNumber:

1 Control Room Systems:* 8forRO,7forSRO-l,and2or3forSRO-U System/JPM Title TypeCode*

Safety Function S,D,A,L 5

a.Respond toRising Drywell Pressure S,P,A,EN,L 4

b.PlaceHPCIinfull flowTest Operation c.Place RCICinservice fromtheRSP S,D,EN 2

S,D 6

d.Perform Non-Emergency Operation ofthe EDG S,N,A 8

e.SwapRACspumps f.Enabling Automatic Backup Stability Protection foranAPRM IAW S,N 7

HC.OP-SE-0001 Step4.10 g.Resetting RPSTrips S,P,A 1

h.SwapControl RoomVenttrains IAWHC.OP-SO.GK-0001 S,D 9

In-Plant Systems:*

3forRO,3forSRO-I,and3or2forSRO-U i.Transfer RPSBusA/BPowerfromAlternate Source toRPSMGSet D,A 7

D,R 1

",Shift in-service CRDflowcontrol valves D,E 3

k.ResondtoaFailed O enSRV AIIROandSRO-Icontrol room(and in-plant) systems mustbedifferent andservedifferent safety functions, allfive SRO-Usystems mustservedifferent safety functions, andin-plant systems and functions mayoverlap those tested inthecontrol room.

• TypeCodes Criteria forR/SRO-l/SRO-U (A)lternate path 4-6/4-6

/2-3 (C)ontrol room (D)irect frombank s9/s8/s4 (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 frombankincluding 1(A) 22/22/21 (P)revious 2exams s3/s3/s2(randomly selected)

(R)CA a1/21/21 (S)imulator

ES-301 Control Room/In-Plant SystemsOutline FormES301-2 Facility:

M DateofExamiriation:

2/22/21 Exam Level:

RO D SRO-I2 SRO-U D Operating TestNumber:

1 Control Room Systems:* 8forRO,7forSRO-I, and2or3forSRO-U System/JPM Title TypeCode*

Safety Function S,D,A,L 5

a.Respond toRising Drywell Pressure S,D,A,EN 4

b.Place HPCIinfull flowTest Operation S,D,EN 2

c.Place RCICinservice fromtheRSP S,D 6

d.Perform Non-Emergency Operation oftheEDG S,N,A 8

e.SwapRACspumps f.Enabling Automatic Backup Stability Protection foranAPRM IAW S,N 7

HC.OP-SE-0001 Step4.10 g.Resetting RPSTrips S,P,A 1

In-Plant Systems:*

3forRO,3forSRO-I, and3or2forSRO-U D,A.

7 i.Transfer RPSBusA/BPowerfromAlternate Source toRPSMGSet D,R

=

1

" Shift in-service CRDflowcontrol valves D,E 3

k.ResondtoaFailed O enSRV AIIROandSRO-Icontrol room(and in-plant) systems mustbedifferent andserve different safety functions, all five SRO-Usystems mustservedifferent safety functions, andin-plant systems and functions mayoverlap those tested inthecontrol room.

• TypeCodes Criteria forR/SRO-I/SRO-U (A)lternate path 4-6/4-6

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

(L)ow-Power/Shutdown a1/21/21 (N)ew or(M)odified frombankincluding 1(A) 2 2/22/21 (P)revious 2exams 53/s3/s2(randomly selected)

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

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

b* c"

1. Theinitial conditions are realistic inthat someequipment and/or instrumentation maybeoutofservice, butitdoesnotcuethe operators into expected events.

g

2. Thescenarios consist mostly ofrelated events.

5f V

V

3. Eachevent description consists ofthefollowing:

thepoint inthescenario when it istobeinitiated a

themalfunction(s) orconditionsthat areenteredtoinitiate theevent a

thesymptoms/cues that will bevisible tothecrew a

theexpected operator actions (by shift position)

(

a theevent termination point (if applicable) y?

4. Theevents arevalid withregard tophysics andthermodynamics.

f

5. Sequencing andtiming ofevents isreasonable andallows theexamination teamtoobtain complete evaluation results commensurate with thescenario objectives.

8-

6. Iftimecompression techniques areused,thescenario summary clearly soindicates.

Cuesaregiven.

r b b(

Operators havesufficient time tocdrry outexpected activities without undue time constraints.

7. Thesimulator modeling isnotaltered.

Sf f

8. Thescenarios havebeenvalidated.

Pursuant to10CFR55.46(d),

anyopensimulator performance deficiencies ordeviations fromthereferenced plant havebeenevaluated toensure thatfunctional y g fidelity ismaintained while running theplanned scenarios.

5'p

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

6 1.0.

AIIindividual operator competencies canbeevaluated, asverified using FormES-301-6 (submit the formalong with thesimulator scenarios).

q, 4

11.Thescenario setprovides theopportunity foreachapplicant tobeevaluated ineachofthe applicable rating factors.

(Competency rating factors asdescribed onFormsES-303-1and ES-303-3.)

d (f 12.Eachapplicant will besignificantly involved intheminimumnumberoftransients andevents specified onFormES-301-5 (submit theform with thesimulator scenarios).

2 13.Applicants areevaluated onasimilar number ofpreidentified critical tasks across scenarios, when possible.

Sp V

l 14.Thelevel ofdifficulty isappropriateto support licensing decisions foreachcrewposition.

of b Target Quantitative 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.

Major transients (1-2) 1/1/1 y

d 4.

EOPsentered/requiring substantive actions (1-2) 2 /2 /3 5.

Entry into acontingency EOPwithsubstantive actions

(>

1perscenario 2 /1 /1 f

set)

IV V (

6.

Preidentified critical tasks (22) 2 /2 /3 JO

• Thefacility licensee signature isnotapplicable forNRC-developed tests.

1. Anindependent NRCreviewer initials items incolumn "c";

chief examiner concurrence isrequired.

i

ES-301 Transient andEventChecklist FormES-301-5 A

E Scenarios 1

2 3

4 T

M L

N CREW CREWPOSITION CREWPOSITION CREWPOSITIONO I

I T

POSITION T

C A

S A

B S

A B

S A

B S

A B

y A

T R

T O

R T

O R

T O

R T

O L

U O

C P

O C

P O

C P

O C

P M(*)

p 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 level andenter theoperating test number andFormES-D-1 event numbers foreachevent type; TS arenotapplicable forROapplicants.

ROsmustserve inboththeat-the-controls (ATC) andbalance-of-plant (BOP) positions.

Instant SROs(SRO-I) mustserve inboththeSROandtheATCpositions, including atleast twoinstrument or component (I/C) malfunctions andonemajor transient, intheATCposition.

IfanSRO-1 additionally serves intheBOP

position, oneI/Cmalfunction canbecredited toward thetwo1/Cmalfunctions required fortheATCposition.

2.

Reactivity manipulations maybeconducted under normal orcontrolledabnormalconditions(refertoSect D.5.d) but mustbesignificant perSection C.2.a ofAppendix D.(*)

Reactivity andnormal evolutions maybereplaced with additional I/Cmalfunctions onaone-for-one basis.

3.

Whenever practical, bothinstrument andcomponent malfunctions should beincluded; only those that require verifiable actions that provide insight totheapplicant's competence count toward theminimum requirements specified for the applicant's license level intheright-hand columns.

4.

Fornewreactor facility licensees that usetheATCoperator primarily formonitoring plant parameters, thechief examiner mayplace SRO-Iapplicants ineither theATCorBOPposition tobestevaluate theSRO-Iinmanipulating plant controls.

ES301 Transient andEventChecklist FormES-301-5 A

E Scenarios Pp 1

2 3

4 T

M L

N CREW CREW CREWPOSITIONCREWPOSITIONO I

I T

POSITION POSITION T

C A

S A

B S

A B

S A

B S

A B

y A

T R

T O

R T

O R

T O

R T

O L

U O

C P

O C

P O

C P

O C

P M(*)

p 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 I/C 3,7 5,7 2,5,7 11 4 4 2 RO#2 MAJ 6

6 4

3 2

2 1 TS 0

0 2 2

ES-301 Transient andEventChecklist FormES'-301-5 Instructions:

1.

Check theapplicantlevel andenter theoperating test number andFormES-D-1 event numbers foreachevent type; TS arenot applicable forROapplicants.

ROsmustserve inboththeat-the-controls (ATC) andbalance-of-plant (BOP) positions.

Instant SROs(SRO-l) mustserve inboththeSROandtheATCpositions, including atleast twoinstrument or component (I/C) malfunctions andonemajor transient, intheATCposition.

IfanSRO-I additionally serves intheBOP

position, one I/C malfunction canbecredited toward thetwoI/Cmalfunctions required fortheATCposition.

2.

Reactivity manipulations maybeconducted under normal orcontrolled abnormal conditions (refer toSection D.5.d) but mustbesignificantper Section C.2.a ofAppendix D.(*)

Reactivity andnormal evolutions maybereplaced withadditional I/Cmalfunctions onaone-for-one basis.

3.

Whenever practical, bothinstrument andcomponentmalfunctions should beincluded; onlythose that require verifiable actions that provide insight tothe applicant's competencecount toward theminimum requirements specified forthe applicant's license level inthe right-hand columns.

4.

Fornewreactor facility licensees that use theATCoperator primarily formonitoring plant parameters, thechief examiner may laceSRO-Iapplicants ineither the ATC orBOP osition tobestevaluate theSRO-Iinmanipulating plant controls.

ES-301 Competencies Checklist FormES3016 Facility:

HOPECREEK DateofExam:

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 1,4,,5,,6 1,2y3,4 gy 1,g4,5 AII 1,2,5,6 All 1,3,4,6 andConditions Comply withand AII AII All All AII All All AII All All AII All UseProcedures 1

Operate Control 2,3,e,71,4,5,e 1,2,3,4 2,3,s,7 1,4,5,e 1,2,3,4 1,2,4,5 l'3,4,6 1,2,5 6

,8,,7,8,7

,8,

,7,8

,7

,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 TScompliance foranRO.

(2) Optional foranSRO-U.

(3) Onlyapplicable toSROs.

Instructions:

Checktheapplicants' license typeandenter oneormoreevent numbers that will allow the examiners toevaluate every applicable competency forevery applicant.

(This includes all rating factors foreachcompetency.)

(Forms ES-303-1 andES-303-3 describe thecompetency rating factors.)

ES-301 Competencies Checklist FormES-3016 Facility:

HOPECREEK DateofExam:

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/Diagnose Events AH 1f An 1,2e,5 All 1,3,4,6 AII 1,2g,5 gig 4

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 Boards2 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:

Checktheapplicants' license typeandenter oneormoreevent numbers that will allow the examiners toevaluate every applicable competency forevery applicant.

(This includes all rating factors foreachcompetency.)

(Forms ES-303-1 andES-303-3 describe thecompetency rating factors.)

Appendix D

Scenario Outline FormES-D-1 Facility:

Scenario No.: 1 Op-Test No.:

1 Examiners:

Operators:

Initial Conditions:=79%

power. BRFPTinRecirc Turnover:

Critical Tasks:

Raise Powerwith Recirculation Pumps 3

g p

Ea@uake M

2 PC07A C

Trip ofSSWPump(TS) 3 QQ09 C

MSLRMSChannel A Fails upscale (TS) 4 RM01A I

Inskument Une&eakin%well 5

RR31A1 I

AM 6

RP06 M

IAuoInWaknfaHure 7

HP06E C

AuplnWahn FaHure 8

CU11B C

(N)ormal, (R)eactivity, (1)nstrument, (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, ORifactuated, 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 thecurrent ATWSconditions ofthis

scenario, preventing ADSautomatic operation andpotential uncontrolle reactor level flood upprevents asignificant transient andsubsequent positive reactivity addition tothereactor.

EOPs direct this action under the current conditions.

This critical task isonlyapplicable ifRPVwaterlevel goesbelow 129".

Failure tosatisfactorily complete thetask isdemonstrated byanautomatic ACTUATIONofADSsuch that the ADSSRVsopenandreduce reactorpressure toless than 550psig.

2.

s CREWmaintains orrestores adequate core coolingbyrestoring/maintaining Compensated Reactor waterlevel to>185" IAWHC.OPEO.zz0101A without EmergencyDepressurizing.

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

EA2.02 Reactor waterlevel RO4.1SRO4.2 Maintaining adequate Corecooling under ATWSconditions is accomplished bymaintaining/restoring level above

-185".

HPCIandRCICarecapable ofmaintaining level under the current conditions.

AB.22-0001 provides directions onmanual initiation ofHPCIwhich will mitigate the automaticinitiation failure.AnEmergency Depressurization isnotwarranted andwould result inalarge injection ofcold water andthepotential displacement of boron fromthecore.

Appendix D

Scenario Outline FormES-D-1 Facility: E Scenario No.: 2 Op-Test No.:

1 Examiners:

Operators:

Initial Conditions:

100% Power Turnover:

RPSMGSet1BG401 has anoisybearing.

Transfer RPSBusBPower to its Alternate Supply inaccordancewith HC.OP-SO.SB-0001.

Critical Tasks:

Event Malf. Event Event No.

No.

Type*

Description 1

N/A N

Transfer

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

ReducePowerto95%

3 Rz02A C

RRCSPressure Transmitter Failure (TS) 4 CU11A C

RWCULeakw/Failure toAutomatically Isolate (TS) 5 TCO2-2 C

HighReactor Pressure 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

1. 2 1.Crew initiates isolation ofRWCU(e.g.,

closure ofRWCUHVF001ORHV-F004)

BEFORE differential flowexceeds 65gpm.

K/A223002Primary Containment Isolation System

/Nuclear SteamSupply Shut-Off A4Ability tooperate and/or monitor intheControl Room A4.01Valve Closures RO3.6SRO3.5 A4.06 Confirm initiation tocompletion RO3.6SRO3.7 TheRWCUSystem hasfailed toisolate automatically.

Failure oftheCrewtomanually isolate thesystem will result inabypass oftheReactor Coolant andPrimary Containment boundaries andrelease ofradioactive materials tothe Reactor Building.

2.Crewmaintains Suppression Chamber Pressure belowtheAction Required region of thePSPcurve.

K/A295024 HighDrywell Pressure EA1Ability tooperate and/or monitor the following astheyapply toHIGHDRYWELLPRESSURE:

EA1.11 Drywell Spray RO4.2SRO4.2 EA2Ability todetermine and/or interpret the following astheyapply toHIGHDRYWELLPRESSURE:

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

A2.02 Steambypass ofthesuppressions pool RO3.9SRO4.1 Ifsuppression chamber pressure cannot bemaintained below the pressure suppression pressure, EOPsdirect actions to emergency depressurize thereactor.

A LOCAcondition while intheaction required region ofthePressure Suppression Pressure

curve, could cause design containment limits tobe exceeded.

Based upontherateofpressure increase inthis

scenario, theCrewhasovertenminutes toinitiate DrywellSprays andprevent entry into theAction Required region ofthePSPcurve.

Thiswill prevent anunnecessary Emergency Depressurization, which isa significant challenge totheSuppression Poolandwould cause theCooldown Limit for theReactorCoolant system to beunnecessarily exceeded.

Reducing reactor pressure within thecooldown limit may also delay/prevent entry into 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 na en ysmAdua@n M

2 SL03A C

ssd mm M 3

ED11A I

ssasRe her 4

EG12 M

DG03B AutoStart Failure ofEDGs 5

C DG04B RCICTrip onOverspeed 6

RCO1 C

SACSPumpTrip 7

QQ15 C

(N)ormal, (R)eactivity, (1)nstrument, (C)omponent,.

(M)ajor

Appendix D

Scenario Outline FormESD-1 Critical TasksScenario

1. 3 1.Crew restores/maintains APRMPowerto<100%within five minutes oftheCoreThermal Power5Minute Average exceeding 3910MWth.

K/A295001 Reactor Feedwater System A2Ability to(a)predict theimpacts ofthefollowing ontheReactor Feedwater System; and(b) based on those predictions, use procedures tocorrect,

control, ormitigate theconsequences ofthose abnormal conditions ofoperations:

A2.04 LossofExtraction Steam RO3.3SRO3.4 K/A2.2Equipment Control 2.2.22 Knowledge oflimiting conditions for operationsandsafety limits RO.3.4 SRO4.1 Theloss ofFeedwater heating duetothetrip of the FWHwill drive reactor power toabove thelicensed limit.

Peak powerinthis transient with nooperato ractionis just over102%power.

This would constitute aviolation ofour Operating License.

HC.OP-IO.22-0006 definesa5 minute averageof3904 MWthduring steady state operations as exceeding theLicensed Power Limit.

Taking the Immediate Operator Actions IAWeither AB.BOP-0001 or AB.RPV-0001 will prevent this violation.

2.CREWstarts SACSPumpBtoprovide cooling toEDGB,ORcross-connects toSACSLoopA,toprevent anEDGBemergency trip fromcooling related problems.

K/A295003 AA1.03Systems necessary toassure safeplant shutdown RO4.4SRO4.4 Thecontinued availability ofEDGBisrequired tomaintain thecapabilityto place theplant inacold shutdown condition.

IfEDGBbecomes inoperable:

(with EDGA currentlyinoperable),

bothloops of shutdown cooling will beinoperable andivill:

prevent placing andmaintaining the plant inacold shutdown condition; andtheinability tocool theSuppression Pool tomaintain temperatures less than 212F.Starting ofthis pump,orcross-connecting toSACSLoopA isrequired duetothefailure ofSACS Pump D.

This Critical Taskisvalid onlyifEDGBhas.been started.

3.BEFORECompensated RPVwaterlevel 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 astheyapply toREACTORLOWWATER LEVEL:

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

EA2.04 Adequate corecooling RO4.6SRO4.8 WhenReactor waterlevel cannot bemaintained above

-185" with injection totheRPV,adequate corecooling cannotbeassured (MSCRWL).

EOPsdirect action toinitiate emergency depressurization whenRPVwaterlevel reaches this value ifthere areinjection sources available.

Torestore adequate core

cooling, theCrewmust Emergency Depressurize andrestores level withlowpressure ECCS.

ES-401 Written Examination Outline FormES-401-1 Facility:

HC21-2 DateofExam:

02/21 ROK/ACategory Points SRO-Only Points Tier GroupK K

K K

K K

A A

A A

G Total A2 G*

Total 1

2 3

4 5

6 1

2 3

4 xw agewas 1

3 5

3

~

4 4 filWeA 1

20 4

3 7

1.Emergency A dd waAamm t

2 1

2 0 jdf@EE jAjj!jjjjj$

1 2 Agjjjj1!!f 1

7 2

1 3

Plant M

.. TC Evolutions Tier b

5 6

2 27 6

4 10 4

7 3 Totals j@gjjjjo W as 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 3

3 4

4 3

3 3

3 4

5 3

38 3

5 8

Totals 1

2 3

4 1

2 3

4 3.Generic Knowledge

& Abilities 10 7

Categories 2

3 3

2 2

2 1

2 Ensure that atleast twotopics fromevery applicable K/A category aresampled within eachtier oftheROand Note' 1'

SRO-only outline sections (i.e.,

except foronecategory inTier3oftheSRO-only

section, the"Tier Totals" in eachK/Acategory shall notbeless thantwo).

(One Tier 3radiation control K/Aisallowed ifitisreplaced bya K/Afromanother Tier3category.)

2.

Thepoint total foreachgroup andtier intheproposed outlinemust match that specified inthetable.

Thefinal point total foreachgroup andtier maydeviate by11fromthat specified inthetable basedonNRCrevisions.

Thefinal ROexammusttotal

75points, andtheSRO-only exammust total 25points.

3.

Systems/evolutions within eachgroup areidentified ontheoutline.

Systems orevolutions that donotapply at thefacility should bedeleted with justification.

Operationally important, site-specific systems/evolutions that are notincluded ontheoutline should beadded.

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

4.

Select topics fromasmanysystems andevolutions aspossible.

Sampleevery system or evolution inthe group before selecting asecond topic foranysystemorevolution.

5.

Absent aplant-specific

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

Use theRO andSROratings fortheROandSROonlyportions, respectively.

6.

Select SROtopics forTiers 1and2fromtheshaded systems andK/Acategories.

7.

Thegeneric (G)

K/AsinTiers 1and2shall beselected fromSection 2oftheK/Acatalog, butthetopics must berelevant totheapplicable evolution orsystem.

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

8.

Onthefollowing

pages, enter theK/Anumbers, abrief description ofeachtopic, thetopics' IRsforthe applicable license

level, andthepoint totals

(#)

foreachsystem andcategory.

Enter thegroup andtier totals for eachcategory inthetable above.

Iffuel-handling equipment issampled inacategory other than Category A2or G*ontheSRO-only exam,enter itontheleft sideofColumn A2forTier2,Group2.(Note 1doesnotapply.)

Useduplicate pagesforROandSRO-only exams.

9.

ForTier 3,select topics fromSection 2oftheK/Acatalog, andenter theK/Anumbers, descriptions, IRs,and point totals

(#)

onFormES-401-3.

Limit SROselections toK/Asthat arelinked to10CFR55.43.

G*

Thesesystems/evolutions mustbeincluded aspart ofthesample(as applicable tothefacility) when Generic Revision 3oftheK/Acatalog isusedtodevelop thesampleplan.

Theyarenotrequired tobeincluded when K/As using earlier revisions oftheK/Acatalog.

Thesesystems/evolutions maybeeliminated fromthesample(as applicable tothefacility) whenRevision 3

oftheK/Acatalog isusedtodevelop thesample plan.

ES-401 2

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

- Tier1Group1 EAPE#/Name Safety Imp K1 K2 K3 A1 A2 G

K/ATopic(s)

Q#

Function

..wee EA2.01

- Ability todetermine and/or interpret mW thefollowing asthey apply to 295026 Suppression Pool High

@ A$@hSUPPRESSION POOLHIGHWATER 4.2 76 Water Temp./5 TEMPERATURE:

Suppression pool water temperature Aljjjjl$

AA2.03

- Ability todetermine and/or 295016 Control Room gjjjjjjjjjljjjjj$interpret thefollowing asthey apply to 44 77 Abandonment

/7 me!!!!!l!!!'

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

CONTROL ROOMABANDONMENT Reactor ressure itli$@jidjj EA2.07

- Ability todetermine and/or interpret I

I I I I

I I

I I I I II 295037 SCRAMConditions

$50%WN thefollowing asthey apply toSCRAM Present andReactor Power ap CONDITION PRESENT ANDREACTOR XA 4.2 78 Above APRMDownscale or Ap POWERABOVEAPRMDOWNSCALE OR Unknown

/1

"" jAEA UNKNOWN:Containment NdEil conditions/isolations 295021 LossofShutdown jjjjjjjjjjjgjjjjjjjjjj 2.2.40

- Equipment Control:

Ability toapply 4.7 79 Coolina

/4

==!!!!!!!l!ij?ilii?l?l!!l==21 Technical Specificationsforasstem.

295001 Partial orComplete Loss 2.4.50

- EmergencyProcedures

/Plan:

Ability ofForced CoreFlowCirculation pmet7sy!C to verify systemalarm setpoints andoperate 4.0 80

/l#

e as w:m:%

controls identified inthealarm response

$3%)

MM manual.

E@d!l@ih 2.4.4 Emergency Procedure/Plan:

Ability to 295018 Partial orTotal Lossof recognhabnonnd inhons fonynent CCW/8 C *##

!P operatmg parameters that areentry level 4.7 81

@bgg conditions for emergency andabnormal WAAmeW!Wii o erating rocedures 600000 Plant Fire On-site

/8 ll@!

!D!!!

AA2.03

- Ability todetermine andinterpret WXA thefollowing asthey apply toPLANT FIRE 3.2 82

!!h@$@iM ONSITE:

Fire alarm EK1.01

- Knowledge ofthe operational bb!!Migg implications ofthefollowing concepts asthey 41 39 295024 HighDrywell Pressure

/

X s32kW apply toHIGHDRYWELL PRESSURE 5

MF@M Drywell integrity:

PlantS ecific EK1.03

- Knowledge oftheoperational 295037 SCRAMConditions A AjPC implications ofthefollowing concepts asthey Present andReactor Power as!!!s!!!!!!!!!!

!;!;!s!!s!;!xit apply toSCRAMCONDITION PRESENT X

Above APRMDownscale or Wl!!l!!!!!!l!!Ak!

ANDREACTORPOWERABOVEAPRM C

Unknown/1 DOWNSCALE ORUNKNOWN:

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

effects onreactor owerSBLC) gaGllEAlEK1.03

- Knowledge oftheoperational 295030 LowSuppression Pool AfA e implications ofthefollowing concepts asthey X

38 41 WaterLevel

/5

!M

+ apply toLOWSUPPRESSION POOL WATERLEVEL:Heatcaaci odjl!!iie!%A EK2.06

- Knowledge oftheinterrelations 295038 HighOff-site Release ilijf!!jjiMWAA!A between HIGHOFF-SITE RELEASE RATE X

x===

3.4 42 Rate/9

@g jjjjpgg andthefollowing:

Process liquid radiation m-"

monitoring sstem

..=.

AK2.02

- Knowledge oftheinterrelations 295003 Partial orComplete mjpijillfl3 between PARTIAL ORCOMPLETE LOSS X

41 43 LossofAC/6 pii!WGiE OFA.C.POWERandthefollowing:

P2lW@!$5 Emergency generators J%!!ji!!f!l!!llljij!!!!!ll!iti AK2.03

- Knowledge oftheinterrelations 600000 Plant Fire On-site

/8 X

!$!@!)i!!!$!!!$!ll!j[

between PLANTFIREONSITEandthe 2.5 44 WiPll!ljEEi$l?l?il followin

Motors WW AK3.02

- Knowledge ofthereasons forthe 295004 Partial orTotal Lossof j[

following responses asthey apply to X

/#

!A!;!!!!!5!d PARTIALORCOMPLETE 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 EmergencyandAbnormal PlantEvolutions

- Tier1Group1 EAPE#/Name Safety Imp K1 K2 K3 A1 A2 G

K/ATopic(s)

Q#

Function lifib!!!!!jl)!jjl?!j AK3.03

- Knowledge ofthereasons for 295001 Partial orComplete ATW)BlitijAilt thefollowing responses astheyapply to LossofForced CoreFlow X

EWW A PARTIAL ORCOMPLETE LOSSOF 2.8 46 Circulation

/1&4 GMlWiW FORCEDCOREFLOWCIRCULATION WiWlNlA Idle looflow ec

,4 AK3.02

- Knowledge ofthereasons for iids thefollowing responses astheyapply to M

GENERATOR VOLTAGE AND 700000 Generator Voltage and X

E0 W ELECTRIC GRIDDISTURBANCES:

3.6 47 Electric Grid Disturbances Actions contained inabnormal operating iiiilikhis ld!lAiAillJ procedure forvoltage andgrid "li@

fiifl!!iililiiiliiilliiiisiit disturbances.

$%jNEA1.03

- Ability tooperate and/or monitor thefollowing astheyapply to 295026 Suppression Pool High X

x n

. A SUPPRESSION POOLHIGHWATER 3.9 48 Water Temp./5 TEMPERATURE:

Temperature Niid monitorin

$!pAifjji;j AA1.07

- Ability tooperate and/or monitor 295023 Refueling Accidents X T" "iflil0 thefollowing astheyapply to 29 49 Cooling Mode/8 M P &!W REFUELING ACCIDENTS:Fuelpool coolin andcleanusstem EA1.05

- Ability tooperate and/or monitor 295025 HighReactor Pressure

/

the following astheyapply toHIGH 3.7 50 X

3 Egy$g3 REACTOR PRESSURE:

RCIC:Plant-NMAlliLiEb S ecific CAiBW1AA2.04

- Ability to determine and/or 295006 SCRAM/1

$$j(j interpret the following astheyapply to 4.1 51 SCRAM:Reactor ressure AA2.03

- Ability todetermine and/or 295005 MainTurbine Generator grAA!iajjjik interpret thefollowing asthey apply to Trip

/3 d@$@l3 MAINTURBINE GENERATOR TRIP :

3.1 52 WAiP Turbine valveosition AA2.01

- Ability todetermine and/or 295019 Partial orTotal Loss'of W

interpret thefollowing asthey apply to InstAir/8 AP

PARTIALORCOMPLETE LOSSOF 3.5 53 A NA INSTRUMENT AIR:Instrument air sstemressure AK2.02

- Knowledge ofthe interrelations between PARTIAL ORCOMI5LETE 295018 Partial orTotal Lossof X

m W +

LOSSOFCOMPONENT COOLING 3.4 54 CCW/8 WATERandthefollowing:

Plant a erations AA1.06

- Ability tooperate and/or monitor 295016 Control Room

[llllbl j@jthefollowing astheyapply toCONTROL 40 55 X

Abandonment

/7

?jk$!ifTM ROOMABANDONMENT:

Reactor water level EK2.12-Knowledge oftheinterrelations between REACTOR LOWWATER 295031 Reactor LowWater X

N A jpdNLEVELandthefollowing:

4.5 56 Level

/2 WMidili$ij5y Primary containment isolation s stem/NS4 AA2.02

- Ability todetermine and/or 295021 LossofShutdown

@QiVM interpret thefollowing astheyapply to Cooling

/4 dhAE LOSSOFSHUTDOWN COOLING 34 57 RHR/shutdown coolin sstemflow 2.4.18

- Emergency Procedures

/Plan:

295028 HighDrywell Temperature

/5

@l!jjlj!l@b Knowledge ofthespecific bases for 3.3 58

=*-

EOPs K/ACategory Totals:

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

- Tier1Group2 EAPE#/Name Safety Ki K2 K3 A1 A2 G

K/ATopic(s)

Imp. Q#

Function 295015 Incomplete SCRAM /1 btdj[AA2.01

- Ability todetermine and/or d@hpe interpret thefollowing asthey apply to 4.3 83 em MM INCOMPLETE SCRAM:Reactor power Am PA& 2.1.25

- Conduct ofOperations:

Ability to 295012 HighDrywell Temperature W QAs

/5 ag mterpret reference materials, such asgraphs,4.2 84 kjE curves,

tables, etc.

jjjj@jj

$!Gi AA2.02

- Ability todetermine and/or 295010 HighDrywell Pressure

/5 jj$lj

@fj??

interpret thefollowing asthey apply to 3.9 85 lEs&fid HIGHDRYWELLPRESSURE

Drywell

?$@M ressure AM$23 AK1.03

- Knowledge oftheoperational 295008 HighReactor Water Level Ndpj%

implications ofthefollowing concepts as 32 59 X

/2 pphE they apply toHIGHREACTORWATER q#

LEVEL:Feedflow/steam flowmismatch

$Wi

$@fk AK2.04

- Knowledge oftheinterrelations 295022 LossofCRDPumps/1 X

E NEW between LOSSOFCRDPUMPSandthe 2.5 60 followine: Reactor waterlevel

$5lM E@!jR AA2.01

- Ability todetermine and/or 295009 LowReactor WaterLevel

$@lj[

interpret thefollowing asthey apply to 4.2 61 gg gj@

LOW REACTOR WATERLEVEL:

Reactor waterlevel 295034 Secondary Containment j@j@@@

the following asthey apply toEA1.03

- Ability tooperate and/or monitor w=

=

Ventilation HighRadiation

/9 X 7 SECONDARY CONTAINMENT 4.0 62

$!j$E@@A VENTILATION HIGH RADIATION M!bW Secondary Containment Ventilation EA2.01

- Abilityto determine and/or 295032 HighSecondary j@jll@jjlljlj interpret the following as they applyto 38 63 Containment AreaTemperature

/5 AC NiMihHIGHSECONDARY CONTAINMENT AREATEMPERATURE:Area tem erature

$$@@iMR 2.1.31

- Conduct ofOperations:

Ability to 295020 Inadvertent Cont.

M@Pi locate control roomswitches,

controls, and Isolation

/5& 7

@b@6 indications, andtodetermine that they 4.6 64 WR correctly reflect thedesired lant lineu -

m EK2.03

- Knowledge ofthe interrelations 500000 HighCTMTHydrogen j@b abetween HIGHCONTAINMENT Cone.

/5 X

kW HYDROGEN CONCENTRATIONS and 3.3 65 fm y4; thefollowing:

Containment Atmosphere NdbWWE Control S stem we am K/ACategory Totals:

1 2

0 1 22% WE Group Point Total.:

7/3 agamwas

ES-401 4

FormES-401-1 HC21-2 Written Examination Outline Plant Systems

- Tier2Group1 K K K K K K A A A Imp System#/ Name A2 G

Q#

1 2 3 4 5 6 1 3 4

'" T W@ A2.08

- Ability to(a) predict the jjj$

impacts ofthefollowing onthe do MGMAVERAGEPOWERRANGE d

M MONITOR/LOCAL POWER

/$e 215005 APRM/LPRM A

+

j$:RANGEMONITORSYSTEM

&J and(b) based onthose predictions, 3.4 86 p5 useprocedures tocorrect,

control, j:g wgf ormitigate theconsequences of gg "QAthose abnom1al conditions:

Faulty A

A orerratic operation of detectors/systems A A2.01

- Ability to(a) predict the j@

impacts ofthefollowing onthe

AM D.C.ELECTRICAL 263000 DCElectrical w

APW DISTRIBUTION

and(b) based on Distribution x

3.2 87 ye w Wy those predictions, useprocedures to

correct, control, ormitigate the consequences ofthose abnormal

! conditionsoro erations:

Grounds 2.4.49

- Emergency Procedures

/

5 Plan: Ability toperform without 223002 PCIS/Nuclear Steam

1. 4 reference toprocedures those 4.4 88 xW Supply Shutoff be actions that require immediate

operation ofsystemcomponents E and controls.

2.4.11

- Emergency Procedures /

300000 Instrument Air m

72069 EA Plan:

Knowledge ofabnormal 4.2 89 Aw condition rocedures.

A 2.2.44

- Equipment Control:

Ability 3$bl$

tointerpret control room indications AjXbPW toverify thestatus andoperation of 4.4 90 218000 ADS

, :g we

asystem, andunderstandhow m

j:.

operator actions anddirectives M

WWeffect lant ands stemconditions.

sAe GP Kl.01

- Knowledge ofthe physical T$

Wh connections and/or cause-effect relationships between 218000 ADS X

WT Aj@WAUTOMATIC 4.0 1

DEPRESSURIzATION SYSTEM andthefollowing:

RHR/LPCI:

$1 M$2Plant-S ecific q;gs 2MTPK1.06

- Knowledge ofthe a&M

-.J physical connections and/or Ed WWcause-effect relationships 239002 SRVs X

m W-EMil between RELIEF/SAFETY 3.4 2

Mfjm my VALVESandthefollowing:

Drywell instrument air/

drywell pneumatics:

Plant-WW A$5S ecific

=

K2.01

- Knowledge ofelectrical 203000 RHR/LPCI:

Injection xam aa powersupplies tothefollowing:

3.5 3

X mys Mode Pums K2.01

- Knowledge ofelectrical 215003 IRM X

MA powersupplies tothefollowing:

2.5 4

IRMchannels/detectors

ES-401 4

FormES-401-1 HC212 Written Examination Outline Plant Systems

- Tier2Group1 K K K K K K A A A Imp A2 G

Q#

System#/Name 1 2 3 4 5 6 1

3 4 Rg@

QM K3.01

- Knowledge oftheeffect eC 262001 ACElectrical that aloss ormalfunction ofthe X

w GAA A.C.ELECTRICAL 3.5 5

Distribution m@ifDISTRIBUTION will haveon

$!!$ dedfollowin

Ma'or s stemloads K3.02

- Knowledge oftheeffect f that aloss ormalfunction ofthe w

UNINTERRUPTABLE POWER 2.9 6

262002 UPS(AC/DC)

X g!Gw SUPPLY(A.C./D.C.)

will have gp W

onfollowing:

Recirculation pump Ted om s eed:Plant-S ecific Wh WA K4.09

- Knowledge of

• W AW REACTOR WATERLEVEL 259002 Reactor WaterLevel CONTROL SYSTEMdesign 31 7

X A

CW Control feature(s) and/or interlocks which provide forthefollowing:

Sinleelement control AAjjAK4.05

- Knowledge of EU SHUTDOWN COOLING SYSTEM(RHR SHUTDOWN 205000 Shutdown Cooling X

AT W

COOLING MODE) design 3.6 8

feature(s) and/or interlocks which provideforthefollowing:

Reactor cooldown rate

@ik AM K5.01

- Knowledge ofthe "T

QAPoperational implications ofthe following concepts astheyapply 263000 DCElectrical X

@xT W

toD.C.

ELECTRICAL 2.6 9

Distribution ad4g%s!p DISTRIBUTION:

Hydrogen Al@I generation during battery f charin

@!S K5.05

- Knowledgeof the f operational implications of the 1

following concepts asthey apply 3.4 10 264000 EDGs X

pg SittoEMERGENCY

@@GENERATORS (DIESEL/JET) :

20 Parallelin A.C.owersources K6.04

- Knowledge oftheeffect F that aloss ormalfunction ofthe followin will haveonthe 9

28 11 212000 RPS X

mmEE MA REACTOR PROTECTION SYSTEM:D.C.electrical dia l2EAif distribution

@@k l@$K6.03

- Knowledge oftheeffect n

W that aloss ormalfunction ofthe 211000 SLC X

A%in 1

following will haveonthe 3.2 12

(@b STANDBYLIQUID CONTROL EA SYSTEM:A.C.ower A1.05

-Ability topredict and/or An siSjMis monitor changes inparameters associated with operating the 217000 RCIC X AieikiilhWiM REACTORCOREISOLATION 3.7 13 Q

COOLING SYSTEM(RCIC)

Q@@j$$controls including:

RCICturbine WE AV s eed gaM A1.04

- Ability topredict and/or

$$T y

monitor changes inparameters 400000 Component Coolmg X 938

$@ associated with operating the 2.8 14 Water s A CCWScontrols including:

Surge TankLevel

ES-401 4

FOrmES-401-1 HC21-2 Written Examination Outline Plant Systems

- Tier2Group1 K K K K K K A A A Imp System#/Name 1 2 3 4 5 6 1 3 4 A2 G

Q#

I@@

A2.11

- Ability to(a) predict the w A WWEimpacts ofthefollowing onthe STANDBYGASTREATMENT SYSTEM

, and(b) basedon 261000 SGTS

/WV pp those predictions, use 3.2 15 pjg procedures tocorrect,

control, or A

AiE mitigate theconsequences of those abnormal conditions or operations:

Highcontainment aw ressure Gj0 A2.01

- Ability to(a) predict the hspA Migbt:impacts ofthefollowing onthe

$jl)AVERAGEPOWERRANGE f

MONITOR/LOCAL POWER RANGEMONITOR SYSTEM m

we and(b) basedonthose 215005 APRM/LPRM Ai&&

=

2.7 16 m!!m predictions, useprocedures to d!E

%S

correct, control, ormitigate the consequences ofthose A abnormalconditions or Ap operations:

Powersupply W$1

jWip deraded A3.02

- Ability tomonitor automatic operationsofthe PRIMARY CONTAINMENT 223002 PCIS/Nuclear Steam Supply Shutoff

"'^

EiM ISOLATION 3.5 17 at X SYSTEM/NUCLEAR STEAM SUPPLYSHUT-OFF including:

Valve closures A3.01

- Abilityto monitor automatic operations ofthe 206000 HPCI M

X EW HIGHPRESSURECOOLANT 3.6 18 INJECTION SYSTEMincluding:

Turbine s eed:

BWR-2,3,4

$ A4.01

- Ability tomanually 300000 Instrument Air ATAE X MA operate and/or monitor inthe 2.6 19

!i5iEi$

control room:Pressure aues A4.06

- Ability tomanually 215004 Source RangeMonitor 421 X ha?g operate and/or monitor inthe 3.2 20 EA control room:

Alarms andlihts gj@j A4.11

- Ability tomanually 209001 LPCS X

=

operate and/or monitor inthe 3.7 21 WEEicontrol room:

S stemflow 2.1.30

- Conduct ofOperations:

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

$4 AP controls.

was

$3 K4.01

- Knowledge ofCCWS Egg re" design feature(s) andor 400000 Component Cooling X

interlocks which provide forthe 3.4 23 Water System (CCWS) following:

Automatic start of standbum A4.01

- Ability tomanually operate and/or monitor inthe 259002 Reactor Water Level X WE control room:

Allindividual 3.8 24 Control MEG Migg component controllers inthe el ME manualmode.

262001 ACElectrical

@[

$jg 2.1.20

- Conduct ofOperations:

Distribution AM TXL Ability tointerpret andexecute 4.6 25 a

$jD!Fib L

ren racedure stes.

ES-401 4

FormES-401-1 HC21-2 Written Examination Outline Plant Systems

- Tier2Group1 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) A3.02

- Ability tomonitor 261000 SGTS automatic operations ofthe 32 26

?

X

!A STANDBYGASTREATMENT Em il;i!$!s!!l!!!A SYSTEMincludin

Fanstart K/ACategory Totals:

2 2 2 3 2 2 2j3@j 3 4@@

Group Point Total:

26/5

ES-401 5

FormES-401-1 HC21-2 Written Examination Outline Plant Systems

- Tier 2Group2 K K K K K K A A A System#/Name A2 G

Imp Q 1 2 3 4 5 6 1 3 4 ns:x pW A2.03

- Ability to(a) predict the appimpacts ofthefollowing onthe 2%lM RODBLOCKMONITOR 17 g@

SYSTEM;and(b) basedon pgg ggygy those predictions, use 215002 RBM p$2 Qj@ procedures tocorrect, control,3.3 91

~7 tAM ormitigate theconsequences of m

$R2those abnormal conditions or

@D AA operations:

Lossofassociated T

RAA reference APRMchannel:

E BWR-3,4,5 2.4.31

- Emergency Procedures 290003 Control RoomHVAC W

!iiAlliex

/Plan:

Knowledeof p,

E TA annunciator

alarms, indications, 41 92 3.3.7.1

/ A i orresonseprocedures.

A1%

MitiA2.4.30

- Emergency Procedures

/Plan;Knowledge ofevents related tosystemoperation

/

Qjiki W%

statusthat mustbereported to 272000 Radiation Monitonng A ga WXL 4.1 93 5q m

internal organizationsor external agencies,suchasthe

/ :

state, theNRC,orthe i$M transmission s stemo erator.

K1.07

- Knowledge ofthe jj physical connections and/or 256000 Reactor CondensateX cause-effect relationships 2.9 27 between REACTOR L.

RihilCONDENSATE SYSTEM and MA

@hjkthefollowin

SJAE condenser K2.10

- Knowledgeof electrical 223001 Primary CTMTand X

,ga gy powersupplies tothefollowing:

2.7 28 Aux' Aa D

ellchillers:

Plant-S ecific l$FiAA K3.04

- Knowledge oftheeffect Agi that aloss ormalfunction ofthe 234000 Fuel Handling

. Ai:

FUELHANDLING EQUIPMENT X

gi 29 29 a

will haveonfollowing:

Reactor Equipment K3.03

@@ manualcontrol system:

Plant-S ecific K4.01

- Knowledge ofOFFGAS E SYSTEMdesignfeature(s) 271000 Off-gas X

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

Dilution of h droen asconcentration y@

K5.04

- Knowledge ofthe g"

operational implications ofthe e ag gpEAfollowing concepts astheyapply 230000 RHR/LPCI X

6@/+U NA toRHR/LPCI:

2.5 31 Torus/Pool Spray Mode TORUS/SUPPRESSION POOL SPRAYMODE:Evaporative coolin

. p M

K6.01

- Knowledge oftheeffect

$1 that alossormalfunction ofthe 216000 Nuclear Boiler Inst.

W AW followin will haveonthe X

=

3.1 32 oA NUCLEARBOILER 22

@W INSTRUMENTATION

A.C.

%33

"$M electrical distribution

ES-401 5

FormES-401-1 HC21-2 Written Examination Outline Plant Systems

- Tier2Group2 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 PWPA1.13

- Ability topredict and/or monitor changes inparameters associated with operating the 202001 Recirculation X Ap mde RECIRCULATION SYSTEM 3.1 33 em controls including:

Recirculation looptemperatures:

Plant-S ecific A2.05

- Ability to(a) predict the impacts ofthefollowing on theCONTROL RODAND 201003 Control Rodand WW mm

.DRIVE MECHANISM

and(b)

Drive Mechanism basedonthose predictions, use 4.1 34 procedures tocorrect,

control, 4

A:

ormitigate theconsequences of those abnormal conditions or C

o erations:

Reactor Scram

,,g p,, A3.01

- Ability tomonitor automatic operations ofthe 219000 RHR/LPCI:

RHR/LPCI:

X 3.3 35 Torus/Pool Cooling Mode TORUS/SUPPRESSION POOL COOLING MODEincluding:

Valve o eration Qj A

A4.03

- Ability tomonitor fs automatic operations ofthe

AWl ROD WORTH MINIMIzER 201006 RWM AiW X

SYSTEM (RWM) (PLANT 3.0 36 wijb SPECIFIC) including:

Latched egg j@M group indication:

P-Spec(Not-BWR6

. fif!hii 2.4.9

- Emergency Procedures

/

@!Vil Plan:

Knowledgeof low power /

WA shutdown implications in 204000 RWCU A!0accident (e.g.,

loss ofcoolant accident orloss ofresidual heat removal) mitiation strate ies.

K3.01

- Knowledge oftheeffect 4

AT + that aloss ormalfunction ofthe 201002 RMCS REACTORMANUAL X

3.4 38 CONTROL SYSTEMwill have 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 indicationstovalidate theresponse of 4.3 94 anotherindicator.

Abilitytoperform specific system and 2.1.23 integrated plant procedures during aIImodes 4.4 98 of lant o eration.

1.

Conduct Ability to evaluate plant performance and makeoperational judgements basedon 4.4 66 ofOperations217 operating characteristics, reactor

behavior, andinstrument inter retation.

2.1.32 Ability toexplainand apply all systemlimits 3.8 67 and recautions.

Subtotal WEW2 MD 2

Knowledge ofthe process for controlling 3.3 95 2.2M temora desinchanes.

Knowledge oftheprocess for conducting 3.6 99 2.2.7 s ecial orinfre uenttests.

2.2.12 Knowledge ofsurveillance procedures.

3.7 68 2

Equipment Ability todetermine theexpected plant Control 2.2.15 configuration using design andconfiguration 3.9 69 control documentation, suchasdrawings, line-u s,ta-outs, etc.

Ability torecognize systemparameters 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 workpermit R'adiation 2.3.7 requirements during normal orabnormal 3.5 70 conditions.

Control Knowledge ofRadiological Safety Procedures pertaining tolicensed operator

duties, suchasresponse toradiation monitor3.4 71 2.3.13alarms, containment entry requirements, fuel handling responsibilities, access tolocked hihradiation

areas, alininfilters, etc.

ES-401 Generic Knowledge andAbilities Outline(Tier 3)

FormES-401-3 Knowledge ofradiation orcontainment 2.3.14hazards that mayarise during

normal, 3.4 75

abnormal, oremergency conditions or activities.

Subtotal Ed 3 /@k[

1 KnowledgeofSRO.responsibilities in 2.4.40 4.5 97 emerenc lanimlementation.

2.4.6 Knowledge ofEOPmitigation strategies.

4.7 100 4'

Knowledge oflocal auxiliary operator tasks Emergency 2.4.35during emergency andtheresultant 3.8 72 Pocedures

/

o erational effects.

2.4.28 Knowledge ofprocedures relating toa 3.2 73 securi event.

Subtotal WA 2

.. j$

2 Tier 3Point Total

$AA 10 JRj[7

ES-401 Record ofRejected K/A's FormES-401-4 RandomSelected Tier / Group ReasonforRejection K1.02

- Knowledge ofthephysical connections and/or cause-effect relationships between RELIEF/SAFETY VALVESandthe following:

SPDS/ERIS/CRIDS/GDS:

Plant-Specific There isnospecific physical connection to 2/1(#2) 239002/K1.06 SPDS/ERIS/CRIDS/GDS with acause-effect relationship for SRVs.Nolicense level question canbewritten forthis specific K/AforSRVs.

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/A1.04Thereisnopressure setpoint orvalue fortheCCWsystems 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 ofplant operation.

2/1(#21) 209001/A4.11Thereisnoreference totheCoreSpray system intheintegrated procedures atalevel foralicense examquestion.

Randomly reselected:

Ability tomanually operate and/or monitor inthecontrol room:System flow.

2.2.38

- Equipment Control:

Knowledge ofconditions and limitations inthefacility license.

2/1(#22) 211000/

2.1.30 ThisK/Areferences TechSpecswhichisattheSROlevel.

Randomly reselected:

Conduct ofOperations:

Ability tolocate andoperate components, including local controls.

A4.09

- Ability tomanually operate and/or monitor inthecontrol room:

TDRFPlockout reset:

TDRFP 2/1(#24) 259002/A4.01Thereisnolockout parameter fortheRFP'satHopeCreek.

~

Randomly reselected:

AIIindividual 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 alicense level question with apurpose ofasystem.

Toolowofacognitive level question.

Randomly reselected:

Ability tointerpret andexecute procedure stes.

A1.05

- Ability topredict and/or monitor changes inparameters associated with operating theSTANDBYGASTREATMENT SYSTEM controls including:

Primary containment oxygen level:

Mark-l&II 2/1(#26) 261000/

A3.02 There isnoOxygenparameter that directly interfaces withthe FRVS system.

Randomly reselected:

A3.02

- Ability tomonitor automatic operations of the STANDBY GASTREATMENT SYSTEM including:

Fan start K3.02

- Knowledgeof the effect that aloss ormalfunction ofthe REACTORMANUAL CONTROL SYSTEMwill haveonfollowing:

Rodblock monitor:

Plant-Specific 2/2(#38) 201002/

K3.01 Anymalfunction orinoperability of the RMCSwouldnot recognize anyinput fromtheRBM.

Cannot write alicense level question without plausible distractors.

Randomly selected:

K3.01-Ability tomove control rods.

EK1.06

- Knowledge oftheoperational implications ofthe following concepts astheyapply toSCRAMCONDITION PRESENTANDREACTOR POWERABOVEAPRM DOWNSCALE ORUNKNOWN:Cooldown effects onreactor power.

1/1(#40) 295037/

EK1.03 Acooldown oftheRPVprior tobeing shutdown under all conditions wouldnotbeallowed IAWemergency operating procedures.

Randomly reselected:

Boron effects onreactor power(SBLC).

EK2.12 Knowledge oftheinterrelations between HIGHOFF-SITERELEASERATEandthefollowing:

Feedwater leakage control:

BWR-6 TherearenoHopeCreekprocedures thatreference Feedwater 1/1(#42)295038/

EK2.06 leakage control with Offsite Release.

Cannot write alicense level question forthis K/A.

Randomly reselected:

Process liquid radiation monitoring system

ES-401 RecordofRejected K/A's FormES-401-4 AK3.01

- Knowledge ofthereasons forthefollowing responses astheyapply toPARTIAL ORCOMPLETE LOSSOFD.C.

POWERLoadshedding 1/1(#45) 295004/

AK3.02 Thereisnoautomatic "load shedding" duetoalossofD.C.Load shedding occurs fromaloss ofA.C.

Randomly reselected:

Groundisolation/fault determination AA1.07

- Ability tooperate and/or monitor thefollowing asthey applytoREFUELINGACCIDENTS

Standby gas treatment/FRVS 1/1(#49)295023/

AA1.02 The above concept(K/A) issimilar toQuestion

1. 26which would cause "Double Jeopardy"ontheexam.

Randomly reselected:

Fuelpool cooling andcleanup system AA2.01

- Abilityto determine and/or interpret thefollowing as theyapply toSCRAM :Reactor power 1/1(#51) 295006/

AA2.04 L.O.D foraquestion onwhat happens toreactor powerona scram(power

lowers, APRMs downscale) wouldbe1.

Randomly reselected:

Reactorpressure 2.4.6

- Emergency Procedures

/Plan:

Knowledge ofEOP mitigation strategies.

1/1(#58) 2950282.4.18 EOPmitigation strategies areattheSROlevel due toselection ofEOPprocedures andactions within thelegsofthe EOP procedures tosatisfy themitigation strategy.

Randomly selected:

Knowledge ofthespecific basesfor EOPs.

2.4.41-Emergency Procedures

/Plan:

Knowledge ofthe emergency action level thresholds andclassifications.

TherearenoECG/classifications fortheInstrument AirSystem IAWtheHopeCreekEALsandRALs.

2/1(#89) 300000 2.4.11 Randomly reselected:

Knowledge ofabnormal condition procedures.

ES-401 RecordofRejected K/A's FormES-401-4 A2.01-Ability to(a) predict theimpacts ofthefollowing onthe RODBLOCKMONITOR SYSTEM;and(b) basedonthose predictions, useprocedures tocorrect,

control, ormitigate the consequences ofthose abnormal conditions oroperations:

Withdrawal ofcontrol rodinhighpowerregion ofcore:

BWR-3,4,5 2/2(#91) 215002/

A2.03 There isnoprocedure that directly addresses ormitigates the consequences ofacontrol rodwithdrawal inthehigher power region ofthecore.

ThisismoreofaGFEStypeK/A.

Randomly reselected:

Lossofassociated reference APRM channel:

BWR-3,4,5 Loss ofassociated reference APRMchannel:

BWR-3,4,5 Lossof associated reference APRMchannel:

BWR-3,4,5 Lossof associated reference APRMchannel:

BWR-3,4,5 2.4.26 Knowledge offacilityprotection requirements, including fire brigade and portable firefighting equipment usage.

Thereisnofire brigade (separate fire department) atHope 3/4(#97) 2.4.40 Creek.

Cannot writeaSRO license level question tothis K/A.

Randomly reselected:

Knowledge ofSROresponsibilitiesin emergency plan implementation.

.