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
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ML15308A608 List:
References
TAC U01925
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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-Only Point~

Tier Group K

K K

G Total l

2 3

A2 G*

Total

l.

4 3

3 3

20 3

4 7

Emergency 2

2 7

2 1

Plant Tier Evolutions Totals 5

4 5

4 27 5

5 I 0 2

2 2

3 2

3 2

2 3

2 3

26 2

3

2.

Plant 2

2 12 0

2 Systems Tier Totals 3

3 3

4 4

4 3

3 4

3 4

38 4

4 8

2 3

4 2

4

3. Generic Knowledge & Abilities 10 Categories I

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, I Rs. 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 2951! I() l. "ntn>I RP<irn

,\\handonrncnt

.2'15026 Suppression i'nPl lligh Wat,*r rc*mp. 5 2950011 SCF,,\\\\1 I 2'!5W~ 1 ligh Ot1~s1tc RcJcc1,c Rah:

')

A2 G

KIA Topic(s) 1./\\2.02 - \\hility to (ktcnninc and\\i1 interpret the* following as the' apply to Jll(ill DRYWEl L PRESSl!RL Dr;11cll tcm icraturc

!\\i\\2.0:' - Ability to determine a11dior interpret the following w, the' appl; to CONTROL ROOM AllANDON\\1! NT Drvw<:ll r.:,surc L!\\2.02 - ;\\bilit> to dctcrlllinc amJior int.'rprct the l(>llo\\\\ing > ion pool kl cl 2.2.3'! - Equipmcnt Control Kmn1kdgc c>f kss than one huur technical -;pccirication action swtcmcnts li>r system,.

2.4.41 - I :mcrgenc; Prnccdurcs Plan:

Knowlcdgc nfthc rncrgrncY actio11 lc1cl threshold<> and cla<>>illcation' 2.4.21 - L1rn:rgcric1 J'[()ccdurcs ! !'Ian:

hnn11 lcdgc of th<.' parameters and logic usd 1<1 a" the status <lf<<;alcty fund ions. such Imp.

4 ()

.ll/

4.5 4.(1 2'i'l1() I l'a11ial or CPlllplctc I.1is' of l orn:d Cure l hJ\\\\ ( 'irculatiPn I &

4 as rcacmit1* control, wrc cooling and hc'at

,I_()

2()~1104 l'm1ial or rotal l.n,s of DC P11r

(,

295006 SCRAM I 1 295031 Reactor Low Water Level

/2 600000 Plant Fire On-site I 8 295005 Main Turbine Generator Trip I 3 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1

&4 295019 Partial or Total Loss of Inst. Air I 8 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. I 5 x

x x

x x

x x

x runoval. reactor coolant,ystcm intcgrit1-,

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

2.2.40 - F4uipmcnt ( "tmli<li. r\\bilitv tn apply technical spccificat1<Jns for a s1-<tcm AKl.02 - Knowledge of the operational implications of the following concepts as the a I to SCRAM : Shutdown mar in EKI.03 - Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL : Water level effects on reactor power AKl.02 - Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Fightin AK2.03 - Knowledge of the interrelations between MAIN TURBINE GENERA TOR TRIP and the following: Recirculation system AK2.06 - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the following:

Reactor ower 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 pum trip: Plant-Specific EK3.02 - Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression pool 3.4 3.7 2.9 3.2 3.8 3.2 3.9 3.9 Q#

77 79 80 81 39 40 41 42 43 44 45 46

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)

AK3.01 - Knowledge of the reasons for 295016 Control Room x

the following responses as they apply to Abandonment I 7 CONTROL ROOM ABANDONMENT :

Reactor SCRAM AA 1.01 - Ability to operate and/or 295004 Partial or Total Loss of monitor the following as they apply to x

PARTIAL OR COMPLETE LOSS OF DC Pwr/6 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 HIGH DRYWELL PRESSURE:

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

monitor the following as they apply to Mode I 8 REFUELING ACCIDENTS : Fuel pool COOiin and cleanup s stem EA2.06 - Ability to determine and/or 295028 High Drywell Temperature interpret the following as they apply to HIGH DRYWELL TEMPERATURE:

I 5 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 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 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 CCW/8 procedures are used in conjunction with EOP's.

700000 Generator Voltage and 2.1.27 - Conduct of Operations:

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

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

EA2.04 - Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to LOW SUPPRESSION POOL WATER Water Level I 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 Present and Reactor Power Above x

PRESENT AND REACTOR POWER 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:

Imp.

Q#

4.1 47 3.3 48 3.9 49 2.9 50 3.4 51 3.5 52 3.5 53 3.8 54 3.9 55 3.9 56 3.5 57 4.2 58 2017

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#

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 500000 High CTMT Hydrogen implications of the following concepts as

3.

x they apply to HIGH CONTAINMENT 59 Conc. / 5 HYDROGEN CONCENTRATIONS:

3 Containment inte ri AK2.04 - Knowledge of the interrelations 2950 I 0 High Drywell Pressure I 5 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 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:

295008 High Reactor Water Level Ability to perform without reference to

4.

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

and controls.

AK3.0I - Knowledge of the reasons for the 295012 High Drywell x

following responses as they apply to HIGH

3.

65 Temperature I 5 DRYWELL TEMPERATURE: Increased 5

drywell cooling K/A Category Totals:

2 Group Point Total:

m

ES-401 System #I Name K

K K

1 2

3 26200.? l I'\\ 11\\CllC) 2ii.:Jil(ll) L[)(1S 2ii31l00 ])l lkctncal I )istributi<lll 212001) !\\I'S 2151lln IRi\\1 262001 AC Electrical x

Distribution 206000 HPCI x

218000 ADS x

205000 Shutdown Cooling x

212000 RPS 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

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) b:t>cd on tlH"C prcdi<:tiuns. u'c' 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 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 reference to procedures those a(tions that require imn1cdiak PperatiPll of SjSlCl11 Ccl111p011l'llh and controls.

2.2.22 - Equipment Control

[(11\\>wlcdgc of limiting condition>

for operations and sa!Ct\\ limih.

24.2 - Frncrgcncv Procedures Plan: K1H>1dcdge elf svskm set pllints. intcrlocb and automatic action, associated ith I :cw c11tr1 conditions Kl.OJ - Knowledge of the physical connections and/or cause-effect relationships between A.C ELECTRICAL DISTRIBUTION and the following: Emergency enerators (diesel/jet)

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

ower: 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 Imp Q#

2 ()

S<>

' 7

.i.1 k7 i.c1 88 4.7 8'1

.:j 6

')()

3.8 3.0 2

3.1 3

3. l 4

4.0 5

ES-401 System # I Name K

K K

1 2

3 300000 Instrument Air x

264000 EDGs 261000 SGTS 211000 SLC 239002 SRVs 209001 LPCS 203000 RHR/LPCI: Injection Mode 215004 Source Range Monitor 263000 DC Electrical Distribution 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

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 K4.07 - Knowledge of EMERGENCY GENERATORS x

(DIESEUJET) 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 K5.02 - Knowledge of the operational implications of the x

following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM : Chugging as it ertains to boron mixin )

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 A 1.04 - Ability to predict and/or monitor changes in parameters associated with operating the x

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 Imp Q#

3.3 6

3.3 7

3.7 8

2.8 9

2.6 10 2.9 II 2.7 12 3.5 13 2.5 14

ES-401 System # I Name K

K K

1 2

3 223002 PCIS/Nuclear Steam Supply Shutoff 262002 UPS (AC/DC) 215003 !RM 215005 APRM I LPRM 259002 Reactor Water Level Control 217000 RCIC 400000 Component Cooling Water 206000 HPCl 300000 Instrument Air 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

A2.08 - 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 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) based on those predictions, use 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 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 speed 2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system operation I status that must be reported to internal organizations or external agencies, such as the state, the NRC, or the transmission s stem o erator.

2.2.22 - Equipment Control:

Knowledge of limiting conditions for o erations and safet limits.

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 Imp Q#

2.7 15 2.6 16 3.3 17 3.7 18 3.7 19 3.7 20 2.7 21 4.0 22 3.0 23

ES-401 System # I Name K

K K

1 2

3 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

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#

3.0 24 3.4 25 3.8 26 2615

ES-401 K

K K

System #I Name 1

2 3

29000.l Control Ror,rn I fVAC

-~*hiJl\\(J \\fom I urbinc ( icn

.\\us 2J 'i002 Rll\\1 290001 Secondary CTMT x

226001 RHR/LPCI: CTMT x

Spray Mode 22300 I Primary CTMT and x

Aux.

20 I 00 I CRD Hydraulic 271000 Off-gas 290003 Control Room HV AC 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

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 procedures to correct cC>ntroL or mitigate th.:..:onscqucnccs or those abnormal conditions or 1ipcratii'n'>

Initiation/failure or fire prnlcctiPll system 2.4.46 - LrncrgcncY Procedures Plan: Ability hl 1cn1\\ that the 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 com~ct. rnntrol. or mitigate the 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 SECONDARY CONTAINMENT and the following: Reactor building ventilation: Plant-S ecific K2.02 - Knowledge of electrical power supplies to the following:

Pum s 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 K5.06 - Knowledge of the operational implications of the x

following concepts as they apply to OFFGAS SYSTEM : Catalytic recombination K6.01 - Knowledge of the effect that a loss or malfunction of the x

following will have on the CONTROL ROOM HVAC:

Electrical ower Imp.

Q

.U l)j i '.'

92 u

lll 3.3 27 2.9 28 2.7 29 3.8 30 2.7 31 2.7 32

ES-401 System # I Name K

K K

1 2

3 216000 Nuclear Boiler Inst.

272000 Radiation Monitoring 241000 Reactor/Turbine Pressure Regulator 215001 Traversing In-core Probe 25900 I 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

A 1.04 - Ability to predict and/or monitor changes in parameters x

associated with operating the NUCLEAR BOILER 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 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 stop/throttle valve o eration A4.03 - Ability to manually operate and/or monitor in the 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 degraded power sources, on the status of limiting conditions for operations.

K5.07 - Knowledge of the operational implications of the x

following concepts as they apply to FUEL POOL COOLING AND CLEAN-UP : Maximum (abnormal) heat 102d 2

Group Point Total:

Imp.

Q 2.6 33 2.7 34 3.3 35 3.0 36 3.1 37 2.5 38 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 2.1.6 Ability to manage the control room crew 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.

2.1.34 Knowledge of primary and secondary plant 2.7 67 chemistry limits.

2. 1.27 Knowledge of system purpose and I or 3.9 75 function.

Subtotal

&~::~* 3 -

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.

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

3.9 68 2.2.14 3.9 69 Subtotal 2

[.~~?!~t~I 2

Knowledge of radiation monitoring systems, 2.3. 15 such as fixed radiation monitors and alarms,

3. 1 96 portable survey instruments, personnel monitoring equipment etc.
3.

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

Knowledge of radiation monitoring systems, 2.3.15 such as fixed radiation monitors and alarms, 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 2.3.13 duties, such as response to radiation monitor 3.4 74 alarms, containment entry requirements, fuel handling responsibilities, access to locked hi h radiation areas, ali nin filters, etc.

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.

Emergency Procedures I 2.4.6 Knowledge of EOP mitigation strategies.

3.7 72 Plan Knowledge of procedures relating to a 2.4.28 securit event.

3.2 73 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 Kl A 2/1 K5.02

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

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

  1. 22: Cannot write an RO level of knowledge question on this KIA. Randomly selected 2.2.39 2/2 K2.02
  1. 28: KIA subject is oversampled (same as question #4).

Randomly selected A3.05 2/2 K5.06

  1. 31: Cannot write an operationally valid question. Randomly selected A 1.08 2/2 A1.04
  1. 33: Cannot write an operationally valid question. Randomly selected A 1.01 2/2 2.2.36
  1. 37: Cannot write an operationally valid question. Randomly selected 2.2.44 2/2 K5.07
  1. 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

'r#-70: KIA is oversampled. Randomly selected 2.4.49

3 2.1.27

  1. 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

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

  1. 83: Cannot write an operationally valid question. Randomly selected 500000 2/1 2.4.49
  1. 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
  1. 91: JPM already tests this subject (oversample). Randomly A2.04 selected 290001 A2.02 2/2 2.4.46
  1. 92: Cannot write an operationally valid question. Randomly selected 2.4.45 212 A2.02
  1. 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:

8/2016 Examination Level:

RO~

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 Complete A Sunday Shift Routine Log 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(::; 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 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(:::; 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

~ 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 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

~ 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)

~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 S 3 I 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 TC16 clogging 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 1 E 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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