ML17186A244

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Draft - Outlines (Folder 2)
ML17186A244
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 07/28/2016
From:
Public Service Enterprise Group
To:
NRC Region 1
Shared Package
ML15308A608 List:
References
TAC U01925
Download: ML17186A244 (23)
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Text

ES-401 Written Examination Outline Form ES-401-1 Facility: Hope Creek 2016 NRC Date of Exam: 08/22/16 SRO-On I; Poinh Tier Group K K K G Total A2 G* I otal I 2 3

  • I. 4 3 2 3 20 3 4 7 Emergency ~

& 2 2 7 2 .)

Plant Tier Evolutions 5 5 3 4 27 5 5 10 Totals 2 2 2 4 2 3 2 3 2 3 26 2 3 5 2.

2 0 2 2 12 0 2 '

Plant '

Systems Tier 3 2 3 5 3 4 4 2 5 3 4 38 4 4 8 Totals 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 3 2 3 2 Note: I. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the 'Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by+/- I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important. site-specific systems that are not included on the outline should be added. Refer to section D. I .b of ES-401. for guidance regarding elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible: sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant specific priority. only those KAs having an importance rating (IR) of2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions. respectively.
6. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.
7.
  • The generic ( G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/ A Catalog. but the topics must be relevant to the applicable evolution or system. Refer to Section D. I .b of ES-401 for the applicable KIA's
8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics* importance ratings (IR) for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
  1. I does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the K/A numbers. descriptions. !Rs. and point totals(#) on Form ES-401-3. Limit SRO selections to Kl As that arc linked to IOCFR55.43

ES-401 2 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

L;\2 02 - ;\hilit) to dclc11ninc <m<Lnr i11tl'rpret th.: folhmi11g as thev appl1 to 4 (J HHIII DRYWl.U. !'RI SSl.RI Drrncll tcmp,*raturl' EA2.04 ** Ahilit) to tkkrn1i1w an<hll" i11tcrprct the f()ll"11ing as the\ <lppl) t<>

295fl:' I i\dcquak ('ore ( "onling 2 77 Rcactnr lm1 11 ate1 kvcl adc*quak c<>rc cooli11t; l'.\2.01. :\hil1t1 tn determine and or intcrpr.:t the fi!llo11 inµ as th,*) appl\ tn 2'l502h Surrn:ss1011 Po,ll I ligh Sl'l'Pl<ISSION J'(1(JJ lll<ill \\.\ILR 42 78 Wakr lc111p ~

l"Uvll'IIC\Tl!lff Suppn:"iun p<><ll 11atc1 (l'mJKfallHl' 2.2J() - l:quipmcnt ( \i11trol: K111)\\ kde,* of 2<J51J06 SCRA \I I ks-; than 1Hh: hour 1<:ch11ical specification adiun statcnh:flL"i f()r :-.y:-.tcJTls.

2.4 4 l - l'rncrgcnc) Prnccdurcs Plan 2951)18 High on~,jh; H.clCil'C Rate Kno11 ledge of" the cmcrgL'nc1* action lc\"<:l 8()

9 thresholds and classilkat1011' 2.4 ..2 l - I~ml..'rg1..*nc~* Pro\xdurcs !'Ian Knn\\ kdgc ,,r tlu: paramclcrs and l11gic ll'l'd 29500 ! Parllal or ( *(ln!rkl<: I os, of to assc*ss tile slallh 1!f said) l[11Ktl\ll1'** su<."11 l nrcccl t lll"C l hm C1rculat1on I & as rcact1vn1* contmL core cooling ;md llc*at Ih XI cj rL'nlO\ aL r~a(,:hn Ct)olant '~ sten1 inkgrity.

containment c1mthti1m'>. rndio;1ctivil1 rcka'.c control. etc.

295fll!*l l'anial or I ntal I os,; pf DC 2.240 - l quipmrnt Contwl ;\ililit\ to apph i.7 l'wr 6 technical spccification' for a S\"skn1.

AKl.02 - Knowledge of the operational 3.

295006 SCRAM I I x implications of the following concepts as 4

39 the appl to SCRAM : Shutdown margin EKl.03 - Knowledge of the operational implications of the following concepts as 295031 Reactor Low Water Level 3.

12 x they apply to REACTOR LOW WATER 7

40 LEVEL : Water level effects on reactor power AKI .02 - Knowledge of the operation applications of the following concepts as 2.

600000 Plant Fire On-site I 8 x they apply to Plant Fire On Site: Fire 9 41 Fi htin AK2.03 - Knowledge of the interrelations 295005 Main Turbine Generator between MAIN TURBINE GENERA TOR 3.

Trip/ 3 x TRIP and the following: Recirculation 2 42 s stem AK2.06 - Knowledge of the interrelations 29500 I Partial or Complete Loss between PARTIAL OR COMPLETE 3.

of Forced Core Flow Circulation I I x LOSS OF FORCED CORE FLOW 8

43

&4 CIRCULATION and the following:

Reactor power AK2.14 - Knowledge of the interrelations 295019 Partial or Total Loss of between PARTIAL OR COMPLETE 3.

Inst Air/ 8 x LOSS OF INSTRUMENT AIR and the 2 44 followin : Plant air s stems EK3.02 - Knowledge of the reasons for the following responses as they apply to 3.

295025 High Reactor Pressure I 3 x HIGH REACTOR PRESSURE : 9 45 Recirculation pump trip: Plant-Specific

ES-401 2 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

EA1 .01 Ability to operate and/or monitor 295026 Suppression Pool High the following as they apply to 4.

Water Temp. I 5 x suppression pool high water 1 46 tern erature: Su ression ool coolin AK3.01 - Knowledge of the reasons for 295016 Control Room the following responses as they apply to 4.

Abandonment I 7 x CONTROL ROOM ABANDONMENT : 1 47 Reactor SCRAM AA1 .01 -Ability to operate and/or monitor the following as they apply to 295004 Partial or Total Loss of DC 3.

Pwr/6 x PARTIAL OR COMPLETE LOSS OF 3

48 D.C. POWER : D.C. electrical distribution s stems EA 1.17 - Ability to operate and/or monitor the following as they apply to 3.

295024 High Drywell Pressure I 5 x HIGH DRYWELL PRESSURE: 9 49 Containment spra : Plant-Specific AA 1.02 - Ability to operate and/or 295023 Refueling Ace Cooling monitor the following as they apply to 2.

Mode I 8 x REFUELING ACCIDENTS : Fuel pool 9 50 COOiin and cleanu s stem EA2.06 - Ability to determine and/or 295028 High Drywell Temperature interpret the following as they apply to 3.

51 I5 HIGH DRYWELL TEMPERATURE: 7 reactor water level EA2.03 - Ability to determine and/or 295038 High Off-site Release Rate interpret the following as they apply to 3.5 52

/9 HIGH OFF-SITE RELEASE RATE :

Radiation levels AA2.04 - Ability to determine and/or 295003 Partial or Complete Loss interpret the following as they apply to 3.

53 of AC I 6 PARTIAL OR COMPLETE LOSS OF 5 A.C. POWER: S stem lineu s 295018 Partial or Total Loss of 2.4.11 - Knowledge of abnormal 4.

54 ccw /8 condition procedures 0 2.1.27 - Conduct of Operations:

700000 Generator Voltage and 3.

Knowledge of system purpose and I or 55 Electric Grid Disturbances 9 function.

2.1. 7- Conduct of Operations: ability to evaluate plant performance and make 295021 Loss of Shutdown Cooling operational judgements based on 4.4 56 14 operating characteristics, reactor behavior, and instrument interpretation.

EA2.04 - Ability to determine and/or interpret the following as they apply to 295030 Low Suppression Pool 3.

LOW SUPPRESSION POOL WATER 57 Water Level I 5 5 LEVEL : Drywell/ suppression chamber differential ressure: Mark-1&11 EK1 .03 - Knowledge of the operational implications of the following concepts as 295037 SCRAM Conditions they apply to SCRAM CONDITION 4.2 Present and Reactor Power Above x PRESENT AND REACTOR POWER 58 APRM Downscale or Unknown I 1 ABOVE APRM DOWNSCALE OR UNKNOWN: Boron effects on reactor power (SBLC)

KIA Category Totals: 4 3 3 3 Group Point Total: 20/7

ES-401 3 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

l1\2 03 :\hilit" w dctcnnine and\ir illlcrprct soonoo i ligh '* i rvn I!) drogcn the fol1P11 ing as th,*1, apply t<> high primar\

."ix 8.l

(\me. cnntainmi.:nt hJ drnµcn ('tmcc1Itration"I:

cornhustibk lin111' for dr; 11 di.

2.1.32 - <'ondud ,,r Operation:<: i\bilit1 t<>

2<)'!1 I:; incomplete SCRAM i c'Xplain and apply ail ')'1l'm limits and 4.P 84 pn:c:iut1rnb.

AA2.fl4 - i\bilit1 t!l determine and*or 2'15008 High lkachlr \Vatcr I c1cl int.:rprl.'t the f\111011 ing <h lhl.') appl) W  ; .l 8~

2 I II< ill RI;\(' I OR \\Al IR I !:VI .I l katup rate: Plant-Spcdlc EKI.Ol - Knowledge of the operational implications of the following concepts as 500000 High CTMT Hydrogen 3.

Cone. 15 x they apply to HIGH CONTAINMENT 3

59 HYDROGEN CONCENTRATIONS:

Containment inte rit AK2.04 - Knowledge of the interrelations between HIGH DRYWELL PRESSURE 2.6 295010 High Drywell Pressure 15 x and the following: Nitrogen makeup system:

60 Plant-S ecific AK3.02 - Knowledge of the reasons for the 295014 Inadvertent Reactivity following responses as they apply to 3.

Addition/ I x INADVERTENT REACTIVITY 7 61 ADDITION: Control rod blocks AA! .02 - Ability to operate and/or monitor 4.

295015 Incomplete SCRAM I 1 x the following as they apply to 0

62 INCOMPLETE SCRAM : RPS AA2.0l -Ability to determine and/or 295009 Low Reactor Water Level interpret the following as they apply to 4.

63 12 LOW REACTOR WATER LEVEL : 2 Reactor water level 2.4.49 - Emergency Procedures I Plan:

Ability to perform without reference to 295008 High Reactor Water Level 4.

procedures those actions that require 64 12 6 immediate operation of system components and controls.

AK2.0l - Knowledge of the interrelations 295012 High Drywell 3.

Temperature I 5 x between high drywell temperature and the 4

65 followin : Drywell ventilation.

KIA Category Totals: 2 Group Point Total: 713

ES-401 4 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G Q#

1 2 3 4 5 6 1 3 4

ES-401 4 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#

1 2 3 4 5 6 1 3 4

,\2 0 I - 1\hilHy t<l I a) predict the impact' 111' tile follo11 ing on th<:

l'Nl\ ll RRUl'l 1\IHJ: f'()\\ IR SU'l'LY ('\.Ci!)( ) , and lb) 2(12002 I 'I'\ 11\C:llCJ based on tlH>sc prc:dictions, thl' ,;,:-; 811 pi occdur\2-" to cnrn.::cr. cu11troi. 1)r mitigate the c1m\cqucncc'; uf 1lh)..;;c abnormal nmditinns or upcratiuns l :ndcr rnlt:igc 1\2 07 - *\bi lit' 1<l la) predict the imp:Kh ,,fthc fdlo11i11g on the I \11 l<Jil v:Y (il\lR \I OR<;

tlllLSr:I JI l), and ibl b:hs'd on thPsc prcdktion,, uss* p1-.>cdurs*s le' 2h41l(H) U )(1S  :~. 7 87 correct, contrnL or mitigdtc tlw C(ll1'Cljlll."nCCS tif' th<J,l' i!fllhlJ!ll;ti condit1uns or operations: Lu's <>f off-site ptn\\'r durmg full-load h_*.:.;tino 2,2 ,,17 i\ bil it1 to determine 263(H)(I DC l:kct1 ical opcrabilit) and, or availabilll) ur .l 4 x~~

I )istributit111 sakty rdaled cquipm<:nl 2.2,22 - r quipmc:nt Cont111I 212000 i{f'S Kno\\ kdgc (lf liJlliliIH: C<llldill"llS 4 S'I for ope1ations and s;ikt1 lim1L; 2 2.42 - ,\[Ji lit\ hl ll'CP~rll!C S\,1s'lll param,*tcrs that arc entr)-k\ el 215110:; 11{\I l.h 90 c'1lllditi1ms l(>r T..:clrnical Spcciflcat11>11' K 1.01 - Knowledge of the physical connections and/or cause- effect 262001 AC Electrical relationships between AC Distribution x ELECTRICAL DISTRIBUTION 3.8 and the following: Emergency generators (diesel/jet)

K1 .08 - Knowledge of the physical connections and/or cause- effect relationships 206000 HPCl x between HIGH PRESSURE 3.0 2 COOLANT INJECTION SYSTEM and the following: AC.

power: BWR-2,3,4 K2.01 - Knowledge of electrical 218000 ADS x power supplies to the following: J, 1 3 ADS lo ic K2.01 - Knowledge of electrical 205000 Shutdown Cooling x power supplies to the following: 3.1 4 Pum motors K3,06 - Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION 2I2000 RPS x SYSTEM will have on following:

4,0 5 Scram air header solenoid operated valves K3.02 - Knowledge of the effect that a loss or malfunction of the (INSTRUMENT AIR SYSTEM) 300000 Instrument Air x will have on the following:

33 6 Systems having pneumatic valves and controls

ES-401 4 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#

1 2 3 4 5 6 1 3 4 K4.07 - Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design feature(s) 264000 EDGs x and/or interlocks which provide 3.3 7 for the following: Local operation and control K4.01 - Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) 261000 SGTS x and/or interlocks which provide 3.7 8 for the following: Automatic s stem initiation K5.04 - Knowledge of the operational implications of the following concepts as they apply 211000 SLC x to STANDBY LIQUID 3.1 9 CONTROL SYSTEM : Explosive Valve o eration K5.05 - Knowledge of the operational implications of the following concepts as they apply 239002 SRYs x to RELIEF/SAFETY VALVES:

2.6 IO Discharge line quencher o eration K6.08 - Knowledge of the effect that a loss or malfunction of the 209001 LPCS x following will have on the LOW 2.9 II PRESSURE CORE SPRAY SYSTEM : Keep fill s stem K6.12 - Knowledge of the effect that a loss or malfunction of the 203000 RHR/LPCI: Injection following will have on the Mode x RHR/LPCI: INJECTION MODE 2.7 12 (PLANT SPECIFIC) : ECCS room inte rit A1 .04 -Ability to predict and/or monitor changes in parameters associated with operating the 215004 Source Range Monitor SOURCE RANGE MONITOR 3.5 13 (SRM) SYSTEM controls including: Control rod block status A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 263000 DC Electrical Distribution x D.C. ELECTRICAL 2.5 14 DISTRIBUTION controls including: Battery char in /dischar in rate A2.03 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION 223002 PCIS/Nuclear Steam SYSTEM/NUCLEAR STEAM Supply Shutoff SUPPLY SHUT-OFF; and (b) 3.0 15 based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or o erations: s stem lo ic failures

ES-401 4 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#

1 2 3 4 5 6 1 3 4 K4.01 - Knowledge of UPS (A.C./D.C.) design feature(s) and/or interlocks which provide 262002 UPS (AC/DC) x for the following: Transfer from 3.1 16 preferred power to alternate ower su plies.

A3.01 - Ability to monitor automatic operations of the 215003 IRM INTERMEDIATE RANGE 3.3 17 MONITOR (IRM) SYSTEM includin : Meters and recorders A3.08 - Ability to monitor automatic operations of the AVERAGE POWER RANGE 215005 APRM I LPRM MONITOR/LOCAL POWER 3.7 18 RANGE MONITOR SYSTEM including: Control rod block status A4.02 - Ability to manually operate and/or monitor in the 259002 Reactor Water Level control room: All individual 3.7 19 Control component controllers in the automatic mode A4.01 - Ability to manually operate and/or monitor in the 217000 RCIC 3.7 20 control room: RCIC turbine s eed 2.4.11 - Emergency Procedures 400000 Component Cooling I Plan; Knowledge of abnormal 2.7 21 Water condition procedures 2.2.39 - Knowledge of less than 206000 HPCI or equal to one hour tech spec 3.9 22 action statements for s stems.

K4.02 - Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or 300000 Instrument Air x interlocks which provide for the 3.0 23 following: Cross-over to other air s stems A3.01 - Ability to monitor automatic operations of the CCWS including: Setpoints on 400000 Component Cooling instrument signal levels for 3.0 24 Water normal operations.warnings, and trips that are applicable to the ccws K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the 217000 RCIC x REACTOR CORE ISOLATION 3.4 25 COOLING SYSTEM (RCIC):

Electrical ower 2.4.20 - Emergency Procedures 211000 SLC I Plan: Knowledge of operational 3.8 26 implications of EOP warnings, cautions, and notes.

KIA Category Totals: 2 2 2 3 2 3 2 Group Point Total: 26/'

ES-401 5 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

ES-401 5 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System #I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

\~ (12 - ;\hilit) to (al prc'dict the illlp<lCls of tiJC !t>llP\\ lllg (>Jl the SJ"CONDARY U.lNT
\IN\11 ' I .

and tb) based on tJm,c prcdid101h.

2'!0001 'll'cnndary C l\IT ')I use: prnccdurcs tn cm-reel. cont ml.

(_)f 111iti~::llc th..: c.:nn~~qu~nc.:t.>* {lf llH"c alrnonnal conditi,,n<., or opcrati(lll:i: l'.\.cc*ssivc outkakagc*

2.4 .45 - .-\bilil\ to prioriti;i: and 24501)() Mmn *1 urhinc ( icn. {)_?,

interpret the signilicancc of each 4.2

\ux.

~Hl11uth.:ia1or or alann.

1\2.03 - .\bi lit; It> (a) predict the irnp;icb uf the follo11 ing on the ROD Ill ll(k 'v1UNll OR SYS 11'.\1. and th) h;bcd on tlhhC pn:dictillth. u:<c pwc.:dur,*s to 21500.2 RB\1 correct. control. or mitigatl* the i ) 'H consequences ot'thtisc ahnPJ mal conditiun:< or opcrat ion,: I .thS or asspuatcd rcli:n:nc:c ,\f'RM channd BWR-3.4.5 Kl .01 - Knowledge of the physical connections and/or cause- effect relationships between 29000 I Secondary CTMT x SECONDARY CONTAINMENT 3.3 27 and the following: Reactor building ventilation: Plant-S ecific A3.05 - Ability to monitor automatic operations of the 226001 RHR/LPCI: CTMT RHR/LPCI: Containment spray 4.0 28 Spray Mode system mode including:

containment res sure.

K3.08 - Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT 22300 I Primary CTMT and SYSTEM AND AUXILIARIES Aux.

x will have on following:

2.7 29 Pneumatically operated valves internal to containment/drywell:

Plant-S ecific K4.05 - Knowledge of CONTROL ROD DRIVE HYDRAULIC SYSTEM design 201001 CRD Hydraulic x feature(s) and/or interlocks 3.8 30 which provide for the following:

Control rod SCRAM A 1.08 - ability to predict and/or monitor changes in parameters 271000 Off-gas x associated with operating the 3.1 31 offgas system controls including s stem flow.

K6.01 - Knowledge of the effect that a loss or malfunction of the 290003 Control Room HY AC x following will have on the 2.7 32 CONTROL ROOM HVAC:

Electrical power A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 216000 Nuclear Boiler Inst. x NUCLEAR BOILER 3.4 33 INSTRUMENTATION controls

ES-401 5 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A2.16 - Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM; and (b) based on those predictions, use 272000 Radiation Monitoring 2.7 34 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Instrument malfunctions A3.10 - Ability to monitor automatic operations of the 241000 Reactor/Turbine REACTOR/TURBINE 3.3 35 Pressure Regulator PRESSURE REGULATING SYSTEM including: Main sto /throttle valve o eration A4.03 - Ability to manually 215001 Traversing In-core operate and/or monitor in the 3.0 36 Probe control room: Isolation valves:

Mark-1&11 Not-BWR1 2.2.44 - ability to interpret control room indications to verify the status and operation of a 259001 Reactor Feedwater system, and understand how 4.2 37 operator actions and directives affect plant and system conditions.

KS.06 - Knowledge of the operational implications of the 233000 Fuel Pool following concepts as they apply Cooling/Cleanup x to FUEL POOL COOLING AND 2.5 38 CLEAN-UP : maximum normal heat load K/A Category Totals: 2 Group Point Total: 121;

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Hope Creek 2016 NRC Date: 08/22/16 RO SRO-Only Category KIA# Topic IR Q# IR Q#

2.1.41 Knowledge of the refueling process. 3.7 94

1. Knowledge of how to conduct system Conduct 2.1.29 lineups, such as valves, breakers, switches, 4.1 66 of Operations etc.

Knowledge of shift or short-term relief 2.1.3 3.7 67 turnover practices 2.1.27 Knowledge of the refueling process 2.8 75 Subtotal Ability to interpret control room indications to Jlfll 3 ,Jfo:::;:.::::1::. **t: 2 verify the status and operation of a system, 2.2.44 4.4 95 and understand how operator actions and directives effect plant and system conditions.

Ability to apply technical specifications for a 2.2.40 4.7 98 system.

Knowledge of the process for making a 2.2.5 3.2 100

2. desiqn or operatinq chanqes to the facility Equipment Control Knowledge of less than one hour technical 2.2.39 3.9 68 specification action statements for systems.

Knowledge of controlling equipment 2.2.14 3.4 69 configuration Subtotal ....*.. 2 ... ... 2 Knowledge of radiation exposure limits under 2.3.4 3.17 96 normal or emergency conditions.

Knowledge of radiation monitoring systems, 3.

such as fixed radiation monitors and alarms, Radiation 2.3.15 2.9 71 portable survey instruments, personnel Control monitoring equipment, etc.

Knowledge of Radialogical Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor 2.3.13 3.4 74 alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal Knowledge of abnormal condition 2.4.11 4.2 97 rocedures.

Knowledge of the bases for prioritizing safety 2.4.22 functions during abnormal/emergency 4.4 99 o erations.

Ability to perform without reference to 4.

procedures those actions that require Emergency 2.4.49 4.6 70 immediate operation of system components Procedures I and controls Plan 2.4.6 Knowledge of EOP mitigation strategies. 3.7 72 Knowledge of procedures relating to a 2.4.28 3.2 73 securit event.

Subtotal Tier 3 Point Total

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Grouo Selected KlA

'#9: Cannot write an operationally valid question. Randomly 2/1 K5.02 selected K5.04

  1. 15: Cannot write an operationally valid question. Randomly 2/1 A2.08 selected A2.03

'#16: Cannot write an operationally valid question. Randomly 2/1 A2.01 selected K4.01

  1. 21: Cannot write an operationally valid question. Randomly 2/1 2.4.30 selected 2.4.11

'#22: Cannot write an RO level of knowledge question on this 2/1 2.2.22 KIA. Randomly selected 2.2.39

  1. 28: KIA subject is oversampled (same as question #4).

212 K2.02 Randomly selected A3.05

'#31: Cannot write an operationally valid question. Randomly 2/2 K5.06 selected A1 .08 l:f.33: Cannot write an operationally valid question. Randomly 212 A1.04 selected A 1.01

  1. 37: Cannot write an operationally valid question. Randomly 212 2.2.36 selected 2.2.44

'#38: Cannot write an operationally valid question. Randomly 2/2 K5.07 selected K5.06

  1. 51: Cannot write an operationally valid question. Randomly 1/1 EA2.06 selected EA2.03
  1. 54: Cannot write an operationally valid question. Randomly 1/1 2.4.8 selected 2.4.11
  1. 56: Cannot write question based on computer read-out.

1/1 2.1.19 Randomly selected 2.1. 7

  1. 66: Cannot write an operationally valid question. Randomly 3 2.1.34 selected 2.1.3
  1. 69: Cannot write an operationally valid question. Randomly 3 2.2.40 selected 2.2.14 3 2.3.5 #70: KIA is oversampled. Randomly selected 2.4.49

'f#.75: Cannot write an operationally valid question. Randomly 3 2.1.27 selected 2. 1.41 295016 #77: Cannot write an operationally valid question. Randomly 1/1 AA2.05 selected 295031, EA2.04

'f#.78: Cannot write SRO level question. Randomly selected 1/1 EA2.02 EA2.01

'f#.83: Cannot write an operationally valid question. Randomly 1/2 295017 selected 500000

'f#.88: Cannot write an SRO level question. Randomly selected 2/1 2.4.49 2.2.37

  1. 90: Cannot write an operationally valid question. Randomly 2/1 2.4.2 selected 2.2.42 290003 'f#.91: JPM already tests this subject (oversample). Randomly 212 A2.04 selected 290001 A2.02

'f#.92: Cannot write an operationally valid question. Randomly 212 2.4.46 selected 2.4.45

'f#.93: Operating scenario already tests this KIA (oversample).

212 A2.02 Randomly selected A2.03

  1. 96: KIA is already selected for Tier 3 (oversample).

3 2.3.15 Randomly selected 2.3.4

  1. 100: KIA is tested in the operating test. Randomly selected 3 2.1.6 2.2.5.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Hope Creek Generating Station Date of Examination: 8/22/16 Examination Level: RO [J SRO D Operating Test Number: 1 Type Administrative Topic (see Note) Describe activity to be performed Code*

ROA.1 Perform The Watchstanding Duties Of The Conduct of Operations N,R Nuclear Control Room Operator Conduct of Operations M,R ROA.2 Respond to A Fuel Pool Cooling Malfunction ROA.3 Perform A Manual Tagout With SAP System Equipment Control N,R Inoperable ROA.4 Respond To An Abnormal Release Of Radiation Control D, P, S Gaseous Radioactivity Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (;:: 1)

(P)revious 2 exams (s 1; randomly selected)

ES-301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Hope Creek Generating Station Date of Examination: 8/22/16 Examination Level: ROD SRO ~ Operating Test Number:

Type Administrative Topic (see Note) Describe activity to be performed Code*

Conduct of Operations D,R SROA.1 Complete the Daily Surveillance Logs SROA.2 Ensure The Operating Shift Is Adequately Conduct of Operations N,R Manned Equipment Control N,R SROA.3 Perform WCD Review and Pre-Approval SROA.4 Respond To An Abnormal Release Of Radiation Control D, P, S Gaseous Radioactivity SROA.5 Utilize The ECG To Determine The Emergency Classification And/Or Emergency Plan D,R Reportability Of An Event And/Or Plant Condition NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:s; 3 for ROs; :s; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (?: 1)

(P)revious 2 exams (:s; 1; randomly selected)

ES-301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Generating Station Date of Examination: 8/22/16 Exam Level: RO C8J SRO-ID SRO-U D Operating Test No:

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function

a. BF011 Exercise Control Rod, Respond To Uncoupled Rod A,D, EN,S 1
b. AEOOS Place The First RFPT In Service D,S 2
c. AC008 Perform a Cooldown Using Bypass Valves D, L, S 3
d. BJ014 Place HPCI in Full Flow Test Operation A, D, EN, L, S 4
e. BC003 Respond To A Loss Of Shutdown Cooling D, L 5
f. PB001 Shift A 4160 V 1E Bus To Alternate Feeder A,N,S 6
g. GK002 Isolate the Control Room HVAC System A,EN,M,S 9
h. EG002 Transfer T ACS to the Standby SACS Loop D,S 8 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

I. SB015 Transfer RPS Bus A/B Power From Alternate Source To RPS MG A,D 7 Set

j. BF002 Shift In-Service CRD Stabilizing Valves D, R 2
k. PNOOS Respond To A Station Blackout E, L, N 6
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank s9J SB I S4 (E)mergency or abnormal in-plant .'.".. 1 I .'.".. 1 I .'.".. 1 (EN)gineered safety feature .'.".. 1 I .'.".. 1 I .'.".. 1 (control room system)

(L)ow-Power I Shutdown .'.".. 1 I .'.".. 1 I .'.".. 1 (N)ew or (M)odified from bank including 1(A) .'.".. 2 I .'."._2 I .'.".. 1 (P)revious 2 exams S31 S3 I s 2 (randomly selected)

(R)CA .'.".. 1 I .'.".. 1 I .'.".. 1 I

(S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Generating Station Date of Examination: 8/22/16 Exam Level: ROD SR0-1 iZ! SRO-U D Operating Test No:

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function

a. BF011 Exercise Control Rod, Respond To Uncoupled Rod A, D, EN,S 1
b. AE005 Place The First RFPT In Service D,S 2
c. AC008 Perform a Cooldown Using Bypass Valves D, L, S 3
d. BJ014 Place HPCI in Full Flow Test Operation A, D, EN, L, S 4
e. BC003 Respond To A Loss Of Shutdown Cooling D, L 5
f. PB001 Shift A 4160 V 1E Bus To Alternate Feeder A,N,S 6
g. GK002 Isolate the Control Room HVAC System A, EN,M,S 9 h.

In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. SB015 Transfer RPS Bus A/B Power From Alternate Source To RPS MG A, D 7 Set
j. BF002 Shift In-Service CRD Stabilizing Valves D,R 2
k. PN005 Respond To A Station Blackout E, L, N 6
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :5_9/ :5_8 I :5_4 (E)mergency or abnormal in-plant ~ 1I ~1 I ~1 (EN)gineered safety feature ~ 1I ~1 I ~ 1 (control room system)

(L)ow-Power I Shutdown ~ 1I ~1 I ~1 (N)ew or (M)odified from bank including 1(A) ~2/ ~2 I ~1 (P)revious 2 exams :5_3/ :5_3 I :s 2 (randomly selected)

(R)CA ~ 1 I ~1 I ~1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Generating Station Date of Examination: 8/22/16 Exam Level: ROD SRO-ID SRO-U [gj Operating Test No:

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function a.

b.

c.

d. BJ014 Place HPCI in Full Flow Test Operation A, D, EN, L, S 4
e. BC003 Respond To A Loss Of Shutdown Cooling D, L 5 f.
g. GK002 Isolate the Control Room HVAC System A,EN,M,S 9 h.

In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. SB015 Transfer RPS Bus A/B Power From Alternate Source To RPS MG A, D 7 Set j.
k. PN005 Respond To A Station Blackout E, L, N 6
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank S91 SB I S4 (E)mergency or abnormal in-plant _:: 1 I .::. 1 I .::. 1 (EN)gineered safety feature _:: 1 I .::. 1 I _:: 1 (control room system)

(L)ow-Power I Shutdown _:: 1 I .::. 1 I .::. 1 (N)ew or (M)odified from bank including 1(A) _:: 2 I _::2 I .::. 1 (P)revious 2 exams S31 S3 I s 2 (randomly selected)

(R)CA _:: 1 I .::. 1 I .::. 1 (S)imulator ES-301, Page 23 of 27

Appendix D Scenario Outline Form ES-D-1 Facility: HOPE CREEK Scenario No.: 1 Op-Test No.:

Examiners: Operators:

Initial Conditions: The Qlant at aQQroximatelzi 88% QOwer. Power ascension in Qrogress following maintenance on RFPT AP101, and an Emergenczi Diesel Generator test in Qrogress.

Turnover: ComQlete EDG Surveillance. Continue with QOWer ascension to Rated Thermal Power.

Event Malf. Event Event No. No. Type* Description N Remove EDG From Service TS EDG Trip R Raise Reactor power using Control Rods.

c Stuck Control Rod c Seismic Event (>OBE) I EHC Filter Clogging C,TS Safety Relief Valve Stuck Open M ATWS c SBLC Failure to Auto Start c RWCU Failure to Automatically Isolate c Loss of EHC c RHR Pump Trip

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor (TS) Technical Specification D-37

Appendix D Scenario Outline Form ES-D-1 Facility: HOPE CREEK Scenario No.: 2 Op-Test No.:

Examiners: Operators:

Initial Conditions: A Reactor startuQ is in 12rogress following a forced outage. Current QOwer is 9%.

Nitrogen MakeuQ to the D~well is in 12rogress following lnerting the Containment.

Turnover: Continue with Reactor startuQ.

Event Malf. Event Event No. No. Type* Description N Start Circulating Water Pumps R Raise Power With Control Rods I, TS Flow Unit Failure C,TS Loss of 80481 120 VAC 1E Inverter M Steam Leak in the Steam Tunnel c MSIV Failure to Automatically Isolate c Small Break LOCA c Suppression Pool Leak

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor (TS) Technical Specification 0-37

Appendix D Scenario Outline Form ES-D-1 Facility: HOPE CREEK Scenario No.: 3 Op-Test No.:

Examiners: Operators:

Initial Conditions: The Qlant is at 95% QOwer with QOWer ascension in Qrogress.

Turnover: Continue QOWer ascension to Rated Thermal Power.

Event Malf. Event Event No. No. Type* Description R, TS Recirculation Pump Runaway c Primary Containment Instrument Gas Leak C,TS Loss of 10A110 c Loss of Feedwater with Automatic Scram Failure c Trip of HPCI M LOCA c Failure of 'A' Channel Core Spray and RHR Logics

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor (TS) Technical Specification D-37
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