ML17186A145

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Final Outlines (Folder 3)
ML17186A145
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 08/14/2016
From:
Public Service Enterprise Group
To:
Operations Branch I
Shared Package
ML15308A608 List:
References
TAC U01925
Download: ML17186A145 (22)
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ES-401 Written Examination Outline Form ES-401-1 Facility: Hope Creek 2016 NRC Date of Exam: 08/22/16 SRO-Only Point~

Tier Group K K K G Total A2 G* Total l 2 3 *

l. 4 3 3 3 20 3 4 7 Emergency 2 2 7 2 1 '

Plant Tier Evolutions 5 4 5 4 27 5 5 I0 Totals 2 2 2 3 2 3 2 2 3 2 3 26 2 3  :;

2.

2 2 12 0 2 '

Plant '

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

.' 4

3. Generic Knowledge & Abilities ,..,

10 I Categories ~

3 2 3 2 2 2 -

Note: I. Ensure that at least two topics from every applicable Kl A 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 Kl 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 +/-1 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. l.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 (JR) of 2.5 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 l and 2 from the shaded systems and Kl A categories.
7.
  • The generic (G) Kl As in Tiers l and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D. l .b of ES-401 for the applicable K/A'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 KIA numbers. descriptions, IRs. and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to IOCFR55.43

ES-401 2 Form ES-401-1 Hope Creek 2016 NRG 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#

1./\2.02 - \hility to (ktcnninc and\i1 interpret the* following as the' apply to 4 ()

Jll(ill DRYWEl L PRESSl!RL Dr;11cll tcm icraturc

!\i\2.0:' - Ability to determine a11dior 2951! I() l. "ntn>I RP<irn interpret the following w, the' appl; to 77

,\handonrncnt CONTROL ROOM AllANDON\1! NT Drvw<:ll r.:,surc L!\2.02 - ;\bilit> to dctcrlllinc amJior

.2'15026 Suppression i'nPl lligh int.'rprct the l(>llo\\ing > ion pool kl cl 2.2.3'! - Equipmcnt Control Kmn1kdgc c>f 2950011 SCF,,\\1 I kss than one huur technical -;pccirication 4.5 79 action swtcmcnts li>r system,.

2.4.41 - I :mcrgenc; Prnccdurcs Plan:

2'!5W~ 1ligh Ot1~s1tc RcJcc1,c Rah:

Knowlcdgc nfthc rncrgrncY actio11 lc1cl 4.(1 80

')

threshold<> and cla<>>illcation' 2.4.21 - L1rn:rgcric1 J'[()ccdurcs ! !'Ian:

hnn11 lcdgc of th<.' parameters and logic usd 2'i'l1() I l'a11ial or CPlllplctc I.1is' of 1<1 a" the status <lf<<;alcty fund ions. such l orn:d Cure l hJ\\ ( 'irculatiPn I & as rcacmit1* control, wrc cooling and hc'at ,I_() 81 4 runoval. reactor coolant ,ystcm intcgrit1-,

rnntairnncnt C<ll1ditirn10>. radiualli\ 11,* rclc<bC C<mlrol. de.

2()~1104 l'm1ial or rotal l .n,s of DC 2.2.40 - F4uipmcnt ( "tmli<li. r\bilitv tn apply P11r (, technical spccificat1<Jns for a s1-<tcm AKl.02 - Knowledge of the operational 295006 SCRAM I 1 x implications of the following concepts as 3.4 39 the a I to SCRAM : Shutdown mar in EKI.03 - Knowledge of the operational implications of the following concepts as 295031 Reactor Low Water Level

/2 x they apply to REACTOR LOW WATER 3.7 40 LEVEL : Water level effects on reactor power AKl.02 - Knowledge of the operation applications of the following concepts as 600000 Plant Fire On-site I 8 x they apply to Plant Fire On Site: Fire 2.9 41 Fightin AK2.03 - Knowledge of the interrelations 295005 Main Turbine Generator between MAIN TURBINE GENERA TOR Trip I 3 x TRIP and the following: Recirculation 3.2 42 system AK2.06 - Knowledge of the interrelations 295001 Partial or Complete Loss between PARTIAL OR COMPLETE of Forced Core Flow Circulation I 1 x LOSS OF FORCED CORE FLOW 3.8 43

&4 CIRCULATION and the following:

Reactor ower AK2.14 - Knowledge of the interrelations 295019 Partial or Total Loss of between PARTIAL OR COMPLETE Inst. Air I 8 x 3.2 44 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 295025 High Reactor Pressure I 3 x HIGH REACTOR PRESSURE :

3.9 45 Recirculation pum trip: Plant-Specific EK3.02 - Knowledge of the reasons for 295026 Suppression Pool High the following responses as they apply to Water Temp. I 5 x SUPPRESSION POOL HIGH WATER 3.9 46 TEMPERATURE: Suppression pool

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

AK3.01 - Knowledge of the reasons for 295016 Control Room the following responses as they apply to Abandonment I 7 x CONTROL ROOM ABANDONMENT :

4.1 47 Reactor SCRAM AA 1.01 - Ability to operate and/or monitor the following as they apply to 295004 Partial or Total Loss of DC Pwr/6 x PARTIAL OR COMPLETE LOSS OF 3.3 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 295024 High Drywell Pressure I 5 x HIGH DRYWELL PRESSURE:

3.9 49 Containment spra : Plant-Specific AA 1.02 - Ability to operate and/or 295023 Refueling Ace Cooling monitor the following as they apply to Mode I 8 x REFUELING ACCIDENTS : Fuel pool 2.9 50 COOiin and cleanup s stem EA2.06 - Ability to determine and/or interpret the following as they apply to 295028 High Drywell Temperature HIGH DRYWELL TEMPERATURE: 3.4 51 I5 Torus/suppression chamber air space temperature: Plant-S ecific EA2.03 - Ability to determine and/or 295038 High Off-site Release Rate interpret the following as they apply to 3.5 52 19 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 3.5 53 of AC I 6 PARTIAL OR COMPLETE LOSS OF A.C. POWER : S stem lineu s 2.4.8 - Emergency Procedures I Plan:

295018 Partial or Total Loss of Knowledge of how abnormal operating 3.8 54 CCW/8 procedures are used in conjunction with EOP's.

2.1.27 - Conduct of Operations:

700000 Generator Voltage and Knowledge of system purpose and I or 3.9 55 Electric Grid Disturbances function.

2.1.19 - Conduct of Operations: Ability 295021 Loss of Shutdown Cooling 14 to use plant computers to evaluate 3.9 56 s stem or com anent status.

EA2.04 - Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to Water Level I 5 LOW SUPPRESSION POOL WATER 3.5 57 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 Present and Reactor Power Above x PRESENT AND REACTOR POWER 4.2 58 APRM Downscale or Unknown I 1 ABOVE APRM DOWNSCALE OR UNKNOWN: Boron effects on reactor power (SBLC)

K/A Category Totals: 4 3 3 3 Group Point Total: 2017

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#

1\1\2.05 - ,\hilitv {() d.:krminc* andn

~'l.'017 I ligh Ufl~,ili.: R.:k:t Rak intcrprd the following. as the\ appl' to

()

j 8 8.l Hllill OFF-SIT!*. RIU1\Sl' R1\ IF Tvkkurnlogin1! data 2.1 J2 - Cnnduct of ( )p~ratio11'; ,\bility to 2'l'll I~ lnwmpkk SCRA!'v1 1 c'<plain and applv all s)slcm limits and 4.0 84 precaution,;.

\;\2.(14 - Ability [(I ,k;tcrminc andior 295()08 l !igh Rcachir Water I eve] inkrpn
t the f(1llowing a;, they apply lo

~~ .3 8:'i 2 ll!Cil! RI 1\CIOI\ \.\Al LR I.I \'I.I I !catup rate: Plant-Spccilic EK! .01 - Knowledge of the operational implications of the following concepts as 500000 High CTMT Hydrogen 3.

Conc. / 5 x they apply to HIGH CONTAINMENT 3

59 HYDROGEN CONCENTRATIONS:

Containment inte ri AK2.04 - Knowledge of the interrelations between HIGH DRYWELL PRESSURE 2.6 2950 I 0 High Drywell Pressure I 5 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 AAl.02 - Ability to operate and/or monitor 4.

295015 Incomplete SCRAM/ l 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.

AK3.0I - Knowledge of the reasons for the 295012 High Drywell following responses as they apply to HIGH 3.

Temperature I 5 x DRYWELL TEMPERATURE: Increased 5 65 drywell cooling K/A Category Totals: 2 Group Point Total: m

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 1\2 03 - 1\billl\ hi la) predict the impacts of the fdh111i111C on the LNIN I LRRl'PI Alil L POW! R

\UPPLY (;\ C!U C I. and (b) 26200.? l I'\ 11\CllC) b:t>cd on tlH"C prcdi<:tiuns. u'c' 2 () S<>

prnccdurcs to C(lrrccL cimtrnL nr mnigatc the consequence:, oflhchc abnormal conditicms or operations:

l n:qu.:nc,* change> in the stem

\2 07 - Ability hi 1a) predict the irnp
Kb uf the foll Cl\\ ing Ufl the 1.:V11R(il NCY GIN Ht:\ IORS tDIF\l'L!JFTJ. and (b 1 basctl on those predictmns. use proccdtircs tn 2ii.:Jil(ll) L[)(1S ' 7

.i.1 k7 wrrccL contrnL or mitigate tlw COnSCcJUC!lCes o!' tlhbC abthlrlllai cunditiom. or operations: l .oss or clff-'>ih: pPm:r during full-load 2.4.49 - f*mcrgcnl Pniccdurcs

!'Ian: 1\hility to perform 11ithoul 2ii31l00 ])l lkctncal reference to procedures those i.c1 88 I )istributi<lll a(tions that require imn1cdiak PperatiPll of SjSlCl11 Ccl111p011l'llh and controls.

2.2.22 - Equipment Control 212001) !\I'S [(11\>wlcdgc of limiting condition> 4.7 8'1 for operations and sa!Ct\ limih.

24.2 - Frncrgcncv Procedures Plan: K1H>1dcdge elf svskm set 2151lln IRi\1 pllints. intcrlocb and automatic .:j 6 ')()

action, associated ith I:cw c11tr1 conditions Kl.OJ - Knowledge of the physical connections and/or cause- effect 262001 AC Electrical relationships between A.C Distribution x ELECTRICAL DISTRIBUTION 3.8 and the following: Emergency enerators (diesel/jet)

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

ower: BWR-2,3,4 K2.01 - Knowledge of electrical 218000 ADS x power supplies to the following: 3.1 3 ADS lo ic K2.01 - Knowledge of electrical 205000 Shutdown Cooling x power supplies to the following: 3. l 4 Pum motors K3.06 - Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION 212000 RPS x SYSTEM will have on following:

4.0 5 Scram air header solenoid operated valves

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 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:

3.3 6 Systems having pneumatic valves and controls K4.07 - Knowledge of EMERGENCY GENERATORS (DIESEUJET) 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 K5.02 - Knowledge of the operational implications of the following concepts as they apply 211000 SLC x to STANDBY LIQUID 2.8 9 CONTROL SYSTEM : Chugging as it ertains to boron mixin )

K5.05 - Knowledge of the operational implications of the following concepts as they apply 239002 SRVs x to RELIEF/SAFETY VALVES:

2.6 10 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 A 1.04 - Ability to predict and/or monitor changes in parameters associated with operating the 215004 Source Range Monitor x 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

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 A2.08 - Ability to (a} predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM 223002 PCIS/Nuclear Steam SUPPLY SHUT-OFF; and (b) 2.7 15 Supply Shutoff based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Surveillance testin A2.01 - Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) ; and (b) 262002 UPS (AC/DC) based on those predictions, use 2.6 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Under volta e A3.01 - Ability to monitor automatic operations of the 215003 !RM 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 speed 2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system operation I 400000 Component Cooling status that must be reported to 2.7 21 Water internal organizations or external agencies, such as the state, the NRC, or the transmission s stem o erator.

2.2.22 - Equipment Control:

206000 HPCl Knowledge of limiting conditions 4.0 22 for o erations and safet limits.

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

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 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 I Plan: Knowledge of operational 211000 SLC 3.8 26 implications of EOP warnings, cautions, and notes.

KIA Category Totals: 2 2 2 3 2 3 2 Group Point Total: 2615

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 #

i\2.04 - Ability to (al predict the impacts or th.: folhl\\ ing 011 the CONTROL ROOfvl I IVi\C : and (b) based <'11 thusc pr.:dictirms. use 29000.l Control Ror,rn I fVAC procedures to correct cC>ntroL or .U l)j mitigate th.: ..:onscqucnccs or those abnormal conditions or 1ipcratii'n'>

Initiation/failure or fire prnlcctiPll system 2.4.46 - LrncrgcncY Procedures

-~*hiJl\(J \fom I urbinc ( icn Plan: Ability hl 1cn1\ that the i '.' 92

.\us alarms arc consistent 11 i1J1 the plant wnditirlJls.

i\2.ll2 Ability to (a) predict the irnpacts or the following on the ROD l3LOCK vlUNITOR SYS l"H\1; and tbi base..! on thr"c pn:dictio1b. use procedures In 2J 'i002 Rll\1 com~ct. rnntrol. or mitigate the u lll conscqucnc..:s oftl11isc abnormal conditions or opcra!ions: I ,,,, n rcducti(ln in recirculation systrn1 llnw (flow comparator): llWR-3,4.5 KI.OJ - Knowledge of the physical connections and/or cause- effect relationships between 290001 Secondary CTMT x SECONDARY CONTAINMENT 3.3 27 and the following: Reactor building ventilation: Plant-S ecific K2.02 - Knowledge of electrical 226001 RHR/LPCI: CTMT Spray Mode x power supplies to the following: 2.9 28 Pum s 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 20 I 00 I CRD Hydraulic x feature(s) and/or interlocks 3.8 30 which provide for the following:

Control rod SCRAM K5.06 - Knowledge of the operational implications of the 271000 Off-gas x following concepts as they apply 2.7 31 to OFFGAS SYSTEM : Catalytic recombination K6.01 - Knowledge of the effect that a loss or malfunction of the 290003 Control Room HV AC x following will have on the 2.7 32 CONTROL ROOM HVAC:

Electrical ower

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 #

A 1.04 - Ability to predict and/or monitor changes in parameters associated with operating the 216000 Nuclear Boiler Inst. x NUCLEAR BOILER 2.6 33 INSTRUMENTATION controls includin : S stem ventin 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 stop/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-l&ll(Not-BWR 1) 2.2.36 - Equipment Control:

Ability to analyze the effect of maintenance activities, such as 25900 I Reactor Feedwater 3.1 37 degraded power sources, on the status of limiting conditions for operations.

K5.07 - 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 (abnormal) heat 102d K/A Category Totals: 2 Group Point Total: 12/i

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Hope C.reek 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 Ability to manage the control room crew 2.1.6 4.8 100 durinQ plant transients.

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 primary and secondary plant 2.1.34 2.7 67 chemistry limits.

Knowledge of system purpose and I or

2. 1.27 3.9 75 function.

Subtotal 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 effect plant and system conditions.

&~::~* 3

- 4.4 2

95 Ability to apply technical specifications for a 2.2.40 4.7 98 system 2.

Equipment Control Knowledge of less than one hour technical 2.2.39 3.9 68 specification action statements for systems.

2.2.14 3.9 69 Subtotal 2 [.~~?!~t~I 2 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3. 15 3. 1 96 portable survey instruments, personnel monitoring equipment etc.

3.

Radiation Ability to use radiation monitoring systems, Control such as fixed radiation monitors and alarms, 2.3.5 2.9 70 portable survey instruments, personell monitoring equipment, etc.

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

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 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 hi h radiation areas, ali nin filters, etc.

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.

4.

Emergency Procedures I 2.4.6 Knowledge of EOP mitigation strategies. 3.7 72 Plan Knowledge of procedures relating to a 2.4.28 3.2 73 securit event.

Subtotal 2 Tier 3 Point Total 7

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

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

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

  1. 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).

2/2 K2.02 Randomly selected A3.05

  1. 31: Cannot write an operationally valid question. Randomly 2/2 K5.06 selected A 1.08
  1. 33: Cannot write an operationally valid question. Randomly 2/2 A1.04 selected A 1.01
  1. 37: Cannot write an operationally valid question. Randomly 2/2 2.2.36 selected 2.2.44
  1. 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 'r#-70: KIA is oversampled. Randomly selected 2.4.49
  1. 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

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

  1. 83: Cannot write an operationally valid question. Randomly 1/2 295017 selected 500000
  1. 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 #91: JPM already tests this subject (oversample). Randomly 212 A2.04 selected 290001 A2.02
  1. 92: Cannot write an operationally valid question. Randomly 2/2 2.4.46 selected 2.4.45
  1. 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: 8/2016 Examination Level: RO~ 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 Complete A Sunday Shift Routine Log 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(::; 3 for ROs;::; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (::; 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: 8/2016 Examination Level: ROD SRO [8J Operating Test Number: 1 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(:::; 3 for ROs;:::; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (.:::: 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: 8/2016 Exam Level: RO IZI SRO-ID SRO-U D Operating Test No: 1 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. PB001ShiftA4160 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 TACS 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 1
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 / SRO-U

{A)lternate path 4-6 I 4-6 I 2-3

{C)ontrol room (D)irect from bank :5. 9 I :5_8 I ::=_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 I ::=_3 I :5. 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: 8/2016 Exam Level: ROD SRO-I [2J SRO-U D Operating Test No: 1 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 1
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 I :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) ~21 ~2 I ~1 (P)revious 2 exams :5. 3 I :5_3 I :5. 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: 8/2016 Exam Level: ROD SRO-ID SRO-U ~ Operating Test No: 1 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.

j. BF002 Shift In-Service CRD Stabilizing Valves D,R 1
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 S9/ S8 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 S3I 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.: 2016 HC Examiners: Operators:

Initial Conditions: The scenario begins with the plant at approximately 88% power, with power ascension in progress following maintenance on Rf PT AP101. Additionally, emergency diesel generator AG400 surveillance testing is in progress.

Turnover: The crew will remove EOG AG400 from service IAW Ste12s 5.4.13d.-19 of HG.OP-ST.KJ-0001, and commence power ascension to 100% power in accordance with REMA.

Event Malf. No. Event Event No. Type* Description 1 N/A N (BOP) Remove EOG from serVice (TS) 2 N/A R (ATC) Raise reactor power usinq control rods 3 CD033039 C (ALL) Stuck control rod 30-39 (TS) 4 PC07A C (ALL) Seismic event (> QBE) causes EHC filter clogging TC16 5 AD02DO C (ALL) Safety Relief Valve F013D stuck open (TS) 6 RP06 M (ALL) Yz core ATWS 7 SL04A C (ATC) 'A' SLC pump fails to auto start SL01B Trip of 'B' SLC pump 8 CU11A C (ATC) RWCU fails to automatically isolate CU11B 9 TC07A C (ALL} Total loss of EHC, loss of bypass valves TC07B 10 0020 C (BOP) 'A' RHR AP202 pump trip (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: .f. Op-Test No.: 2016 HC Examiners: Operators:

Initial Conditions: Reactor start up is in progress following a forced outage.

Turnover: The crew will place remaining circulating water pumps in service IAW HG.OP-SO. DA-0001 step 5.1.28 through 5.2.10, and continue with reactor startup.

Event Malf. No. Event Event No. Type* Description 1 N/A N (BOP) Place remaining circulating water pump in service 2 N/A R (ATC) Raise power with control rods 3 NM12D I (ALL) Recirculation system flow summer K607D failure (TS) 4 ED09B1 C (ALL) Loss of 80481 120 VAC 1E inverter (TS) 5 MS04B C (ALL) Steam leak in steam tunnel - scram 6 MS19B C (ATC) MSIV F022B isolation failure 7 RH07D M (ALL) LOCA - RHR leak via pump suction, Loop D HP08 HPCI failure 8 PC06 C (ALL) Suppression pool leak (N)ormal, (R)eactivity, ( l)nstrument, (C)omponent, (M)aior

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.:~ Op-Test No.: 2016 HC Examiners: Operators:

Initial Conditions: 95% power Turnover: Ascend to 100% power IAW HC.OP-IO.ZZ-0006 Event Malf. No. Event Event No. Type* Description 1 N/A R (ATC) Raise power with recirculation pumps 2 N/A C (ALL) 'A' Recirculation pump runaway (TS) 3 IA03 C (BOP) Primary containment instrument gas leak 4 ED03 C (ALL) Loss of 10A110 (TS) 5 0002, 0003, M (ALL) Loss of feedwater with automatic scram failure FW04B, FW04C onlevel3 6 HP03 C (BOP) HPCI pump trip 7 RR31A2 M (ALL) LOCA 8 R20E I (BOP) Failure of A channel of Core Spray and RHR loqic (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)aior

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