ML21075A104

Draft Written Examination and Operating Test Outlines (Folder 2)

ML21075A104
Person / Time
Site:	Hope Creek
Issue date:	03/09/2021
From:	Public Service Enterprise Group
To:	Todd Fish Operations Branch I
References
EPID L-2021-OLL-0001
Download: ML21075A104 (25)

Text

Appendix D

Scenario Outline FormESD-1 Facility: X Scenario No.: 1 Op-Test No.:

1 Examiners:

Operators:

Initial Conditions:=79%

power. BRFPTinRecirc Turnover:

Critical Tasks:

Raise Powerwith Recirculation Pumps 1

m R

Ea@uakem) l 2

PC07A C

Trip ofSSWPump(TS) 3 QQ09 C

MSLRMSChannel AFails upscale (TS) 4 RM01A I

Inskumenwne

&emn WweH 5

RR31A1 I

AM 6

RP06 M

IAukInWaknfaHure 7

HP06E C

.' 8 CU11B C

AutoIsdation FaHure E

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

Appendix D

Scenario Outline FormESD-1 Facility:

Scenario No.: 2 Op-Test No.:

1 Examiners:

Operators:

Initial Conditions:

100%Power Turnover:

RPSMGSet1BG401 has anoisybearing.

Transfer RPSBusBPower to

- T its Alternate Supply inaccordance with HC.OP-SO.SB-0001.

Critical Tasks:

1 N/A N

Transfer

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

ReducePowerto95%

n 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

PC03E I

A/CChannel InitiationFailures 8.

ET052 C

KL-HV-5147 Failure toClose x

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

Appendix D

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

1' Examiners:

Operators:

Initial Conditions:

Turnover:

Critical Tasks:

Leam 1

FW12B R,C Inae en System Adua@n W

2 SL03A C

3 ED11A I

ssMsRe her 4

EG12 M

DGO3B AubmadFaHumMNs 5

C DG04B RCICTrip onOverspeed 6

. RC01 C

SACSPumpTrip 7

QQ15 C

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

ES301 Administrative TopicsOutline FormES-3011 Facility: M DateofExamination:2/15/21 Examination Level:

RO 2 SRO D Operating TestNumber:

1 Administrative Topic (seeNote)

Type Describe activity tob'e performed 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 bfOperations 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.

ES-301 Administrative Topics Outline FormES-301-1

,J EmergencyPlan N/A NOTE:AIIitems (five total) are required forSROs.ROapplicants require only four items unless they areretaking only the administrative topics (which would require all five items).

• TypeCodesandCriteria:

(C)ontrol room,(S)imulator,orClass(R)oom (D)irect from bank(53forROs;s4forSROsandROretakes)

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

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

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

2/15/21 Examination Level:

RO C SRO @

Operating TestNumber:

1 Administrative Topic (seeNote)

Type Describe activity tobeperformed Code*

PERFORM theShift Manager review oftheOP-AA-105-102, Attachment 2,foranSROlicense

' Conduct ofOperations renewal fortheControl RoomSupervisor D,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, overtimelimitations, etc.

Complete DailySurveillance log Conduct ofOperations Task Standard:

Operator implements thelogat the beginning of thedaybycompleting Attachment 1,Section A,ofHC.OP-DLzz-0026 P,R andidentifies attachments requiredIAWthe answer

.key KA-2.1.18

- Ability tomake

accurate, clear, andconcise,

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

Youhave been presented with theWCDforIndependent 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 LoopAInjection Header.

Determine any D,R required actions andRECORD thembelow 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 TheECGToDetermine 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 withEP-HC-111-101.

KA2.4.38

-Ability totakeactions called forin thefacility emergency

plan, including

[supporting oracting asemergency coordinator ifreuired.

NOTE:Allitems (five total) arerequired forSROs.

ROapplicantsrequire only fouritems unless they areretaking only theadministrative topics (which would require all fiveitems).

• TypeCodesandCriteria:(C)ontrol

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

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

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

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

M DateofExamination:2/15/21 Exam Level:

RO 2 SRO-ID SRO-U O Operating TestNumber:

1 Control Room Systems:* 8forRO,7for SRO-1, 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.Place HPCIinfull flowTest Operation c.Place RCICinservice fromtheRSP S,D,A,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

1 In-Plant Systems:*

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

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

D,R 1

1

' Shift in-service CRDflowcontrol valves D,E 3

k.ResondtoaFailed O enSRV AllROandSRO-1control room(and in-plant) systems mustbedifferent andservedifferent safety functions, all five SRO-Usystems mustserve different safety functions, andin-plant systems and functions mayoverlap those tested inthecontrol room.

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

/2-3 (C)ontrol room (D)irect frombank s9/s8/54 (E)mergency orabnormal in-plant a1/21/21 (EN)gineered safety feature a1/21/h1(control roomsystem)

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

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

Facility:

M DateofExamination:2/15/21 ExamLevel:

RO C SRO-I2 SRO-UO Operating TestNumber:

1 Control Room Systems:" 8forRO,7forSRO-1, 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 flow Test Operation c.Place RCICinservice fromtheRSP S,D,A,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

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.Respond toaFailed O enSRV AllROandSRO-Icontrol room(and in-plant) systems mustbedifferent andserve different safety functions, all five SRO-Usystems mustserve different safety functions, andin-plant systems and functions mayoverlap those tested inthecontrol room (A)ltemate 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) 2 2/22/21 (P)revious 2exams 5 3/s3/s2(randomly selected)

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

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

HC21-2 DateofExam:

02/21 ROK/ACategoryPoints SRO-OnlyPoints.-

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 I

3 5

3 EMA@

4 4

V 1

20 4

3 7

1.Emergency T"ECL"'

T.TL 2

1 2

0 A@U1 2 i!jdj@

1 7

2 1

3 Evolutions Tier 7

3 16 5

6 A 2 27 6

4 10 4

Totals ggj$gg jagpp 1

2 2

2 3 2 2

3 2

2 4

2 26 2

3 5

2.

'~

-'C Plant 2

1 1

2 1

1 1

1 1

1 1

1 12 0

1 2

3 Systems Tier 3

3 4

4 3

3 4

3 3

5 3

38 3

5 8

Totals 1

2 3

4 1

2 3

4 3.GenericKnowledge&Abilities 10 7

Categories 2

3 3

2 2

2 1

2 Note' 1'

Ensure that atleast twotopics fromevery applicable K/A category aresampled within eachtier oftheROand 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 Tier 3category.)

2.

Thepoint total foreachgroup andtier intheproposed outlinemust match that specified inthetable.

Thefinal point total foreachgroupandtier maydeviate byt1fromthat specified inthetable basedonNRCrevisions. --"

Thefinal ROexammusttotal

75points, andtheSRO-only exam must 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 groupbefore selecting asecond topic foranysystemorevolution.

5.

Absent aplant-specific

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

Use theRO andSROratings fortheROandSRO-only

portions, 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 thanCategory A2or G*ontheSRO-only exam,enter itontheleft side ofColumn A2forTier 2,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, These systems/evolutions mustbeincluded aspart ofthesample(as applicable tothefacility) when Generic Revision 3oftheK/Acatalog isusedtodevelop thesample plan.

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 g@@@EA2.01

- Ability todetermine and/or interpret 295026 Suppression Pool High

@@@thefollowing asthey apply to RANW SUPPRESSION POOLHIGHWATER 4.2 76 Water Temp.

/5 jjj@j TEMPERATURE:

Suppression pool water EAjlifE!!!!!llin temperature

!!!lj!!!

!!!!W!!!!!!!!W AA2.03Ability todetermine and/or 295016 Control Room j@lll$!lW interpret thefollowing asthey apply to 44 77 Abandonment

/7

!jll==!!!!!l!!i

!!!!!T[

CONTROL ROOMABANDONMENT m!a!!!E!!!!!!!!!!!l;lj!!!!!ll!ill[l!!!!!!!!!!!!

Reactor ressure Ell)jiC!l%jjil!!!!!!!!!!!!!EA2.07Ability todetermine and/or interpret 295037 SCRAMConditions f!!!l?2@jj!l$

thefollowing asthey apply toSCRAM Present andReactor Power mm!!!ij!!jiM!!!!!iG$ CONDITION PRESENT ANDREACTOR 78 AboveAPRMDownscale or

@j@A POWERABOVEAPRMDOWNSCALE OR 4.2 Unknown

/1 gAymn UNKNOWN:Containment WAjjE)Al[i?l4 conditions/isolations 295021 LossofShutdown jjjjgg 2.2.40

- Equipment Control:

Ability toapply 47 79 Cooling

/4

!liyi!M1WA Technical Specificationsforasystem.

295001 Partial orComplete Loss jifil;ji!!!!!l!!!!!!!!!!2!!i jjjj 2.4.50

- Emergency Procedures

/Plan:

Ability ofForced CoreFlowCirculation il!!!!!jgjjjjj[to verify systemalarm setpoints andoperate 4.0 80

/1& 4 6,wigjpf controls identified inthealarm response i!@!B!!!!

manual.

TTj!WE!AlW 2.4.4 Emergency Procedure/Plan:

Ability to 2950I8Partial orTotal Lossof

@@p[

recognizeabnormal indications for system CCW/8 pgj operating parameters that areentry level 4.7 81 ex conditions for emergency andabnormal Dhjib o erating procedures 600000 Plant FireOn-site

/8 j@l@!% AA2.03Ability todetermine andinterpret e!j!ME iW!2!E thefollowing asthey apply to PLANT FIRE 3.2 82 ONSITE:

Fire alarm jjjjf$fjpe EKl.01Knowledge ofthe operational Am e@implications ofthefollowing concepts asthey

^

295024 HighDrywell Pressure

/

5

@lA W!MilWapply toHIGHDRYWELLPRESSURE 41 39 X

Ed!;iM!(

D ell inteo i :Plant-S ecific 42j!NE!:li:l!2E EK1.03

- Knowledge oftheoperational 295037 SCRAMConditions

@@j![ implications ofthefollowing concepts asthey Present andReactor Power hy jjpQapply toSCRAMCONDITION PRESENT 4.2 40 X

AboveAPRMDownscale or ag$pm ANDREACTOR POWERABOVEAPRM Unknown

/1 499g lllWl!

effects onreactor ower(SBLC) g!?!j?

W EK1.03Knowledge oftheoperational 295030 LowSuppression Pool l$$

6lhe implications ofthefollowing concepts asthey Water Level

/5 W$12 apply toLOWSUPPRESSION POOL 3.8 41 X

AE WATERLEVEL:Heatcaacity AtWAAllhlli:

EK2.06Knowledge oftheinterrelations 295038 HighOffsite Release l!!!!!!!!!DR 1b between HIGHOFF-SITE RELEASE RATE 3.4 42 X

Rate/9 jil!ll!ljj!;l!jlAl!jG Eg andthefollowing:

Process liquid radiation

$216AlEl!!121 monitorin system WMWEAK2.02Knowledge oftheinterrelations 295003 Partial orComplete MEETSbetween PARTIAL ORCOMPLETE LOSS LossofAC/6 p@j@;!

Q OFA.C.POWER andthefollowing:

4.1 43 X

Emeroency enerators

~ews

AK2.03Knowledge oftheinterrelations 600000 Plant Fire On-site

/8 X

!j!jl&

between PLANTFIREONSITEandthe 2.5 44 sidfollowing:

Motors MB $4!kj!l.l!!!!!!!!!!l!ll AK3.02

- Knowledge ofthereasons forthe 295004 Partial orTotal Lossof Q

following responses asthey apply to X

""W PARTIALORCOMPLETE LOSSOFD.C.

2.9 45 DCPwr/6 l!@

POWER:Ground isolation/fault W;$

WA!l!!i?

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 pj$NEAggAK3.03

- Knowledge ofthereasons for 295001 Partial orCornplete

$p@@@

thefollowing responses astheyapply to LossofForced CoreFlow X

NM WWPARTIAL ORCOMPLETELOSSOF 2.8 46 Circulation

/1&4 4ADAMil FORCEDCOREFLOWCIRCULATION Idle looflow P AK3.02

- Knowledge ofthereasons for 4$@C!l0l@f thefollowing responses astheyapply to

• C GENERATOR VOLTAGEAND 700000 Generator Voltage and X

Electric Grid Disturbances Egg AM ELECTRIC GRIDDISTURBANCES:

3.6 47 Actions contained inabnormal operating procedure forvoltage andgrid s disturbances.

WW EA1.03

- Ability tooperate and/or monitor 295026 Suppression PoolHigh h@iSl/ig thefollowing astheyapply to X

WW&

b SUPPRESSION POOLHIGHWATER 3.9 48 WaterTemp.

/5

/:-

..m TEMPERATURE:

Temperature Mi@j% ?jMihiki% monitorin 6 AA1.07

- Ability tooperate and/or monitor 295023 Refueling Accidents thefollowing astheyapply to X

29 49 Cooling Mode/8 REFUELING ACCIDENTS:Fuelpool coolin andcleanus stem pggg EA1.05

- Ability tooperate and/or monitor 295025 HighReactor Pressure

/

M WjEEthe following astheyapply toHIGH 3

MAA@h REACTOR PRESSURE:

RCIC:Plant-3.7 50 X

S ecific

' AA2.04

- Ability to determine and/or 295006 SCRAM/1

@jj[

interpret the following astheyapply to 4.1 51 wwmWMSCRAM:Reactor ressure ppp@@AA2.03

- Ability todetermine and/or 295005 MainTurbine Generator BjjjppQ interpret thefollowing as they applyto 3.1 52 Trip

/'3

$3r@

@@MAINTURBINE GENERATOR TRIP :

M Turbine valveosition as aARWAA2.01

- Ability todetermine and/or interpret thefollowing asthey apply to 295019 Partial orTotal Lossof Inst.

Air/8 27 A PARTIAL ORCOMPLETELOSSOF 3.5 53 MS%AACINSTRUMENT AIR:Instrument air gpAidiW s stemressure B@R@@!ji; AK2.02

- Knowledge oftheinterrelations between PARTIALORCOIl/IPLETE 295018 Partial orTotal Lossof X

AAE LOSSOFCOMPONENT COOLING 3.4 54 CCW/8 A2WW WATERandthefollowing:

Plant assmm o erations PM WA AA1.06

- Ability tooperate and/or monitor X $QjQN thefollowing astheyapply toCONTROL 40 55 295016 Control Room

@iit%db ROOMABANDONMENT:

Reactor water Abandonment

/7 level EK2.12-Knowledge oftheinterrelations mp%

between REACTOR LOWWATER

- " m$b 295031 Reactor LowWater X

w LEVELandthefollowing:

4.5 56 Level

/2 AA Primary containment isolation em AWG@Ws stem/NS4

@@j@ AA2.02

- Ability todetermine and/or 295021 LossofShutdown ppWjpA interpret thefollowing astheyapply to 34 57 y8 gj@RHR/shutdown coolin s stem flowimAA QMLOSSOFSHUTDOWN COOLING:

Cooling

/4

+

m 2.4.18

- Emergency Procedures

/Plan:

295028 HighDrywell hp4:A@Ein jjjji Knowledge ofthespecific basesfor 3.3 58 Temperature

/5 q,gg as EOPs j:

K/ACategory Totals:

3 5

3 4 $(j$5p Group Point Total:

20/7 wd w-

~

ES-401 3

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

- Tier1Group2 EAPE#/Name Safety K1 K2 K3 A1 A2 G

K/ATopic(s)

Imp. Q#

Function AA2.01

- Ability todetermine and/or 295015 Incomplete SCRAM /1

,--c@lA interpret thefollowing asthey apply to 4.3 83 7MftBA INCOMPLETE SCRAM:Reactor ower

$9 WM 2.1.25

- Conduct ofOperations:

Ability to 295012 HighDrywell Temperature E

q%e

/5 wp ga mterpret reference materials, such asgraphs,4.2 84

$$iE%$k

curves, tables, etc.

E E@ AA2.02

- Ability todetermine and/or 295010 HighDrywell Pressure

/5 QgilE interpret thefollowing asthey apply to An yyg! HIGHDRYWELLPRESSURE

Drywell 3.9 85 pressure AK1.03

- Knowledge oftheoperational 295008 HighReactor WaterLevel X

? implications ofthefollowing concepts as 3.2 59

/2 they apply toHIGHREACTORWATER LEVEL:Feedflow/steam flowmismatch A;@ j$A AK2.04

- Knowledge oftheinterrelations 295022 LossofCRDPumps/1 X

WE W;6 between LOSSOFCRDPUMPSandthe 2.5 60 followin :Reactor waterlevel AA2.01

- Ability todetermine and/or 295009 LowReactor Water Level Mipe mterpret thefollowing astheyapply to 4.2 61 a

m m g 2 LOW REACTOR WATERLEVEL:

@@ijidi$@dReactor waterlevel EA1.04

- Ability tooperate and/or monitor 295034 Secondary Containment Aff$Ap the following asthey apply to Ventilation HighRadiation

/9 X

T dh SECONDARY CONTAINMENT 4.1 62

@@y PilA SBGT/FRVS:

Plant-S ecific7 wA VENTILATION HIGH RADIATION E!@WW@if EA2.01

- Abilityto determine and/or 295032 HighSecondary JPjjjt interpret the following as they apply to

@22!$!E HIGHSECONDARY CONTAINMENT 3.8 63 Containment AreaTemperature

/5

" E ENA AREATEMPERATURE:Area tem erature 2.1.31

- Conduct ofOperations:

Ability to 295020 Inadvertent Cont.

pppyglocate control roomswitches, controls, and 4.6 64 Isolation

/5& 7 ad y A indications, andtodetermine that they TEM A$ilk correctl reflect thedesired lant lineu,

j@ $R EK2.03

- Knowledge ofthe interrelations 500000 HighCTMTHydrogen

$j@@

$jybetween HIGHCONTAINMENT Conc.

/5 X

^

m 4

HYDROGENCONCENTRATIONS and 3.3 65

$$@@thefollowing:

Containment Atmosphere P

E Control S stem La K/ACategory Totals:

1 2

0 1 jj2/((

j/1jj GroupPoint Total:

7/3

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

[ A2.08

- Ability to(a) predict the jEimpacts ofthefollowing onthe AVERAGEPOWERRANGE d MONITOR/LOCAL POWER WE RANGEMONITORSYSTEM:

215005 APRM/LPRM xe 91 and(b) based onthose predictions, 3.4 86 A

di useprocedures tocorrect,

control, ormitigate theconsequences of those abnormal conditions:

Faulty M

orerratic operation of AAAdetectors/systems A2.01

- Ability to(a) predict the impacts ofthefollowing onthe D.C.ELECTRICAL 263000 DCElectrical xmn DISTRIBUTION

, and(b) based on Distribution cin 3.2 87 mps those predictions, useprocedures to

correct, control, ormitigate the m

ag consequences ofthose abnormal "M

th conditions oro erations:

Grounds A2.4.49-Emergency Procedures

/

Plan: Ability toperform without 223002 PCIS/Nuclear Steam AA reference toproceduresthose 4.4 88 Supply Shutoff 33@! A actions thatrequire immediate Up b

operation ofsystemcomponents

> andcontrols.

300000 Instrument Air Ak pq 2.4.11

- Emergency Procedures /

w WdKPlan:

Knowledge ofabnormal 4.2 89 72069 2

Ps xwa sex condition rocedures.

2.2.44

- Equipment Control:

Ability A

pgy tointerpret control room indications 218000 ADS j@

j@ toverify thestatus andoperation of 4.4 90 At

asystem, andunderstandhow

+

MW operator actions anddirectives 2Wl?

$$!Meffect lant andsystem conditions.

WA Kl.01

- Knowledge ofthephysical mm W4A W@

connections and/or cause-effect 221Aa m

relationships between 218000 ADS X

A32AUTOMATIC 4.0 1

ed;a

!AE A DEPRESSURIzATION SYSTEM t@

8% andthefollowing:

RHR/LPCI:

Plant-S ecific K1.06

- Knowledge ofthe

)physical connections and/or J

@A cause-effect relationships 239002 SRVs X

WE WA between RELIEF/SAFETY 3.4 2

m VALVESandthefollowing:

de pp Drywell instrument air/

drywell D$!

0 pneumatics:

Plant-e S ecific K2.01

- Knowledge ofelectrical 203000 RHR/LPCI:

Injection X Mode qgjp powersupplies tothefollowing:

3.5 3

Pums K2.01

- Knowledge ofelectrical 215003 IRM X

a m

, =A powersupplies tothefollowing:

2.5 4

i/Ek di#WIRMchannels/detectors

ES-401 4

FormES-401-1 HC212 Written Examination Outline Plant Systems

- Tier 2Group1 K K K K K K A A A imp A2 G

Q#

System

1. /Name 1 2 3 4 5 6 1 3 4 B@

WWK3.01

- Knowledge oftheeffect

%A that aloss ormalfunction ofthe 262001 ACElectrical Distribution WA A.C.ELECTRICAL 3.5 5

X DISTRIBUTION will haveon followin

Ma'or s stemIoads F

NAA K3.02

- Knowledge oftheeffect

$A DE@

that aloss ormalfunction ofthe 262002 UPS(AC/DC)

X N"

W WW UNINTERRUPTABLE POWER 2.9 6

SUPPLY(A.C./D.C.)

will have onfollowing:

Recirculation pump 9 s eed:Plant-S ecific AS K4.09

- Knowledge of BR REACTORWATERLEVEL 259002 Reactor WaterLevel Widil

1. R CONTROL SYSTEMdesign X

mm 31 7

Control f;

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

L Sinleelement control M K4.05

- Knowledge of SHUTDOWN COOLING

@i@if SYSTEM(RHR SHUTDOWN 205000 Shutdown Cooling X

Q QlMif COOLING MODE) design 3.6 8

feature(s) and/or interlocks Ajityji) Reactor cooldown ratey y

which provideforthefollowing:

K5.01

- Knowledge ofthe operational implications ofthe following concepts astheyapply 263000 DCElectrical X

A A

toD.C.

ELECTRICAL 2.6 9

Distribution m 7 WW DISTRIBUTION:

Hydrogen 5WWgeneration during battery charin 5 K5.05

- Knowledge of the A

operational implications of the nah 264000 EDGs X

ye following concepts asthey apply 3.4 10 toEMERGENCY diag GENERATORS (DIESEL/JET)

WWA Mii@Parallelin A.C.owersources u

K6.04

- Knowledge oftheeffect

@d

, that aloss ormalfunction ofthe followin will haveonthe 212000 RPS X

2.8 11 REACTORPROTECTION SYSTEM:D.C.electrical distribution K6.03

- Knowledge oftheeffect C

AW thatalossormalfunction ofthe 211000 SLC X

gp t following will haveonthe 3.2 12 wA

? STANDBYLIQUID CONTROL SYSTEM:A.C.ower fL Tl0 A1.05

- Ability topredict and/or S$W

@ASmonitor changes inparameters associated with operating the 217000 RCIC X WWE MA REACTORCOREISOLATION 3.7 13 m

wA COOLING SYSTEM(RCIC) smia mm controls including:

RCICturbine s eed A1.04

- Ability topredict and/or 400000 Component Coohng X s

%W monitor changes inparameters f

associated with operating the 2.8 14 Water CCWScontrols including:

Surge TankLevel

ES-401 4

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

- Tier2Group1 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""[

Tjij[!?

A2.11

- Ability to(a) predict the s

i E

E impacts ofthefollowing onthe

!-o MM STANDBY GASTREATMENT

[jjlj(!!j@$lll)jljlll!!j SYSTEM;and(b) basedon j@!@p procedures tocorrect,

control, or jjf!j those predictions, use 3.2 15 261000 SGTS

=A Wiijaisip!;

mitigate theconsequences of pl!0!A3)E those abnormal conditi,ons or

$Q fipi?i!

operations:

Highcontainment xm ressure A&

jjE A2.01

- Ability to(a) predict the A

impacts ofthefollowing onthe jan

$ AVERAGEPOWERRANGE Q$1MONITOR/LOCAL POWER Mi3iW RANGEMONITOR SYSTEM; 215005 APRM/LPRM

1l1lll jp and(b) based onthose 2.7 16 me

=.

predictions, useprocedures to

correct, control, ormitigate the ddA consequences ofthose

!!!iliiilii!!!!!!!!!!!!!!!!!!

%bj abnormalconditions or hC!!

j Aij;!ll?A operations:

Powersupply FM fif!!!!!!;!An deraded Elyid A3.02

- Ability tomonitor p

igli.itlixautomatic operations ofthe 223002 PCIS/Nuclear Steam PRIMARY CONTAINMENT

! J X

AA ISOLATION 3.5 17 Supply Shutoff SYSTEM/NUCLEAR STEAM c

ww t$iijjjj[llii:

SUPPLYSHUT-OFF including:

bh!l!D A

Valve closures A3.01

- Abilityto monitor p

w automatic operations ofthe 206000 HPCI W

X

'iMili5!1io HIGHPRESSURECOOLANT 3.6 18 INJECTION SYSTEMincluding:

A MW Turbine s eed:BWR-2,3,4 EA f A A4.01

- Ability tomanually 300000 Instrument Air E!M X A Cigiii:

operate and/or monitor inthe 2.6 19 control room:

Pressure aues a A4.06

- Ability tomanually 215004 Source RangeMonitor j

X i jjjjj!jj[

operate and/or monitor inthe 3.2 20 wmeijiii;li ajA$5 control room:

Alarms andIIhts Wh3

!!!!!!!!l!Liiiliii)!illiilillilli A4.11

- Ability tomanually 209001 LPCS jpg X gjw operate and/or monitor inthe 3.7 21

1. 5!!!ll[!i?

W control room:

S stemflow gg jjjjjjy 2.1.30

- Conduct ofOperations:

Jh components, including localjPy Ability tolocate andoperate 44 22 211000 SLC Qg was f!!!Wll!!AA controls.

d@!

i!il$w K4.01

- Knowledge ofCCWS

%@$$i.1!A!P design feature(s) andor 400000 Componenooling X

jbjjjj interlocks which provide forthe 3.4 23 following:

Automatic start of pp" witEixis standbum A4.01

- Ability tomanually operate and/or monitor inthe 259002 Reactor WaterLevel X :i control room:

AIIindividual 3.8 24 Control pislisik component controllers Inthe manual mode.

262001 ACElectrical

. 2.1.20

- Conduct ofOperations:

Distribution flif Ability tointerpret andexecute 4.6 25 racedure stes.

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

1. /Name 1

2 3 4 5 6 1 3 4 A2 G

Q#

@@jG ijijjl?jjl;jjls A1.03

- Ability topredict and/or

@$jjjjjji t

monitor changes inparameters 261000 SGTS

$@F associated with operating the 3.2 26 X i$iAjif STANDBYGASTREATMENT A SYSTEMcontrols including:

Off-site release levels may jvlago K/ACategory Totals:

2 2

2 3 2 2 3 2)f2/2; 2

4 1E2/3E Group Point Total:

26/5

.=

. 2.

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 a

Imp Q 1 2 3

4 5

6 1

3 4 ed A2.03

- Ability to(a) predict the impacts ofthefollowing onthe Vd WAV RODBLOCKMONITOR W

NAlti' SYSTEM;and(b) basedon gpg W41those predictions, use Ai@p procedures tocorrect, control,3.3 91 215002 RBM AAi; ormitigate theconsequences of thoseabnormal conditions or E

A!A operations:

Lossofassociated

^

NA reference APRMchannel:

BWR-3,4,5 290003 Control RoomHVAC

' n

2.4.31

- Emergency Procedures g.........

..y /Plan:

Knowledge of 4.I 92

' :A annunciator

alarms, indications, orresonserocedures.

[jE!!!!!iijil fij?jAjia!$i2.4.30

- Emergency Procedures A

/Plan; Knowledge ofevents em

. CfA related tosystem operation

/

272000 Radiation Monitoring PAj Qp statusthat mustbereported to 4.1 93 a:de internal organizationsor external agencies,suchasthe state, theNRC,orthe transmission s stemo erator.

K1.07

- Knowledge ofthe physical connections and/or 256000 Reactor CondensateX cause-effect relationships 2.9 27 between REACTOR CONDENSATE SYSTEM and EiAW@i@iM thefollowin

SJAE condenser 223001 Primary CTMTand p

K2.10

- Knowledge of electrical Aux powersupplies tothefollowing:

2.7 28 X

maitD ellchillers:

Plant-S ecific K3.04

- Knowledge oftheeffect that aloss ormalfunction ofthe 234000 Fuel Handling FUELHANDLING EQUIPMENT X

29 29 Equipment K3.03 will haveonfollowing:

Reactor manual control system:

Plant-S ecific K4.01

- Knowledge ofOFFGAS n

A +

SYSTEMdesign feature(s) 271000 Off-gas X

and/or interlocks whichprovide2.9 30 jgg gy forthefollowing:

Dilution of h droen asconcentration K5.04

- Knowledge ofthe operational implications ofthe 230000 RHR/LPCI:

following concepts astheyapply X

W+

/C s toRHR/LPCI:

2.5 31 Torus/Pool Spray Mode TORUS/SUPPRESSION POOL SPRAYMODE:Evaporative coolin K6.01

- Knowledge oftheeffect q:3 that aloss ormalfunction ofthe 216000 Nuclear Boiler Inst.

following will haveonthe X

3.1 32 NUCLEAR BOILER INSTRUMENTATION

A.C.

electrical distribution

ES-401 5

FormES-401-1 HC212 Written Examination Outline Plant Systems

- Tier2Group2 K K K K K K A A A Imp Q System#/Name A2 G

1 2 3 4 5 6 1 3 4 monitor changes inparameters associated with operating the 202001 Recirculation X Afhn ih RECIRCULATION SYSTEM 3.1 33 controls including:

Recirculation M

AEClooptemperatures:

Plant-Wie M)3AS ecific

? A2.05

- Ability to(a) predict the impacts ofthefollowing on theCONTROL RODAND A DRIVEMECHANISM

and(b) 201003 Control Rodand

$3!

A basedonthose predictions, use 4.1 34 Drive Mechanism procedures tocorrect,

control, ormitigate theconsequences of those abnormal conditions or 521 o erations:

Reactor Scram g

A3.01

- Ability tomonitor 4

automatic operations ofthe 219000 RHR/LPCI:

RHR/LPCI:

X 33 35 Torus/Pool Cooling Mode 2 TORUS/SUPPRESSION POOL COOLING MODEincluding:

Valve o eration

@h

(

A4.03

- Ability tomonitor automatic operations ofthe ROD WORTH MINIMIzER 201006 RWM kW X.i SYSTEM (RWM) (PLANT 3.0 36 d$ SPECIFIC) including:

Latched Nf Nya group indication:

P-Spec(Not-BWR6 E 2.4.9

- Emergency Procedures

/

e$iit tifiMPlan:

Knowledgeof low power /

204000 RWCU EAiE shutdown implications in 3.8 37 Addj

@Uaccident (e.g.,

loss ofcoolant

$j[@

accident orlossofresidual heat A iG removalmiti ation strate les.

(K3.02

- Knowledge oftheeffect idiA (that aloss ormalfunction ofthe 201002 RMCS 3

WW REACTORMANUAL X

29 38 CONTROL SYSTEMwill have onfollowing:

Rodblock monitor:

Plant-S ecific waw

,=x K/ACategory Totals:

1 1 2 1

1 1 1 p$gi1 1 W22%

Group Point Total:

12/3 Me ePN

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 allmodes 4.4 98 of lanto eration.

1.

Conduct Abilityto evaluate plant performance and ofOperations217 makeoperational judgements based on 44 66 operating characteristics, reactor

behavior, andinstrument inter retation.

2.1.32 Ability toexplainand apply all system limits3.8 67 and recautions.

Subtotal

$j@

2 @l!2 Knowledge oftheprocess for controlling 3.3 95 2.231 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 andconfig,uration 3.9 69 control documentation, suchasdrawings, 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 @@2 2.3.6 Ability toapprove release permits.

3.8 96 3

Ability tocomply withradiation 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 monitor 2313 34 71

alarms, 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

@E23 pj@@1 KnowledgeofSROresponsibilities in 4.5 97 2.4.40 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 Procedures

/

o erational effects.

Plan Knowledge of procedures relating toa 3.2 73 2.4.28securit event.

Subtotal jhj@2 $$l!!il;!@i 2

Tier 3Point Total 10 jjjggj 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 Thereisnospecific 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/A1.04 There isnopressure 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 TechSpecswhich isattheSROlevel.

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/A4.01 Thereisnolockout parameter fortheRFP's atHopeCreek.

Randomly reselected:

Allindividual 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 withapurpose ofasystem.

Toolowofacognitive level question.

Randomly reselected:

Ability tointerpret andexecute procedure steps.

A1.05

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

Primary containment oxygen level:

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

A1.03 There isnoOxygenparameter that directly interfaces with the FRVS system.

Randomlyreselected:

Off-site release levels EK1.06

- Knowledge oftheoperational implications ofthe following concepts asthey applytoSCRAMCONDITION PRESENTANDREACTOR POWER ABOVEAPRM DOWNSCALE ORUNKNOWN:

Cooldown effects onreactor power.

1/1(#40) 295037/

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

Randomly reselected:

Boroneffects onreactor power (SBLC).

EK2.12Knowledge oftheinterrelations between HIGH OFF-SITERELEASERATEandthefollowing:

Feedwater leakage control:

BWR-6 1/1(#42)295038/

EK2.06 TherearenoHopeCreekprocedures that reference Feedwater leakage control withOffsite Release.

Cannot write alicense level question forthis K/A.

Randomly reselected:

Process liquid radiation monitoring system AK3.01

- Knowledge ofthereasons forthefollowing responses astheyapply toPARTIALORCOMPLETELOSSOFD.C.

POWER:Loadshedding 1/1(#45)295004/

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

Randomly reselected:

Ground isolation/fault determination

ES-401 RecordofRejected K/A's FormES-401-4 AA1.07

- Ability tooperate and/or monitor thefollowing asthey apply toREFUELING ACCIDENTS

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

AA1.02 Theaboveconcept (K/A) issimilar toQuestion

1. 26whichwould cause"Double Jeopardy" ontheexam.

Randomly reselected:

Fuelpoolcooling andcleanup system AA2.01

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

AA2.04 L.O.D foraquestion onwhathappens toreactor powerona scram (power lowers, APRMsdownscale) wouldbe1 Randomly reselected:

Reactor pressure 2.4.6

- Emergency Procedures

/Plan:

Knowledge ofEOP mitigation strategies.

1/1(#58) 2950282.4.18EOPmitigation strategies areattheSROlevel duetoselection ofEOPprocedures andactions withinthelegs oftheEOP procedures tosatisfy the mitigation strategy.

Randomly selected:

Knowledgeof the specific basesforEOPs.

2.4.41-Emergency Procedures

/Plan:Knowledge ofthe emergency action level thresholds andclassifications.

TherearenoECG/classifications fortheInstrument AirSystem 2/1(#89) 3000002.4.11 IAWtheHopeCreekEALsandRALs.

Randomly reselected:

Knowledge ofabnormal condition procedures.

A2.01-Ability to(a) predict theimpacts ofthefollowing onthe RODBLOCKMONITORSYSTEM;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 Thereisnoprocedure that directly addresses ormitigates the consequences ofacontrol rodwithdrawal inthehigher power region ofthecore.

ThisismoreofaGFEStypeK/A.

Randomly reselected:

Lossofassociated reference APRM channel:

BWR-3,4,5

ES-401 RecordofRejected K/A's FormES-401-4 2.4.26 Knowledge offacility protection requirements, including fire brigade andportable firefighting equipment usage.

Thereisnofire brigade (separate fire department) atHope 3/4

(#97) 2.4.40 Creek.

Cannot write aSROlicense level question tothis K/A.

Randomly reselected:

Knowledge ofSROresponsibilities in emergency planimplementation.

>