ML20260H152
| ML20260H152 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/14/2019 |
| From: | Exelon Generation Co |
| To: | Todd Fish Operations Branch I |
| Fish T | |
| Shared Package | |
| ML19105A122 | List: |
| References | |
| CAC 000500 | |
| Download: ML20260H152 (28) | |
Text
ES-301 Administrative Topics Outline FormES3011 Facility:
JamesA.Fitzpatrick DateofExamination:Feb2020 Examination Level:
RO Operating TestNumber:18-1 Administrative Topic (see Type Describe activity tobeperformed Note)
Code*
CoreThermal HeatBalance Verification Using Turbine P, D,R SteamPressure Conduct ofOperations 17-1 NRC K/A2.1.19 (3.9),
OP-65,RAP-7.3.03 Perform RCICLineup Verification PerST-24A Conduct ofOperations N,S K/A 2.1.31 (4.6),
ST-24A Explain RPS Operation Using Electrical Drawings Equipment Control M,R K/A2.2.41(3.5),
1.60-17, 1.67-97, 1.67-99, 1.67-101 Determine Worker Exposure forEmergent Work Radiation Control D,R K/A2.3.4 (3.2),
RP-AA-203 NOTE:Allitems (five total) arerequired forSROs.ROapplicants requireonly fouritems unless they areretaking only theadministrative topics (which wouldrequire all five items).
- TypeCodesandCriteria:(C)ontrol room,(S)imulator, orClass(R)oom (D)irect frombank(53forROs;s4forSROsandROretakes)
(N)ew or(M)odified frombank(21)
(P)revious 2exams(51,randomly selected)
ES-301 Administrative Topics Outline FormES-301-1 Facility:
JamesA.Fitzpatrick DateofExamination:Feb2020 Examination Level:
SRO Operating TestNumber:18-1 Administrative Topic (see Type Describe activity tobeperformed Note)
Code*
CoreThermal HeatBalance Verification Using Turbine P, D,R SteamPressure Conduct ofOperations 17-1 NRC K/A2.1.19 (3.8),
OP-65,RAP-7.3.03 Determine ReportabilityRequirements
- Technical Conduct ofOperations N,R Specification Shutdown andGroupIIsolation K/A 2.1.18 (3.8),NUREG1022,LS-AA-1400 Explain RPS Operation Using Electrical Drawings and DetermineTechnical Specification Impact ofInoperability Equipment Control M,R K/A2.2.41 (3.9), 1.60-17, 1.67-97,1.67-99, 1.67-101, Technical Specification 3.3.1.1 Determine Worker Exposure forEmergent Workand Radiation Control D,R Required Actions K/A2.3.4 (3.7),
EN-RP-201 Determine Emergency Classification and Initiate Event Emergency Plan M,R Notification K/A2.4.40 (4.5),
EP-AA-1014, EP-CE-114-100 NOTE:Allitems(five total) arerequired forSROs.ROapplicants require onlyfour items unless they areretaking onlytheadministrative topics (which wouldrequire all fiveitems).
- TypeCodesandCriteria:(C)ontrol room,(S)imulator, orClass(R)oom (D)irect frombank(53forROs;s4forSROsandROretakes)
(N)ew or(M)odified frombank(21)
(P)revious 2exams(51,randomly selected)
ES-301 Control Room/in-Plant Systems Outline FormES-301-2 Facility:
JamesA.Fitzpatrick DateofExamination:Feb2020 ExamLevel:
RO/SRO-I Operating TestNumber:18-1 Control RoomSystems:* 8forRO,7forSRO-I, and2or3forSRO-U System/JPM Title TypeCode*
Safety Function a.Control RoomHeating, Ventilation and Air Conditioning /IsolateP,D,EN,S Control RoomandRelay RoomVentilation 9
17-1NRC K/A290003A4.01(3.2/3.2),
OP-55B b.Reactor Feedwater System
/Transfer Feedwater LevelControl to Master-Auto, Level Drifts Low M,A,L,S 2
K/A259001 A4.01 (3.6/3.5),
OP-2A c.LowPressure CoreSpray
/Shutdown CoreSpray Following Terminate/Prevent andSubsequent Injection N,L,EN,S 4
K/A209001 A4.01(3.8/3.6),
EP-5,OP-14 d.A.C.Electrical Distribution
/Restore L34toNormal Power
- Source, Lossof10400Bus D, A,S 6
K/A262001 A4.01 (3.4/3.7),
OP-46A, AOP-17 e.Primary Containment Isolation System
/Nuclear SteamSupply Shut-Off
/Reset Group2Isolation, Restore RWCU,RWCUSteam Leak M,A,EN,S 5
K/A223002A4.03(3.6/3.5),
AOP-15, OP-28 f.Control RodDrive Hydraulic System
/Restore CRDtoNormal Alignment Following ATWS,CRDController Fails inAutomatic D,A,S 1
K/A201001 A2.07(3.2/3.1),
EP-3,OP-25 g.MainandReheat SteamSystem
/Perform MainSteamSystem Shutdown N,L,S 3
K/A239001A4.01(4.2/4.0),
OP-1 h.Average PowerRangeMonitor/Local PowerRangeMonitor
/
Bypass LPRM(ROOnly)
K/A215005 A4.06 (3.6/3.8),
OP-16 D,S 7
in-Plant Systems:* 3forRO,3forSRO-l, and3or2forSRO-U i.Primary Containment IsolationSystem
/Nuclear SteamSupply P,D,A,E Shut-Off
/Restore H2/O2 MonitorsFollowing Isolation 5
17-1NRC K/A223002 A2.09(3.6/3.7),
EP-2,OP-37 j.D.C.Electrical Distribution
/Perform In-Plant Actions forStation Blackout D,R,E 6
K/A295003AA1.04 (3.6/3.7),
AOP-49 k.Control RodDrive Hydraulic System /Swap CRDFlowControl Valves D,R 1
K/A201001 2.1.20 (4.6/4.6),
OP-25 AIIROandSRO-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.
- TypeCodes Criteria forR/SRO-l/SRO-U (A)Iternate path 4-6/4-6
/2-3 (C)ontrol room (D)irect frombank 59/s8/s 4 (E)mergency orabnormal in-plant 2 1/21/21 (EN)gineered safety feature 2 1/21/21(control roomsystem)
(L)ow-Power/Shutdown 2 1/21/21 (N)ew or(M)odified frombankincluding 1(A) 2 2/22/21 (P)revious 2exams s3/s3/s2 (randomly selected)
(R)CA 2 1/21/21 (S)imulator
Appendix D
Scenario Outline FormESD-1 Facility:
Jh Scenario No.:NRC-1 Op-Test No.:j8-1 Examiners:
Operators:
Initial Conditions:
The plant isoperating atapproximately 93%power.
RBCLCpumpAisoutof service for maintenance. SRV Aisinoperable. Line 3isoutofservice andready toberestored.
Turnover:
Restore Line3toservice perOP-44G.9.Then,raise Reactor power to98%using Recirculation flow.
Event Malf. Event Event No.
No.
Type*
Description N
RestoreLine 3toService 1
N/A
RaiseReactor Power with Recirculation Flow 2
N/A
LossofOffsite Power 3
ED44 SRO AOP-72, Technical Specifications C
SRVInadvertently Opens 4
AD06:C
C
- All FW01:A ARP09-6-4-11, AOP-41 SteamLeakinDrywell AOP-39, AOP-1 LossofCoolant Accident 7
RR15:A M
First Torus Spray Valve UsedFails toOpen 8
Remote
HPO2 C
- All EOP-2 (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor
I Appendix D
Scenario Outline FormES-D1 Facility:
James A.Fitzpatrick SCenario No.:NRC-1 Op-Test No.:18-1 1.Malfunctions afterEOPentry(1-2) 2 Events 8&9 2.Abnormal events (2-4) 4 Events 3,4,5,6 3.Major transients (1-2) 1 Event7 4.EOPsentered/requiring substantive actions(1-2) 2 EOP-2,EOP-4 5.Entry into acontingency EOPwith substantive 2
actions (21 perscenario set)
EOP-2Alternate Level Control Leg EOP-2Emergency Depressurization Leg 6.Pre-identified critical tasks (22) 2 CRITICAL TASKDESCRIPTIONS:
CT-1:Givenacoolant leakinside theContainment, thecrewwill spray theDrywell, inaccordance with EOP-4.Drywell spray mustbeinitiated within 15 minutes ofToruspressure exceeding 15psig.
CT-2:Givenacoolant
- leak, alossofhighpressure injection
- systems, andtheinability torestore and maintain Reactor waterlevel abovetheTopofActive Fuel(TAF),
thecrewwill initiate actions foran Emergency RPVDepressurization, inaccordance withEOP2.Reactor waterlevel mustberestored andmaintained aboveTAFwithin thirty minutes of lowering belowTAF.
Appendix D
Scenario Outline FormES-D-1 Facility: h Scenario No.:NRC-2 Op-Test No.:j8-1 Examiners:
Operators:
Initial Conditions:
The plant isoperating atapproximately 71%power.
RBCLCpumpAisoutof service formaintenance.
Turnover:
SwapFeedwater level control fromlevel column AtoBperOP-2Asection G.27.Then, erform aControl Rodattern ad'ustment inaccordancewith Reactor Enineerin instructions.
Event Malf. Event Event No.
No.
Type*
Description N
SwapFeedwater Level Control Instruments 1
N/A
performControl Rod Pattern Adjustment 2
N/A
CRDFlowControl Valve Fails Closed 3
RD03:A
RR23:B I
- All OP-16, Technical Specifications C
LossofRBCLCFlowtoRecirculation PumpB 5
SW01:B
- BOP, SRO OP-27, AOP-8, Technical Specifications Thermal Hydraulic Instability AOP-8, AOP-1 Hydraulic Failure toScram 7
m M
- M EOP-3 C
Inadvertent GroupIisolation 8
RP03
First SLCPumpDelayed Trip 9
SL01
Appendix D
Scenario Outline FormES-D-1 Facility:
James A.Fitzpatrick Scenario No.:NRC-2 Op-Test No.:18-1 1.Malfunctions afterEOPentry (1-2) 2 Event8&9 2.Abnormal events (2-4) 2 Events 5&6 3.Major transients (1-2) 1 Event7 4.EOPsentered/requiring substantive actions(1-2) 1 EOP-2 5.Entry into acontingency EOPwith substantive 1
actions (21 perscenario set)
EOP-3 6.Pre-identified critical tasks(22) 2 CRITICAL TASKDESCRIPTIONS:
CT-1:Given afailure toscramwithReactor power above2.5%,thecrewwill lowerReactor powerby oneormoreofthefollowing
- methods, inaccordance withEOP-3:
Terminating andpreventing allRPVinjection exceptSLC,RCIC,andCRD Tripping Recirculation pumpA Injecting boron TheReactor powerreduction mustbeinitiated within five minutes ofthestart ofthefailure toscram.
CT-2:Givenafailure
- toscram, thecrewwill initiate Control Rodinsertion, inaccordance withEOP3.All insertable control rodsmustbeinserted within one hourofthestart ofthefailure toscram.
Appendix D
Scenario Outline FormES-D-1 Facility: W Scenario No.:NRC-3 Op-Test No.:j8-1 Examiners:
Operators:
Initial Conditions:
The plant isoperating atapproximately 100%power.
RBCLCpumpA isoutof service for maintenance.
Turnover:
Swa CRD ums er OP-25 section G.10.
Event Malf. Event Event No.
No.
Type*
Description N
Swap CRD Pumps 1
N/A
Condensate Booster Pump Trips 2
FW25:C
- ATC, SRO ARP09-6-3-22, AOP-41, RAP-7.3.16 I
- ATC APRMFails As-Is 3
NM14:A SRO ARP09-5-2-2(44),
OP-16 4
I
- BOP, HPCIInadvertently Initiates; Turbine Trip Pushbutton Fails HP05 SRO override AOP-77, AOP-32, Technical Specifications EPICFails 5
YC01 I-SRO ARP09-8-1-4, ST-40C, Technical Specifications Remaining Condensate Booster PumpsTrip AOP-41, AOP-1,EOP-2 RR33 SteamLeakinDrywell 7
M
- BOP RCICFails toAutomatically Start 8
RCO2 SRO EOP-2 RR33 RR16 Multiple Level Instrument Failures 9
RR17 I
- AII RR19 RR31 (N)ormal, (R)eactivity, (1)nstrument, (C)omponent, (M)ajor
Appendix D
Scenario Outline FormESD-1 Facility:
James A.Fitzpatrick Scenario No.:NRC-3 Op-Test No.:18-1 1.Malfunctions afterEOPentry (1-2) 2 Event8&9 2.Abnormal events (2-4) 3 Events 2,4,6 3.Major transients (1-2) 1 Event7 4.EOPsentered/requiring substantive actions(1-2) 2 EOP2,EOP4 5.Entry into acontingency EOPwith substantive 1
actions (21 perscenario set)
EOP-7 6.Pre-identified critical tasks (22) 2 CRITICAL TASKDESCRIPTIONS:
CT-1:Givenacoolant leakinside theContainment, thecrewwill spray theDrywell, inaccordance with EOP4.Drywell spraymustbeinitiated within 15 minutes ofToruspressure exceeding 15psig.
CT2:Given anunknownReactor waterlevel, the crewwill flood theRPV,inaccordance withEOP7.
TheRPVmustbeflooded totheMainSteamLines within 30minutes ofwhenReactor waterlevel becomesunknown.
Appendix D
Scenario Outline FormESD1 Facility:
Jh Scenario No.:NRC-4 Op-Test No.:J.8-1 Examiners:
Operators:
Initial Conditions:
The plant isoperating atapproximately 90%power.
RBCLCpumpAisoutof service for maintenance. Torus Cooling isinservice following completion ofRCICsurveillance testing.
Turnover:
Secure Torus Cooling per OP-13B.
Then,raise Reactor powerusing control rodsand Recirculation flowertherovided reactivit instructions.
Event Malf. Event Event No.
No.
Type*
Description N-SecureTorus Cooling 1
N/A
RHRSWPumpsTrip 2
SW04:A SRO ARP09-3-1-25, Technical Specifications R
Raise Reactor Power withControl RodsandRecirculation Flow 3
N/A
Stuck Control Rod 4
RD10
RCICSteamLeak,Fails toAutomatically Isolate 5
RC09
MC01 C
- All AOP-31, AOP-1,EOP-2 Coolant LeakinDrywell 7
m M
TenControl RodsFail toScram;CRDDrive WaterPressure 8
RD13
Feedwater PumpsTrip; HPCIFails toAutomatically Start 9
Appendix D
Scenario Outline FormES-D-1 Facility:
James A.Fitzpatrick SCenario No.:NRC4 Op-Test No.:18-1 1.Malfunctions afterEOPentry (1-2) 2 Events 8&9 2.Abnormal events (2-4) 2 Events 5&6 3.Major transients (1-2) 1 Event7 4.EOPsentered/requiring substantive actions(1-2) 2 EOP-2, EOP4 5.Entry into acontingency EOPwith substantive 1
actions (21 perscenario set)
EOP-3 6.Pre-identified critical tasks(22) 3 CRITICAL TASKDESCRIPTIONS:
CT-1:Givenacoolant leakinside theContainment, thecrewwill spray theDrywell, inaccordance with EOP4.Drywell spray mustbeinitiated within 15 minutes ofToruspressure exceeding 15psig.
CT2:Givenacoolant leakinside theContainment anddegraded highpressure injection
- sources, the crewwillestablish injection totheReactor, in accordance withEOP-2and/or EOP3.Injection mustbeestablished suchthatReactor waterlevel doesnotlower below-19".
CT-3:Givenafailure
- toscram, thecrewwill initiate Control Rodinsertion, inaccordance withEOP-3.
All insertable control rodsmustbeinserted within one hourofthestart ofthefailure toscram.
ES-401 1
FormES-401-1 Tier Group ROK/ACategory Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G*
Total 1,
1 4
4 3
3 3
3 20 4
3 7
Emergency and 2
1 1
1 N/A 2
1 N/A 1
7 2
1 3
Abnormal Plant EvolutionsTier Totals5 5
4 5
4 4
27 6
4 10 1
2 2
3 2
2 3
2 2
3 2
3 26 3
2 5
2 Plant 2
2 0
1 1
1 1
1 1
1 2
1 12 0
1 2
3 Systems Tier Totals4 2
4 3
3 4
3 3
4 4
4 38 4
4 8
3.Generic Knowledge andAbilities 1 2
3 4
10 1
2 3
4 7
Categories 3
3 1
3 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 in Tier 3oftheSRO-only
- section, the"Tier Totals" in eachK/Acategory shall notbeless thantwo).
(one Tier3 radiation control K/Aisallowed ifitisreplaced bya K/Afromanother Tier 3category.)
2.Thepoint total foreachgroup andtier intheproposed outline must match that specified inthetable.
Thefinal point total foreachgroup andtier maydeviate by11fromthat specified inthetable basedonNRCrevisions.
Thefinal ROexammusttotal
- 75points, andtheSRO-only exammusttotal 25points.
3.Systems/evolutions within eachgroup areidentified ontheoutline.
Systems or evolutions that donotapply at thefacility should bedeleted with justification.
Operationally important, site-specific systems/evolutions that arenotincluded ontheoutline should beadded.
Refer toSection D.1.b ofES-401 for guidance regarding the elimination ofinappropriate K/Astatements.
- 4. Select topics fromasmanysystems andevolutions aspossible.
Sample every systemor evolution inthe groupbefore selecting asecondtopic foranysystem orevolution.
- 5. Absent aplant-specific
- priority, onlythose K/Ashaving animportance rating (IR) of2.5orhigher.
Use theRO andSROratings fortheROandSRO-only
- portions, respectively.
- 6. Select SROtopics forTiers 1and2fromtheshadedsystems andK/Acategories.
7.Thegeneric (G)
K/AsinTiers 1and2shall beselected fromSection 2oftheK/Acatalog, butthetopicsmust berelevant totheapplicable evolution orsystem.
Refer toSection D.1.b ofES-401 fortheapplicable K/As.
8.Onthefollowing
- pages, enter theK/Anumbers, abrief description ofeachtopic, thetopics' IRsforthe applicable license
- level, andthepoint totals
(#)
foreachsystem andcategory.
Enter thegroup andtier totals foreachcategory inthetable above.Iffuel-handling equipment issampled inacategory other than Category A2orG*ontheSRO-only exam,enteritontheleft sideofColumnA2forTier 2,Group2.(Note 1
doesnotapply.)
Useduplicate pages forROandSRO-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* Generic K/As Thesesystems/evolutions mustbeincluded aspartofthesample(as applicable tothefacility) whenRevision 3
oftheK/Acatalog isusedtodevelop thesample plan.
Theyarenotrequired tobeincluded whenusing earlier revisions oftheK/Acatalog.
- Thesesystems/evolutions maybeeliminated fromthesample(as applicable tothefacility) whenRevision 3of theK/Acatalog isusedtodevelop thesample plan.
ES401 2
FormES401-1 ES-401 BWRExamination Outline FormES-401-1 EmerencandAbnormal Plant Evolutions-Tier 1/Group 1(RO/SRO E/APE#/Name/ Safet Function K1 K2 K3 A1 A2 G*
K/AToics IR Q#
295021 (APE 21)
Loss of Shutdown Cooling
/
X 2.1.23 Ability toperform specific system and4.4 76 4
integrated plant procedures during all modesofplant operation.
295023(APE 23)
Refueling Accidents
/8 X
AA2.03 Ability todetermine and/or interpret 3.8 77 thefollowing asthey apply toREFUELING ACCIDENTS:
Airborne contamination levels 295018(APE 18)
Partial orComplete Lossof X
AA2.02 Ability todetermine and/or interpret 3.2 78 CCW/8 thefollowing asthey apply toPARTIAL OR COMPLETE LOSSOFCOMPONENT COOLING WATER:Cooling water temperature 295030(EPE7)LowSuppression Pool Water X
2.2.38 Knowledge ofconditions and 4.5 79 Level
/5 limitations inthefacilit license.
295037(EPE14)
ScramCondition Present X
EA2.01 Ability todetermine and/or interpret 4.3 80 andReactor PowerAboveAPRMDownscale thefollowing astheyapply toSCRAM orUnknown
/1 CONDITION PRESENT ANDREACTOR POWER ABOVEAPRMDOWNSCALE OR UNKNOWN:
Reactor ower 295004Partial orComplete LossofD.C.
X AA2.03 Ability todetermineand/or interpret 2.9 81 Power thefollowing astheyapply toPARTIAL OR COMPLETE LOSS OFD.C.POWER:
Battevolta e 295038(EPE 15)
HighOffsite Radioactivity X
2.4.20 Knowledge of theoperational 4.3 82 Release Rate/9 implications ofEOP warnings, cautions,and notes.
295001(APE 1)Partial orComplete Lossof X
AK2.07 Knowledge oftheinterrelations 3.4 1 Forced CoreFlowCirculation
/1&4 between PARTIAL ORCOMPLETE LOSS OFFORCEDCOREFLOWCIRCULATION andthefollowin
- Coreflow indication 295003(APE 3)Partial orComplete Lossof X
AA2.02 Ability todetermine and/or interpret 4.2 2 ACPower/6 thefollowing asthey apply toPARTIAL OR COMPLETELOSSOFA.C.POWER:
Reactorower/ ressure
/andlevel 295004(APE 4)Partial orTotal LossofDC X
AA2.03Ability todetermine and/or interpret 2.8 3 Power/6 thefollowing astheyapply toPARTIALOR COMPLETELOSSOFD.C.POWER:
Battevolta e
295005(APE 5)MainTurbine Generator Trip
/
X 2.4.31 Knowledge ofannunciator alarms,4.2 4 3
indications, orresonserocedures.
295006 (APE 6)Scram/1 X
AK3.06 Knowledge ofthereasons forthe 3.2 5 following responses astheyapply to SCRAM:Recirculation pumpspeed reduction:
Plant-Specific 295016(APE 16)
Control RoomAbandonment X
AK3.01 Knowledge ofthereasons forthe 4.1 6
/7 following responses astheyapply to CONTROLROOMABANDONMENT:
Reactor SCRAM 295018(APE18)
Partial orComplete Lossof X AK1.01 Knowledge oftheoperational 3.5 7 CCW/8 implications ofthefollowing concepts as theyapply toPARTIAL ORCOMPLETE LOSSOFCOMPONENT COOLING WATER:Effects oncomponent/system operations
ES401 3
FormES-401-1 295019(APE 19)PartialorComplete Lossof X
AA1.01 Ability tooperate and/or monitor the3.5 8 InstrumentAir /8 following astheyapply toPARTIAL OR COMPLETE LOSSOFINSTRUMENT AIR:
Backuairsu I 295021(APE 21)
Loss of Shutdown Cooling
/
X AA1.02 Ability tooperate and/or monitor the3.5 9 4
following astheyapply toLOSSOF SHUTDOWN COOLING:
RHR/shutdown coolin 295023(APE 23)
Refueling Accidents
/8 X
AK2.05 Knowledge oftheinterrelations 3.5 10 between REFUELING ACCIDENTS andthe following:
Secondary containment ventilation 295024 HighDrywell Pressure
/5 X
EK1.01 Knowledge oftheoperational4.1 11 implications ofthefollowing concepts as theyapply toHIGHDRYWELL PRESSURE D
ell interit
- Plant-S ecific 295025(EPE2)HighReactor Pressure
/3 X
EA1.04 Ability tooperate and/or monitor the3.8 12 following astheyapply toHIGHREACTOR PRESSURE: HPCl:
Plant-S ecific 295026(EPE3)Suppression PoolHighWater X
EK3.01 Knowledge ofthereasons forthe 3.8 13 Temperature
/5 following responsesastheyapply to SUPPRESSION POOLHIGHWATER TEMPERATURE:
Emergency/normal depressurization 295028(EPE 5)HighDrywell Temperature X
2.2.42 Ability torecognize system 3.9 14 (Mark IandMarkIIonly)
/5 parameters that areentry-level conditions for TechnicalS ecifications.
295030(EPE7)LowSuppression PoolWaterX EK1.02 Knowledge of theoperational 3.5 15 Level
/5 implications ofthe following concepts as they apply toLOWSUPPRESSION POOL WATERLEVEL:
Pum NPSH 295031(EPE8)Reactor LowWaterLevel
/2 X
2.4.34 Knowledge ofROtasksperformed 4.2 16 outside themaincontrol room during an emergency andtheresultant operational effects.
295037(EPE14)
ScramCondition Present X
EK2.03 Knowledge oftheinterrelations 4.1 17 andReactor PowerAboveAPRMDownscale between SCRAMCONDITION PRESENT orUnknown/1 ANDREACTORPOWERABOVEAPRM DOWNSCALE ORUNKNOWN andthe followin
- ARI/RPT/ATWS:
Plant-S ecific 295038 (EPE15)
HighOffsite Radioactivity X
EK1.02 Knowledge oftheoperational 4.2 18 Release Rate/9 implications ofthefollowing concepts as theyapply toHIGHOFF-SITE RELEASE RATE:Protection oftheeneral ublic 600000(APE24)
Plant Fire OnSite
/8 X
AA2.14 Ability todetermine andinterpret the3.0 19 following astheyapply toPLANTFIREON SITE:
Equipment that will beaffected byfire su ression activities ineachzone AK2.02 Knowledge oftheinterrelations 700000 (APE25)
Generator Voltage and X
between GENERATOR VOLTAGE AND 3.1 20 Electric GridDisturbances
/6 ELECTRIC GRIDDISTURBANCES andthe followin
- Breakers, relas
ES-401 4
FormES4011 ES-401 BWRExamination Outline FormES-401-1 EmerencandAbnormal Plant Evolutions-Tier 1/Grou2 RO/SRO E/APE#/Name/ Safet Function K1 K2 K3 A1 A2 G*
K/AToics IR Q#
295033 (EPE10)
High Secondary X
EA2.03 Ability todetermine and/or interpret 4.2 83 Containment Area Radiation Levels /9 thefollowing astheyapply toHIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS:
tCause ofhigharea radiation 295014(APE14)
Inadvertent Reactivity X
2.1.7 Ability toevaluate plant performance 4.7 84 Addition
/1 andmakeoperational judgments based on operating characteristics, reactor
- behavior, andinstrument inter retation.
295010(APE10)
HighDrywell Pressure
/5 X
AA2.01 Ability todetermine and/or interpret 3.8 85 thefollowing astheyapply toHIGH DRYWELL PRESSURE:tLeak rates AK2.01 Knowledge oftheinterrelations 295013 (APE13)
HighSuppression Pool X
between HIGHSUPPRESSION POOL 3.6 21 WaterTemperature
/5 WATERTEMPERATURE andthe followin
- Su ression oolcoolin 295020(APE 20)
Inadvertent ContainmentX AK1.02 Knowledge oftheoperational3.5 22 Isolation
/5&7 implications ofthefollowing concepts as they applytoINADVERTENT CONTAINMENT ISOLATION:
Power
/
reactivit control 295029(EPE6)HighSuppression PoolWater X
EA1.03Ability tooperateand/or monitor2.9 23 Level
/5 thefollowing as theyapply toHIGH SUPPRESSION POOL WATERLEVEL:
RHR/LPCI 295032(EPE 9)HighSecondary Containment X
EK3.01 Knowledgeof the reasons forthe 3.5 24 AreaTemperaturel 5
following responses asthey apply toHIGH SECONDARY CONTAINMENT AREA TEMPERATURE:
Emergency/normal deressurization 295009 LowReactor WaterLevel X
AA2.01 Ability todetermine and/orinterpret 4.2 25 thefollowing astheyapply toLOW REACTOR WATERLEVEL:
Reactor water level 295035 (EPE12)
2.4.1 Knowledge ofEOPentry conditions 4.6 26 HihDifferential Pressure
/5 andimmediate action steps.
295036(EPE13)
EA1.01 Ability tooperate and/or monitor3.2 27 HighSump/Area WaterLevel
/5 thefollowing astheyapply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATERLEVEL:Secondary containment equipment andfloor drain s stems
ES-401 5
FormES-401-1 ES-401 BWRExamination Outline FormES-401-1 Plant S stems-Tier 2/Grou1 RO/SRO System
- /Name K1K2K3K4K5K6A1A2A3A4G*
K/ATopic(s)
IR Q#
262001(SF6 AC)
AC Electrical X
A2.06Ability to(a) predict theimpacts ofthe 2.9 86 Distribution following ontheA.C.ELECTRICAL DISTRIBUTION:
and(b) basedonthose predictions, useprocedures tocorrect,
- control, ormitigate theconsequences of those abnormal conditions oroperations:
De-energizing aplant bus 203000 (SF2, SF4RHR/LPCI)
X 2.1,31Ability tolocate control roomswitches,4.3 87
- controls, andindications, andtodetermine RHR/LPCI:
Injection Mode that theycorrectly reflect thedesired plant lineup.
211000(SF1 SLCS)
Standby Liquid X
A2.01Ability to(a) predict theimpacts ofthe 3.8 88 Control following ontheSTANDBYLlQUID CONTROL SYSTEM;and(b) basedonthose predictions, useprocedures tocorrect,
- control, ormitigate theconsequences of those abnormal conditions oroperations:
Pumptrip 215005(SF7 PRMS)
Average Power X
A2.07 Ability to(a) predict theimpacts ofthe3.4 89 RangeMonitor/Local PowerRange following ontheAVERAGE POWERRANGE Monitor MONITOR/LOCAL POWERRANGE MONITOR SYSTEM; and(b) basedonthose predictions, useprocedures tocorrect,
- control, or mitigate theconsequences of those abnormal conditions oroperations:
Recirculation flow channels flow mismatch 209001 (SF2, SF4LPCS)
X 2.4.9 Knowledgeof low power/shutdown 4.2 90 Low-Pressure CoreSpray implications inaccident (e.g., loss ofcoolant accident orloss ofresidual heat removal) mitigation strategies.
203000 (SF2, SF4RHR/LPCI)X K1.17 Knowledge ofthephysical connections 4.0 28 RHR/LPCI:
Injection Mode and/or cause/effect relationships between RHR/LPCl:
INJECTION MODE(PLANT SPECIFIC) andthefollowing:
Reactor pressure 205000(SF4 SCS)
A1.01Ability topredict and/or monitor 3.3 29 changes inparameters associated with operating theSHUTDOWN COOLING SYSTEM(RHR SHUTDOWN COOLING MODE) controls including:
Heatexchanger cooling flow 205000(SF4 SCS)
K3.02Knowledge oftheeffect that aloss or 3.2 30 malfunction oftheSHUTDOWN COOLING SYSTEM(RHR SHUTDOWN COOLING MODE) will haveonfollowing:
Reactor water level:
Plant-Specific 206000 (SF2, SF4HPCIS)
X A1.06Ability topredict and/or monitor 3.8 31 High-Pressure Coolant injection changes inparameters associated with operating theHIGHPRESSURE COOLANT INJECTION SYSTEM controls including:
System flow
ES-401 6
FormES4011 209001(SF2, SF4LPCS)
X K5.04 Knowledge oftheoperational 2.8 32 Low-Pressure Core Spray implications ofthefollowing concepts asthey apply toLOWPRESSURE CORESPRAY SYSTEM:Heatremoval (transfer) mechanisms 211000(SF1 SLCS)
Standby Liquid X
A3.05Ability tomonitor automatic operations 4.1 33 Control oftheSTANDBYLIQUID CONTROL SYSTEMincluding:
Flowindication:
Plant-Specific 212000(SF7 RPS)
Reactor Protection X
K4.02Knowledge ofREACTOR 3.5 34 PROTECTION SYSTEMdesign feature(s)
. and/or interlocks which provide forthe following:
Theprevention ofareactor SCRAM
.. following asingle component failure 215003(SF7 IRM)
X K2.01Knowledge ofelectrical power supplies 2.5 35 Intermediate-Range Monitor tothefollowing:
IRMchannels/detectors 215003(SF7 IRM)
X A4.01Ability tomanually operate and/or 3.3 36 Intermediate-Range Monitor monitor inthecontrol room:
IRMrecorder indication 215004(SF7 SRMS)
Source-Range X
A3.04Ability tomonitor automatic operations 3.6 37 Monitor oftheSOURCERANGEMONITOR(SRM)
SYSTEM including:
Control rodblock status 215005(SF7 PRMS)
Average Power X
2.1.28 Knowledge ofthepurpose and 4.1 38 RangeMonitor/Local PowerRange function ofmajor system components and Monitor controls.
217000 (SF2, SF4RCIC)
Reactor A2.08 Ability to(a) predict theimpacts ofthe3.0 39 CoreIsolation Cooling following on the REACTOR CORE
- ISOLATION COOLING SYSTEM(RCIC);
and (b) based onthose predictions, use procedures tocorrect,
- control, ormitigate the consequences ofthose abnormal conditions oroperations:
Lossoflube oil cooling 218000(SF3 ADS)
Automatic X
K3.02Knowledge oftheeffect that aloss or 4.5 40 Depressurization malfunction oftheAUTOMATIC DEPRESSURizATION SYSTEM will have on following:
Ability torapidly depressurize the reactor 223002(SF5 PCIS)
Primary X
K3.19Knowledge oftheeffect that alossor 2.8 41 Containment Isolation/Nuclear Steam A malfunction ofthePRIMARYCONTAINMENT Supply Shutoff
"" ISOLATION SYSTEM/NUCLEAR STEAM SUPPLYSHUT-OFF will haveonfollowing:
Containment atmosphere sampling 239002(SF3 SRV)
Safety Relief X
K6.05Knowledge oftheeffect that alossor 3.0 42 Valves malfunction ofthefollowing will haveonthe RELIEF/SAFETY VALVES:Discharge line vacuumbreaker n
259002(SF2 RWLCS)
Reactor WaterX K1.16Knowledge ofthephysical connections 3.4 43 Level Control
.. and/or cause-effect relationships between REACTOR WATERLEVELCONTROL SYSTEMandthefollowing:
HPCI:Plant-7.
- Specific 261000(SF9 SGTS)
Standby Gas X
A3.01 Ability tomonitor automatic operations 3.2 44 Treatment oftheSTANDBY GASTREATMENT SYSTEMincluding:
Systemflow 261000(SF9 SGTS)
Standby Gas X 2.1.30 Ability tolocate andoperate 4.4 45 Treatment components, including local controls.
ES-401 7
FormES4011 262001(SF6 AC)ACElectrical X
A4.01 Ability tomanually operate and/or 3.4 46 Distribution monitor inthecontrol room:
Allbreakers and disconnects (including available switch yard):
Plant-Specific 262002(SF6 UPS)Uninterruptable X
A2.02 Ability to(a) predict theimpacts ofthe 2.5 47 PowerSupply (AC/DC) following ontheUNINTERRUPTABLE POWERSUPPLY(A.C./D.C.);
and(b) based onthose predictions, useprocedures to
- correct, control, ormitigate theconsequences ofthose abnormal conditions oroperations:
Overvoltage 263000(SF6 DC)DCElectrical X
K2.01Knowledge ofelectrical powersupplies 3.1 48 Distribution tothefollowing:
Major D.C.loads 264000(SF6 EGE)
Emergency X
K6.08 Knowledge oftheeffect that alossor 3.6 49 Generators (Diesel/Jet)
EDG malfunction ofthefollowing will haveonthe EMERGENCY GENERATORS (DIESEL/JET):
A.C.power 264000(SF6 EGE)
Emergency X
K5.05 Knowledge oftheoperational 3.4 50 Generators (Diesel/Jet)
EDG implications ofthefollowing concepts asthey apply toEMERGENCY GENERATORS (DIESEL/JET): Paralleling A.C.power sources 300000(SF8 IA) instrument Air X
K4.03 Knowledge ofINSTRUMENT AIR 2.8 51 SYSTEM design feature(s) andorinterlocks which provide forthefollowing:
Securing of IASupon lossofcooling water 300000(SF8 IA)
Instrument Air X 2.4.49 Ability toperform without reference to 4.6 52 proceduresthose actions that require immediate operation ofsystemcomponents andcontrols.
400000(SF8 CCS)
Component X
K6.05 Knowledge ofthe effect that aloss or 2.8 53 Cooling Water malfunction ofthe following will haveonthe CCWS:Motors K/ACategory Point Totals:
2 2 3 2 2 3 2 2/3 2 3 GroupPoint Total:
26/5 3
/2
ES401 8
FormES-401-1 ES-401 BWRExamination Outline FormES-401-1 Plant S stems-Tier 2/Grou2 RO/SRO S stem#/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/AToics IR Q#
290002(SF4 RVI)
Reactor Vessel Internals X
2.2.25 Knowledge ofthebasesin 4.2 91 Technical Specifications forlimiting conditions foro erations andsafelimits.
234000FuelHandling Equipment X
A2.01Ability to(a) predict theimpacts of 3.7 92 thefollowing ontheFUELHANDLING EQUIPMENT; and(b) basedonthose predictions, useprocedures tocorrect,
- control, ormitigate theconsequences of those abnormal conditions oroperations:
Interlock failure 202002(SF1 RSCTL)
Recirculation Flow Control X
2.2.40 Ability toapply Technical 4.7 93 S ecifications forasstem.
201001(SF1 CRDH)
CRDHydraulic X
2.2.12 Knowledge ofsurveillance 3.7 54 rocedures.
201003(SF1 CRDM)
Control RodandDrive X
A1.03 Ability topredict and/or monitor 2.9 55 Mechanism changes inparameters associated with operating theCONTROL RODAND DRIVEMECHANISM controls including:
CRDdrive waterflow 201002(SF1 RMCS)
Reactor Manual Control X
K1.05 Knowledge ofthephysical 3.4 56 connections and/or cause-effect relationshipsbetween REACTOR MANUALCONTROL SYSTEMandthe following: Rodworth minimizer:
Plant-S ecific 202001(SF1, SF4RS)Recirculation X
K5.10 Knowledge oftheoperational2.8 57 implications ofthefollowing concepts as they apply toRECIRCULATION SYSTEM:
Motor generatorsetoperation:
Plant-Secific 204000(SF2 RWCU)
Reactor WaterCleanup X
K4.06 Knowledge ofREACTOR WATER 2.6 58 CLEANUP SYSTEM design feature(s) and/or interlocks which provide forthe following:
Maximizeplant efficiency (use ofreenerative heat exchan er 214000(SF7 RPIS)
RodPosition Information X
K6.02 Knowledge ofthe effect that aloss2.7 59 ormalfunction ofthefollowingwill have on theRODPOSITION INFORMATION SYSTEM:
Position indication robe 215001(SF7 TIP)
Traversing In-Core Probe X
A2.07Ability to(a) predict theimpacts of 3.4 60 thefollowing ontheTRAVERSING IN-COREPROBE;and(b) basedonthose predictions, useprocedures tocorrect,
- control, ormitigate theconsequences of those abnormal conditions oroperations:
Failure toretract during accident conditions:
Mark-l&II 215002(SF7 RBMS)
RodBlock Monitor X
A4.03Ability tomanually operate and/or2.8 61 monitor inthecontrol room:
Trib asses 219000(SFS RHRSPC)
RHR/LPCl:
X A4.04Ability tomanually operate and/or3.0 62 Torus/Suppression PoolCooling Mode monitor inthecontrol room:
Minimum flow valves 223001(SF5 PCS)
Primary Containment and X
A3.04Ability tomonitor automatic 4.2 63 Auxiliaries operations ofthePRIMARY CONTAINMENT SYSTEM AND AUXILIARIES including:
Containment
/
d ellresonse durinLOCA 256000Reactor Condensate System X
K3.02 Knowledge oftheeffect that aloss3.2 64 ormalfunction oftheREACTOR CONDENSATE SYSTEM will haveon followin
- CRDh draulics sstem
ES-401 9
FormES-401-1 241000(SF3 RTPRS) Reactor/Turbine Pressure X K1.31 Knowledge ofthephysical 3.1 65 Regulating connections and/or cause-effect relationships between REACTOR/TURBINE PRESSURE REGULATING SYSTEM andthe followin
- Turbine rotection K/ACategory Point Totals:
2 0
1 1
1 1
1 1
1 2
1 Group Point Total:
12/3
/1
/2
Category K/A #
Topic RO SRO-oni IR IR 2.1.26 Knowledge ofindustrial safety procedures (such asrotating 3.4 66 equipment, electrical,hightemperature, highpressure,
- caustic, chlorine, o
enandh droen 2.1.44 Knowledge ofROduties inthecontrol roomduring fuel handling 3.9 67 suchasresponding toalarms fromthefuel handling
- area, communication with thefuel storage
- facility, systems operated from thecontrol room in support offueling operations, andsupporting 1.Conduct of instrumentation.
Operations 2.1.37 Knowledge ofprocedures, guidelines, orlimitations associated with 4.3 68 reactivit manaement.
2.1.13Knowledge offacility requirements for controlling vital/controlled 3.2 94 access.
2.1.41 Knowled eoftherefuelin rocess.
3.7 95 Subtotal 3
2 2.2.14 Knowledge oftheprocess for controlling equipment configuration or 3.9 69 status.
2.2.39 Knowledge ofless thanorequal toonehour Technical Specification 3.9 70 action statements fors stems.
2.Equipment2.2.22 Knowled eoflimitin conditions foro erations andsafet limits.
4.0 71 Control 2.2.7 Knowled eoftherocess forconductin s ecial orinfre uent tests.
3.6 96 2.2.18 Knowledge oftheprocess formanaging maintenance activities 3.9 97 during shutdown operations, suchasrisk assessments, work rioritization, etc.
Subtotal 3
2 2.3.5 Ability touseradiation monitoring
- systems, suchasfixed radiation2.9 72 monitors andalarms, portable survey instruments, personnel monitorin e uiment,etc.
3.Radiation2.3.12 Knowledge ofradiological safety principles pertaining tolicensed 3.7 98 Control operator
- duties, suchascontainment entry requirements, fuel handling responsibilities, access tolocked high-radiation
- areas, alininfilters, etc.
Subtotal 1
1 2.4.41 Knowledge oftheemergency action level thresholds and 2.9 73 classifications.
2.4.3 Abilit toidentiost-accident instrumentation.
3.7 74 4.
2.4.26Knowledge offacility protection requirements, including fire brigade3.1 75 Emergency and ortable fire fihtine uimentusae.
nce ures
/
2.4.18 Knowled eofthespecific basesforEOPs.
4.0 99 2.4.30 Knowledge ofevents related tosystemoperation/status that mustbe 4.1 100 reported tointernal organizations orexternal
- agencies, suchasthe
- State, theNRC,orthetransmission s stemo erator.
Subtotal 3
2 Tier 3Point Total 10 7
ES-401 Record ofRejected K/As FormES-4014 Tier /
Randomly Selected K/A ReasonforRejection Grou Thefollowin toledAVAsWere excluded$di#the s'ehilMhtic andrandodsam
- inAroness:
295027 High Containment Thistopic applies toplants with MarkIII Temperature containments only.
Thefacility hasaMarkI 1/1 containment.
295011 HighContainment Thistopic applies toplants withMarkIII Temperature containments only.
Thefacility hasaMarkI 1/2 containment.
207000 Isolation (Emergency)
Thissystem isnotinstalled atthefacility.
2/1 Condenser 209002 HPCS This system isnotinstalled atthefacility.
201004 RSCS This systemis no longer installed atthefacility.
201005 RCIS Thissystem isnotinstalled atthefacility.
2.2.3 Knowledge ofthedesign,ThisK/Aapplies tomulti-unitfacilities only.
procedural, andoperational G
differences between units.
2.2.4 Ability toexplain the ThisK/Aapplies tomulti-unit facilities only.
variations incontrol board/control roomlayouts, G
- systems, instrumentation, and procedural actions between units atafacility.
ES-401 Record ofRejected K/As FormES-4014 The followin V/Aswerere'ectedibilowinfthe sstematiciliHifft%ndom stunk racess:.
Question 5
Anacceptable question could notbedeveloped duetolack ofadirect turbine generator trip on 295006 Scram aReactor scram atthefacility.
AK3.05
- Knowledge ofthe Randomly resampled K/A295006 Scram 1/1 reasons forthefollowing AK3.06
- Knowledge ofthereasons forthe responses astheyapply to following responses astheyapply toSCRAM:
SCRAM: Direct turbine Recirculation pumpspeedreduction:
Plant-generatortrip:
Plant-Specific Specific.
Question 6
Anacceptable question could notbedeveloped without toomuchoverlap fromthelast twoNRC 295016 Control Room exams.
Abandonment Randomly resampled K/A295016 Control AK3.03
- Knowledge ofthe Room Abandonment AK3.01
- Knowledge of 1/1 reasons forthefollowing the reasons forthefollowing responses asthey responses astheyapply to apply to CONTROL ROOMABANDONMENT:
CONTROL ROOM Reactor SCRAM~
ABANDONMENT:
Disabling control roomcontrols Question 13 Anacceptable question could notbedeveloped duetosimplistic K/A, lack ofspecific bases 295026 Suppression PoolHigh related toK/A,andsimilarity toQuestion 21 Water Temperature Randomly resampled K/A295026 Suppression EK3.02
- Knowledge ofthe PoolHighWater TemperatureEK3.01 1/1 reasons forthefollowing Knowledge ofthereasons for the following responses astheyapply to responses astheyapply toSUPPRESSION SUPPRESSION POOLHIGH POOLHIGHWATERTEMPERATURE:
WATERTEMPERATURE:
Emergency/normal depressurization.
Suppression poolcooling Question 14 Anacceptable question could notbedeveloped duetolackofsystem setpoints, interlocks and 295028 HighDrywell automatic actions associated withtheEOP Temperature entry condition forhighDrywell temperature.
1/1 2.4.2
- Knowledge ofsystem setRandomly resampled K/A295028HighDrywell
- points, interlocks andautomatic Temperature 2.2.42
- Ability torecognize actions associated with EOP system parameters that areentry-level entry conditions.
conditions forTechnical Specifications.
ES-401 Record ofRejected K/As FormES-401-4 Question18 Anacceptable question could notbedeveloped duetolack oftestable ROlevel material.
295038 HighOffsite Radioactivity Release Rate Randomly resampled K/A295038 HighOffsite Radioactivity Release RateEK1.02 EK1.01
- Knowledge ofthe Knowledge oftheoperational implications ofthe 1/1 operational implications ofthe following concepts astheyapply toHIGHOFF-following concepts asthey SITERELEASERATE:Protection ofthe apply to HIGH OFF-SITE general public RELEASE RATE:
Biological effects ofradioisotope ingestion Question 25 Anacceptable question could notbedeveloped without oversampling Secondary Containment 2 504Seconda Controlconcepts(see alsoQuestions
- 24,26, 27,and83).
Radiation Randomly resampledK/A295009 LowReactor EA2.02
- Ability todetermineWater Level AA2.01
- Ability todetermine and/or interpret thefollowing as and/or interpret thefollowing astheyapply to C NTA ENTVENT TION t ev I' HIGHRADIATION:
Causeof highradiation levels Question 41 Anacceptable question could notbedeveloped duetosimplistic natureof K/A (anyfailure of soaton ucearStea uply r'ad'i"a i"n es e
usly lead b only@
Shutoff K306
- Knowledge oftheeffect Randomly resampled K/A223002 Primary Containment Isolation/Nuclear Steam Supply 2/1 tph aosys or9 aulnc onofthe Shutoff K3.19
- Knowledge oftheeffect that a loss ormalfunction ofthePRIMARY ISOLATION CONTAINMENT ISOLATION PPLYSHUT-OFF w Ihae
- 00
- 09 D
R**R onfollowing:
Turbine buildingatmosphere sampling.
4,
ES-401 RecordofRejected K/As FormES-401-4 Question46 Anacceptable question could notbedeveloped without either lowLODortesting GFEStype 262001 ACElectrical knowledge.
Distribution Randomly resampled K/A262001 ACElectrical A4.02
- Abilitytomanually Distribution A4.01
- Ability tomanually operate 2/1 operate and/or monitor inthe and/or monitor inthecontrol room:Allbreakers control room:
Synchroscope, anddisconnects (including available switch including understanding of yard):
Plant-Specific.
running and incoming voltages Question 50 Anacceptable question could notbedeveloped without toomuchoverlap fromthelast twoNRC 264000 Emergency Generators exams' (Diesel/Jet)
EDG Randomly resampled K/A264000 Emergency K5.06
- Knowledge ofthe Generators (Diesel/Jet)
EDGK5.05 2/1 operational implications ofthe Knowledge oftheoperational implications ofthe following concepts asthey following concepts astheyapply to apply toEMERGENCY EMERGENCY GENERATORS (DIESEL/JET):
GENERATORS (DIESEL/JET):
Paralleling A.C.powersources.
Loadsequencing Question 59 Anacceptablequestion couldnotbedeveloped without toomuchoverlap fromthelast twoNRC 214000RodPosition exams.
Information Randomly resampled K/A 214000 RodPosition K6.01
- Knowledge oftheeffect Information K6.02
- Knowledge oftheeffect that that aloss ormalfunction ofthe aloss ormalfunction ofthe following will have fpo oSN*'lH a9vepon hleg OD ontheRODPOSITION INFORMATION SYSTEM:Position indication probe.
SYSTEM:
A.C.electrical power Question 64 Anacceptable question could notbedeveloped without oversampling RHRconcepts across the 230000RHR/LPCI:
exam.
Torus/Suppression PoolSpray Mode Randomly resampled K/A256000Reactor Condensate SystemK3.02
- Knowledge ofthe K3.02
- Knowledge oftheeffecteffect thataloss ormalfunction ofthe 2/2 that alossormalfunction ofthe REACTOR CONDENSATE SYSTEMwill have TORUS/SPPRESSION POOL onWWng:W WauH wh.
SPRAYMODEwill haveon following:
Suppression pool temperature
ES-401 RecordofRejected K/As FormES-401-4 Question68 Anacceptable question could notbedeveloped atadiscriminating level duetolimited related 2.1.15-Knowledge of administrative requirements forROs(they just administrative requirements for review these aspartofturnover).
temporary management 3
directives, suchasstanding Randomly resampled K/A2.1.37
- Knowledge
- orders, night orders,operations ofprocedures, guidelines, orlimitations
- memos, etc.
associated withreactivity management.
Question 81 Anacceptable question could notbedeveloped attheSROlevel without being lowLODand 295006 Scram overlapping withoperating exam.
AA2.03
- Ability todetermine Randomlyresampled K/A295004 Partial or 1/1 and/or interpret the following as Complete LossofD.C.PowerAA2.03
- Ability theyapply toSCRAM:
Reactor todetermine and/or interpret thefollowing as waterlevel they applytoPARTIAL ORCOMPLETE LOSS OF D.C. POWER:Battery voltage.
Question 86 Anacceptable question could notbedeveloped attheSRO level without being lowLODdueto 262001 ACElectrical thesimplistic nature oftheK/A.
Distribution Randomly resampled K/A262001ACElectrical A2.07
- Ability to(a) predict the Distribution A2.06
- Ability to(a) predict the impacts ofthefollowing onthe impacts ofthefollowing on theA.C.
A.C.ELECTRICAL ELECTRICAL DISTRIBUTION; and(b) based 2/1 DISTRIBUTION; and(b) basedonthose predictions, useprocedures tocorrect, onthose predictions, use
- control, ormitigate the consequences ofthose procedures tocorrect, control,abnormal conditions oroperations:
De-ormitigate theconsequences of energizing aplant bus.
those abnormal conditions or operations:
Energizing adead bus
t ES-401 Record ofRejected K/As FormES-401-4 Question92 Anacceptable question could notbedeveloped attheSROlevel without being lowLODand 259001 Feedwater overlapping theoperating exam.
A2.03
- Ability to(a) predict the Randomly resampled K/A234000 Fuel impacts ofthefollowing onthe Handling Equipment A2.01
- Ability to(a)
REACTOR FEEDWATER predict theimpacts ofthefollowing ontheFUEL SYSTEM; and(b) based on HANDLING EQUIPMENT;and(b) based on 2M those predictions, use those predictions, useprocedures tocorrect, procedures to correct, control,control, ormitigate theconsequences ofthose ormitigate the consequences ofabnormal conditions oroperations:
Interlock those abnormal conditions or failure.
operations:
Lossof condensate pump(s)