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

I 2

3 G

Total A2 G*

I otal I.

4 3

2 3

20 3

4 7

Emergency 2

2 7

2

~

.)

Plant Tier Evolutions Totals 5

5 3

4 27 5

5 10

2.

Plant Systems 2

Tier Totals 2

2 2

0 3

2 3

3. Generic Knowledge & Abilities Categories 4

2 5

3 3

3 2

3 2

2 4

4 2

5 2

3 2

3 2

3 26 2

3 5

12 0

2 3

4 38 4

4 8

4 10 7

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 295fl:' I i\\dcquak ('ore ( "onling 2 2'l502h Surrn:ss1011 Po,ll I ligh Wakr lc111p

~

2<J51J06 SCRA \\I I 2951)18 High on~,jh; H.clCil'C Rate 9

29500 ! Parllal or ( *(ln!rkl<: I os, of l nrcccl t lll"C l hm C1rculat1on I &

cj 295fll!*l l'anial or I ntal I os,; pf DC l'wr 6 295006 SCRAM I I 295031 Reactor Low Water Level 12 600000 Plant Fire On-site I 8 295005 Main Turbine Generator Trip/ 3 29500 I Partial or Complete Loss of Forced Core Flow Circulation I I

&4 295019 Partial or Total Loss of Inst Air/ 8 295025 High Reactor Pressure I 3 x

x x

K2 K3 A1 x

x x

x A2 G

KIA Topic(s)

L;\\2 02 - ;\\hilit) to dclc11ninc <m<Lnr i11tl'rpret th.: folhmi11g as thev appl1 to 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<>

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

2.4 4 l - l'rncrgcnc) Prnccdurcs Plan Kno11 ledge of" the cmcrgL'nc1* action lc\\"<:l thresholds and classilkat1011' 2.4..2 l - I ~ml..'rg1..*nc~* Pro\\xdurcs !'Ian Knn\\\\ kdgc,,r tlu: paramclcrs and l11gic ll'l'd to assc*ss tile slallh 1!f said) l[11Ktl\\ll1'** su<."11 as rcact1vn1* contmL core cooling ;md llc*at rL'nlO\\ aL r~a(,:hn Ct)olant '~ sten1 inkgrity.

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

2.240 - l quipmrnt Contwl ;\\ililit\\ to apph technical spccification' for a S\\"skn1.

AKl.02 - Knowledge of the operational implications of the following concepts as the appl to SCRAM : Shutdown margin EKl.03 - Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL : Water level effects on reactor power AKI.02 - Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Fi htin AK2.03 - Knowledge of the interrelations between MAIN TURBINE GENERA TOR TRIP and the following: Recirculation s stem AK2.06 - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the following:

Reactor power AK2.14 - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the followin : Plant air s stems EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE :

Recirculation pump trip: Plant-Specific Imp.

4 (J 42 I h i.7

3.

4

3.

7

2.

9

3.

2

3.

8

3.

2

3.

9 Q#

77 78 8()

XI 39 40 41 42 43 44 45

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 x

the following as they apply to

4.

46 Water Temp. I 5 suppression pool high water 1

tern erature: Su ression ool coolin AK3.01 - Knowledge of the reasons for 295016 Control Room x

the following responses as they apply to

4.

47 Abandonment I 7 CONTROL ROOM ABANDONMENT :

1 Reactor SCRAM AA1.01 -Ability to operate and/or 295004 Partial or Total Loss of DC monitor the following as they apply to

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 295024 High Drywell Pressure I 5 x

monitor the following as they apply to

3.

49 HIGH DRYWELL PRESSURE:

9 Containment spra : Plant-Specific AA 1.02 - Ability to operate and/or 295023 Refueling Ace Cooling x

monitor the following as they apply to

2.

50 Mode I 8 REFUELING ACCIDENTS : Fuel pool 9

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 I 5 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 RA TE :

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

700000 Generator Voltage and 2.1.27 - Conduct of Operations:

3.

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

9 2.1. 7-Conduct of Operations: ability to 295021 Loss of Shutdown Cooling evaluate plant performance and make 14 operational judgements based on 4.4 56 operating characteristics, reactor behavior, and instrument interpretation.

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

3.

LOW SUPPRESSION POOL WATER 57 Water Level I 5 LEVEL : Drywell/ suppression chamber 5

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

Hope Creek 2016 NRC Written Examination Outline Form ES-401-1 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 500000 High CTMT Hydrogen implications of the following concepts as

3.

x they apply to HIGH CONTAINMENT 59 Cone. 15 HYDROGEN CONCENTRATIONS:

3 Containment inte rit AK2.04 - Knowledge of the interrelations 295010 High Drywell Pressure 15 x

between HIGH DRYWELL PRESSURE 2.6 60 and the following: Nitrogen makeup system:

Plant-S ecific AK3.02 - Knowledge of the reasons for the 295014 Inadvertent Reactivity x

following responses as they apply to

3.

61 Addition/ I INADVERTENT REACTIVITY 7

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:

295008 High Reactor Water Level Ability to perform without reference to

4.

12 procedures those actions that require 6

64 immediate operation of system components and controls.

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

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 System #I Name K

K K

1 2

3 4

Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

Form ES-401-1 Imp Q#

ES-401 System # I Name K

K K

1 2

3 2(12002 I 'I'\\ 11\\C:llCJ 2h41l(H) U )(1S 263(H)(I DC l:kct1 ical I )istributit111 212000 i{f'S 215110:; 11{\\I 262001 AC Electrical x

Distribution 206000 HPCl x

218000 ADS x

205000 Shutdown Cooling x

2I2000 RPS x

300000 Instrument Air x

4 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A2 A

A G

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) based on tlH>sc prc:dictions, thl' 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' 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 opcrabilit) and, or availabilll) ur sakty rdaled cquipm<:nl 2.2,22 - r quipmc:nt Cont111I Kno\\\\ kdgc (lf liJlliliIH: C<llldill"llS 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 c'1lllditi1ms l(>r T..:clrnical Spcciflcat11>11' K 1.01 - Knowledge of the physical connections and/or cause-effect relationships between AC ELECTRICAL DISTRIBUTION and the following: Emergency generators (diesel/jet)

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

power: BWR-2,3,4 K2.01 - Knowledge of electrical power supplies to the following:

ADS lo ic K2.01 - Knowledge of electrical power supplies to the following:

Pum motors K3,06 - Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on following:

Scram air header solenoid operated valves K3.02 - Knowledge of the effect that a loss or malfunction of the (INSTRUMENT AIR SYSTEM) will have on the following:

Systems having pneumatic valves and controls Imp Q#

811

~. 7 87

.l 4 x~~

4 S'I l.h 90 3.8 3.0 2

J, 1 3

3.1 4

4,0 5

33 6

ES-401 System # I Name K

K K

1 2

3 264000 EDGs 261000 SGTS 211000 SLC 239002 SRYs 209001 LPCS 203000 RHR/LPCI: Injection Mode 215004 Source Range Monitor 263000 DC Electrical Distribution 223002 PCIS/Nuclear Steam Supply Shutoff 4

Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

K4.07 - Knowledge of EMERGENCY GENERATORS x

(DIESEL/JET) design feature(s) and/or interlocks which provide for the following: Local operation and control K4.01 - Knowledge of STANDBY GAS TREATMENT x

SYSTEM design feature(s) and/or interlocks which provide for the following: Automatic s stem initiation K5.04 - Knowledge of the operational implications of the x

following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM : Explosive Valve o eration K5.05 - Knowledge of the operational implications of the x

following concepts as they apply to RELIEF/SAFETY VALVES:

Discharge line quencher o eration K6.08 - Knowledge of the effect that a loss or malfunction of the x

following will have on the LOW PRESSURE CORE SPRAY SYSTEM : Keep fill s stem K6.12 - Knowledge of the effect that a loss or malfunction of the x

following will have on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) : ECCS room inte rit A1.04 -Ability to predict and/or monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including: Control rod block status A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the x

D.C. ELECTRICAL 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 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) 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 Imp Q#

3.3 7

3.7 8

3.1 9

2.6 IO 2.9 II 2.7 12 3.5 13 2.5 14 3.0 15

ES-401 System # I Name K

K K

1 2

3 262002 UPS (AC/DC) 215003 IRM 215005 APRM I LPRM 259002 Reactor Water Level Control 217000 RCIC 400000 Component Cooling Water 206000 HPCI 300000 Instrument Air 400000 Component Cooling Water 217000 RCIC 211000 SLC KIA Category Totals:

2 2

2 4

Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

K4.01 - Knowledge of UPS (A.C./D.C.) design feature(s) x and/or interlocks which provide for the following: Transfer from preferred power to alternate ower su plies.

A3.01 - Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM includin : Meters and recorders A3.08 - Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including: Control rod block status A4.02 - Ability to manually operate and/or monitor in the control room: All individual component controllers in the automatic mode A4.01 - Ability to manually operate and/or monitor in the control room: RCIC turbine s eed 2.4.11 - Emergency Procedures I Plan; Knowledge of abnormal condition procedures 2.2.39 - Knowledge of less than or equal to one hour tech spec action statements for s stems.

K4.02 - Knowledge of (INSTRUMENT AIR SYSTEM) x design feature(s) and or interlocks which provide for the following: Cross-over to other air s stems A3.01 - Ability to monitor automatic operations of the CCWS including: Setpoints on instrument signal levels for normal operations.warnings, and trips that are applicable to the ccws K6.01 - Knowledge of the effect that a loss or malfunction of the x

following will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC):

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

3 2

3 2

Group Point Total:

Imp Q#

3.1 16 3.3 17 3.7 18 3.7 19 3.7 20 2.7 21 3.9 22 3.0 23 3.0 24 3.4 25 3.8 26 26/'

ES-401 System # I Name K

K K

1 2

3 5

Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

A A2 A

A G

4 5

6 1

3 4

Form ES-401-1 Imp.

Q

ES-401 System #I Name K

K K

1 2

3 2'!0001 'll'cnndary C l\\IT 24501)() Mmn *1 urhinc ( icn.

\\ux.

21500.2 RB\\1 29000 I Secondary CTMT x

226001 RHR/LPCI: CTMT Spray Mode 22300 I Primary CTMT and x

Aux.

201001 CRD Hydraulic 271000 Off-gas 290003 Control Room HY AC 216000 Nuclear Boiler Inst.

5 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

A A2 A

A G

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.

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 interpret the signilicancc of each

~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 correct. control. or mitigatl* the 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 SECONDARY CONTAINMENT and the following: Reactor building ventilation: Plant-S ecific A3.05 - Ability to monitor automatic operations of the RHR/LPCI: Containment spray system mode including:

containment res sure.

K3.08 - Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES will have on following:

Pneumatically operated valves internal to containment/drywell:

Plant-S ecific K4.05 - Knowledge of CONTROL ROD DRIVE x

HYDRAULIC SYSTEM design feature(s) and/or interlocks which provide for the following:

Control rod SCRAM A 1.08 - ability to predict and/or monitor changes in parameters x

associated with operating the offgas system controls including s stem flow.

K6.01 - Knowledge of the effect that a loss or malfunction of the x

following will have on the CONTROL ROOM HVAC:

Electrical power A 1.01 - Ability to predict and/or monitor changes in parameters x

associated with operating the NUCLEAR BOILER INSTRUMENTATION controls Imp.

Q

')I 4.2

{)_?,

i )

'H 3.3 27 4.0 28 2.7 29 3.8 30 3.1 31 2.7 32 3.4 33

ES-401 System # I Name K

K K

1 2

3 272000 Radiation Monitoring 241000 Reactor/Turbine Pressure Regulator 215001 Traversing In-core Probe 259001 Reactor Feedwater 233000 Fuel Pool Cooling/Cleanup K/A Category Totals:

5 Form ES-401-1 Hope Creek 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

A A2 A

A G

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 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 REACTOR/TURBINE PRESSURE REGULATING SYSTEM including: Main sto /throttle valve o eration A4.03 - Ability to manually operate and/or monitor in the 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 system, and understand how operator actions and directives affect plant and system conditions.

KS.06 - Knowledge of the operational implications of the x

following concepts as they apply to FUEL POOL COOLING AND CLEAN-UP : maximum normal heat load 2

Group Point Total:

Imp.

Q 2.7 34 3.3 35 3.0 36 4.2 37 2.5 38 121;

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility:

Hope Creek 2016 NRC Date:

08/22/16 Category RO SRO-Only 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.

2.1.3 Knowledge of shift or short-term relief 3.7 67 turnover practices 2.1.27 Knowledge of the refueling process 2.8 75 Subtotal Jlfll 3

,Jfo:::;:.::::1::.. **t:

2 Ability to interpret control room indications to 2.2.44 verify the status and operation of a system, 4.4 95 and understand how operator actions and directives effect plant and system conditions.

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

2.2.5 Knowledge of the process for making a 3.2 100

2.

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

3.9 68 2.2.14 Knowledge of controlling equipment 3.4 69 configuration Subtotal 2

2 2.3.4 Knowledge of radiation exposure limits under 3.17 96 normal or emergency conditions.

3.

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

Knowledge of Radialogical Safety Procedures pertaining to licensed operator 2.3.13 duties, such as response to radiation monitor 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 2.4.11 Knowledge of abnormal condition 4.2 97 rocedures.

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

4.

Ability to perform without reference to Emergency 2.4.49 procedures those actions that require 4.6 70 Procedures I immediate operation of system components Plan and controls 2.4.6 Knowledge of EOP mitigation strategies.

3.7 72 2.4.28 Knowledge of procedures relating to a 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 Kl A 2/1 K5.02

'#9: Cannot write an operationally valid question. Randomly selected K5.04 2/1 A2.08

  1. 15: Cannot write an operationally valid question. Randomly selected A2.03 2/1 A2.01

'#16: Cannot write an operationally valid question. Randomly selected K4.01 2/1 2.4.30

  1. 21: Cannot write an operationally valid question. Randomly selected 2.4.11 2/1 2.2.22

'#22: Cannot write an RO level of knowledge question on this KIA. Randomly selected 2.2.39 212 K2.02

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

Randomly selected A3.05 2/2 K5.06

'#31: Cannot write an operationally valid question. Randomly selected A1.08 212 A1.04 l:f.33: Cannot write an operationally valid question. Randomly selected A 1.01 212 2.2.36

  1. 37: Cannot write an operationally valid question. Randomly selected 2.2.44 2/2 K5.07

'#38: Cannot write an operationally valid question. Randomly selected K5.06 1/1 EA2.06

  1. 51: Cannot write an operationally valid question. Randomly selected EA2.03 1 /1 2.4.8
  1. 54: Cannot write an operationally valid question. Randomly selected 2.4.11 1/1 2.1.19
  1. 56: Cannot write question based on computer read-out.

Randomly selected 2.1. 7 3

2.1.34

  1. 66: Cannot write an operationally valid question. Randomly selected 2.1.3 3

2.2.40

  1. 69: Cannot write an operationally valid question. Randomly selected 2.2.14 3

2.3.5

  1. 70: KIA is oversampled. Randomly selected 2.4.49

3 2.1.27

'f#.75: Cannot write an operationally valid question. Randomly selected 2. 1.41 295016

  1. 77: Cannot write an operationally valid question. Randomly 1 /1 AA2.05 selected 295031, EA2.04 1/1 EA2.02

'f#.78: Cannot write SRO level question. Randomly selected EA2.01 1/2 295017

'f#.83: Cannot write an operationally valid question. Randomly selected 500000 2/1 2.4.49

'f#.88: Cannot write an SRO level question. Randomly selected 2.2.37 2/1 2.4.2

  1. 90: Cannot write an operationally valid question. Randomly selected 2.2.42 212 290003

'f#.91: JPM already tests this subject (oversample). Randomly A2.04 selected 290001 A2.02 212 2.4.46

'f#.92: Cannot write an operationally valid question. Randomly selected 2.4.45 212 A2.02

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

Randomly selected A2.03 3

2.3.15

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

Randomly selected 2.3.4 3

2.1.6

  1. 100: KIA is tested in the operating test. Randomly selected 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 Administrative Topic (see Note)

Type Describe activity to be performed Code*

Conduct of Operations N,R ROA.1 Perform The Watchstanding Duties Of The Nuclear Control Room Operator Conduct of Operations M,R ROA.2 Respond to A Fuel Pool Cooling Malfunction Equipment Control N,R ROA.3 Perform A Manual Tagout With SAP System Inoperable Radiation Control D, P, S ROA.4 Respond To An Abnormal Release Of 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:

Administrative Topic (see Note)

Type Describe activity to be performed Code*

Conduct of Operations D,R SROA.1 Complete the Daily Surveillance Logs Conduct of Operations N,R SROA.2 Ensure The Operating Shift Is Adequately Manned Equipment Control N,R SROA.3 Perform WCD Review and Pre-Approval Radiation Control D, P, S SROA.4 Respond To An Abnormal Release Of Gaseous Radioactivity SROA.5 Utilize The ECG To Determine The Emergency Plan D,R Emergency Classification And/Or 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 1 E 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 (S)imulator I

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 1 E 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

~ 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/ ~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 Set A, D 7

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 1 E 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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