ML12111A190

Draft - Outlines (Folder 2)

ML12111A190
Person / Time
Site:	Hope Creek
Issue date:	01/23/2012
From:	Todd Fish Operations Branch I
To:	Public Service Enterprise Group
Jackson D
Shared Package
ML113070699	List: IR 05000354/2012301 ML12061A285 ML12083A212 ML12083A223 ML12083A235 ML12083A242 ML12111A179 ML12111A188 ML12111A190 ML12111A200 ML12111A202 ML12172A046
References
TAC U01845
Download: ML12111A190 (24)

Text

ES-401 Written Examination Outline Form ES-401-1 II Facility: Hope Creek Station Date of Exam: 03/05/2012

~j SRO-Only Points Tier Group K K K A2 G* Total 1 2 3

~=:::==*==~

1. 1 3 3 4 3 4 3 20 4 3 7 Emergency & 1-------1-+--+---1 Abnormal 2 1 2 N/A 1 1 N/A 1 7 2 3 Plant Evolutions Tier Totals 4 4 6 4 5 4 27 5 5 10

-+_~~:_~_~~-:~~~-~~~~-~~-~:~~O~I~1~--:---+----:--~

2.

Plant

~

Systems r-___  : __

Tier Totals 3 2 3 4 3 4 4 4 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 7

Categories 2 2 3 3 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA 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 KlAs having an importance rating (IR) 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 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs in Tiers 1 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.1.b of ES-401 for the applicable KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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 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 KlAs that are linked to 10 CFR 55.43.

ES-401 1 Form ES-401-1 Hope Creek Station Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function KJA Topic(s)

AA2.07 - Ability to determine and/or 295005 Main Turbine Generator interpret the tollowing as they apply to X 3.6 76 Trip / 3 MAIN TURBINE GENERATOR TRIP:

Reactor water level EA2.01 - Ability to determine and/or 295030 Low Suppression Pool interpret the tollowing as they apply to X 4.2 77 Water Level / 5 LOW SUPPRESSION POOL WATER LEVEL: Suppression pool level AA2.02 - Ability to detemline and/or 295006 SCRAM / 1 X interpret the following as they apply to 4.4 78 SCRAM: Control rod position 2.4.34 - Emergency Procedures / Plan:

295021 Loss of Shutdown Knowledge ofRO tasks performed outside X 4.1 79 Cooling /4 the main control room during an emergency and the resultant operational effects.

2.1.23 - Ability to pertorm specific system 295004 Partial or Total Loss of DC Pwr / 6 X and integrated plant procedures during all 4.4 80 modes of plant operation.

2.4.41 - Emergency Procedures i Plan:

295024 High Drywell Pressure /

X Knowledge of the emergency action level 4.6 81 5

thresholds and classifications.

EA2.04 - Ability to determine and/or 295031 Reactor Low Water interpret the tollowing as they apply to X 4.8 82 Level / 2 REACTOR LOW WATER LEVEL:

Adequate core cooling AKI.O I - Knowledge of the operation applications of the following concepts as 600000 Plant Fire On-site / 8 X 2.5 39 they apply to Plant Fire On Site: Fire Classifications by type AKI.02 - Knowledge ofthe operational 295006 SCRAM / 1 X implications of the following concepts as 3.4 40 they apply to SCRAM: Shutdown margin AKl.03 - Knowledge of the operational 295023 Refueling Acc Cooling implications of the following concepts as X 3.7 41 Mode / 8 they apply to REFUELING ACCIDENTS:

Inadvertent criticality AK2.14 - Knowledge of the interrelations 295019 Partial or Total Loss of between PARTIAL OR COMPLETE LOSS X 3.2 42 Inst. Air /8 OF INSTRUMENT AIR and the following:

Plant air systems AK2.02 - Knowledge of the interrelations 295004 Partial or Total Loss of between PARTIAL OR COMPLETE LOSS X 3.0 43 DC Pwr /6 OF D.C. POWER and the following:

Batteries EK2.14 - Knowledge of the interrelations 295031 Reactor Low Water between REACTOR LOW WATER X 3.9 44 Level /2 LEVEL and the following: Emergency generators AK3.01 - Knowledge of the reasons for the 295003 Partial or Complete following responses as they apply to X 3.3 45 Loss of AC / 6 PARTIAL OR COMPLETE LOSS OF A.C.

POWER: Manual and auto bus transfer EK3.05 - Knowledge of the reasons for the 295026 Suppression Pool High following responses as they apply to X 3.9 46 Water Temp. / 5 SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor SCRAM EK3.03 - Knowledge of the reasons for the 295037 SCRAM Conditions following responses as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND X 4.1 47 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown /1 DOWNSCALE OR UNKNOWN :

- Lowering reactor water level

ES-401 2 Form ES-401-1 Hope Creek Station Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function KIA Topic(s) Q# I AA 1.04 - Ability to operate and/or monitor 295021 Loss of Shutdown the following as they apply to LOSS OF X SHUTDOWN COOLING: Alternate heat 3.7 48 Cooling / 4 removal methods AAl.07 - Ability to operate and/or monitor 295001 Partial or Complete the following as they apply to PARTIAL Loss of Forced Core Flow X OR COMPLETE LOSS OF FORCED 3.1 49 Circulation / 1 & 4 CORE FLOW CIRCULATION: Nuclear boiler instrumentation system AAI.02 - Ability to operate and/or monitor 295016 Control Room the following as they apply to CONTROL X ROOM ABANDONMENT:

2.9 50 Abandonment / 7 Reactor/turbine pressure regulating system EA2.0 I - Ability to determine and/or 295024 High Drywell Pressure / interpret the following as they apply to X HIGH DRYWELL PRESSURE: Drywell 4.2 51 5

pressure EA2.04 - Ability to determine and/or 295038 High Off-site Release interpret the following as they apply to X HIGH OFF-SITE RELEASE RATE:

4.1 52 Rate / 9 Source of off-site release AA2.02 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and GENERATOR VOLTAGE AND Electric Grid Disturbances X ELECTRIC GRID DISTURBANCES:

3.5 53 Voltage outside the generator capability curve.

2.1.31 - Ability to locate control room 295005 Main Turbine switches, controls, and indications, and to X determine that they correctly reflect the 4.6 54 Generator Trip / 3 desired plant lineup.

295030 Low Suppression Pool 2.2.12 - Equipment Control: Knowledge of X 3.7 55 Water Level / 5 surveillance procedures.

2.2.42 - Equipment Control: Ability to 295028 High Drywell recognize system parameters that are entry-Temperature / 5 X level conditions for Technical 3.9 56 Specifications.

AA2.03 - Ability to determine and/or interpret the following as they apply to 295018 Partial or Total Loss of X PARTIAL OR COMPLETE LOSS OF 3.2 57 CCW/8 COMPONENT COOLING WATER:

Cause for partial or complete loss EK3.02 - Knowledge of the reasons for the 295025 High Reactor Pressure following responses as they apply to HIGH X 3.9 58

/3 REACTOR PRESSURE: Recirculation pump trip: Plant-Specific KIA Category Totals: 3 3 4 3 4/4 3/3 Group Point Total: 20/7 I

ES-401 3 Form ES-401-1 Hope Creek Station Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # I Name Safety Function KIA Topic(s)

AA2.01 High Suppression Pool Tempemture, Ability to detelmine and/or 295013 High Suppression Pool interpret the following as they apply to X 4.0 83 Temperature I 5 HIGH SUPPRESSION POOL TEMPERATURE: Suppression Pool Temperature 295032 High Secondary 2.1.20 - Conduct of Operations: Ability to Containment Area Temperature X intclJlret and execute procedure steps. 4.6 84 15 2.4.30 - Emergency Procedures / Plan; Knowledge of events related to system 295017 High Off-site Release operation,' status that must be reported to X 4.1 85 Rate 19 internal organizations or external agencies, such as the state, the NRC, or the tmnsmission system opemtor.

AK1.03 - Knowledge of the opemtional 295010 High Drywell Pressure implications of the following concepts as X 3.2 59 15 they apply to HIGH DRYWELL PRESSURE: Temperature increases AK2.02 - Knowledge of the interrelations 295009 Low Reactor Water between LOW REACTOR WATER LEVEL 3.9 X 60 Level 12 and the following: Reactor water level control EK3.03 - Knowledge ofthe reasons for the 295034 Secondary following responses as they apply to Containment Ventilation High X SECONDARY CONTAINMENT 4.0 61 Radiation I 9 VENTILATION HIGH RADIATION:

Personnel evacuation EAI.02 - Ability to operate and/or monitor 295035 Secondary the following as they apply to Containment High Differential X SECONDARY CONTAINMENT HIGH 3.8 62 Pressure 15 DIFFERENTIAL PRESSURE:

SBGT/FRVS EA2.02 - Ability to determine and/or 295036 Secondary intelJlret the following as they apply to Containment High SumplArea X SECONDARY CONTAINMENT HIGH 3.1 63 Water Levell 5 SUMP/AREA WATER LEVEL: Water level in the affected area 295008 High Reactor Water 2.1.27 - Conduct of Opemtions: Knowledge X 3.9 64 Level 12 of system pUlJlose and / or function.

AK3.06 - Knowledge of the reasons for the following responses as they apply to 295020 Inadvertent Cont.

X INADVERTENT CONT AINMENT 3.3 65 Isolation I 5 & 7 ISOLATION: Suppression pool water level response KIA Category Totals: 1 1 2 1 111 1/2 Group Point Total: 7/3 I

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

1 2 3 4 5 6 1 3 4 A2.04 - Ability to (a) predict the impacts of the tollowing on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and l b) 206000 HPCI X based on those predictions, use 3.0 86 procedures to COITcct, control, or mitigate thc consequences of those abnonnal conditions or operations:

A.c. failures: BWR-2,3,4 A2.04 - Ability to (a) predict the impacts of the tollowing on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to 262001 AC X 4.2 87 cOlTect, control, or mitigate the consequences of those abnonnal conditions or operations: Types of loads that, if de-energized, would hinder plant operdtion.

2.2.44 - Equipment Control: Ability to interpret control room indications to verify the status and operation of 261000 SGTS X a system, and understand how 4.4 88 operator actions and directives dIeet plant and system conditions.

2.2.38 Knowledge of conditions and 215004 SRM X limitations in the t~lcility license 4.5 89 A2.09 - Ability to (a) predict the impacts of the tollowing on the PRIMARY CONTAINMENT ISOLA TION SYSTEM;NUCLEAR 223002 PelS/Nuclear Steam STEAM SUPPLY SHUT-OFF; Supply Shutoff X and (b) based on those predictions, 3.7 90 use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System initiation Kl.05 - Knowledge of the physical connectiollS ancllor cause- effect relationships between 264000 EDGs X EMERGENCY GENERATORS 3.2 1 (DIESEUJET) and the following:

Emergency generator fuel oil supply system Kl.Ol - Knowledge of the physical connectiollS ancllor cause- effect relationships between STANDBY 211000 SLC X 3.0 2 LIQUID CONTROL SYSTEM and the following: Core spray line break detection: Plant-Specific K2.01 - Knowledge of electrical 239002 SRVs X power supplies to the following: 2.8 3 SRV solenoids K3.02 - Knowledge ofthe effect that a loss or malfunction of the AUTOMATIC 218000 ADS X 4.5 4 DEPRESSURIZATION SYSTEM will have on the following: Ability to rapidly depressurize the reactor

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

A2.

561 K3.01 - Knowledge of the effect 262001 AC Electrical X

Ii: that a loss or malfunction of the AC. ELECTRICAL 3.5 5 Distribution DISTRIBUTION will have on following; Major System Loads K3.01 Knowledge of the effect that a loss or malfunction of the HIGH PRESSURE COOLANT 206000 HPCI X 4.0 6 INJECTION SYSTEM will have on I';i!!",!'!ii":' following; Reactor water level control: BWR-2,3,4 K4.03 Knowledge of SHUTDOWN COOLl:-lG SYSTEM (RHR SHUTOOWN 205000 Shutdown Cooling X COOLING MODE) design 3.8 7 feature(s} andior interlocks which provide for the following: Low

.... reactor water level: ific K4.01 Knowledge of U:-IINTERRUPTABLE POWER SUPPLY (AC.lD.C.) design 262002 UPS (AC/DC) X feature(s) andior interlocks which 3.1 8 Il provide for the following: Transfer from preferred power to alternate power supplies t* KS.Ol Knowledge of the operational implications of the 300000 Instrument Air X following concepts as they apply to 2.5 9 I**** r~~;*t; the INSTRUMENT AIR SYSTEM:

.. ' . Airc KS.Ol Knowledge of the operational implications of the 263000 DC Electrical .: following concepts as they apply to X 2.6 10 Distribution D.C. ELECTRICAL DISTRIBUTION: Hydrogen generation durin"" battery charging .

. '..:' K6.01 - Knowledge of the effect that a loss or malfunction of the I' following will have on the 261000 SGTS X 2.9 11

..... STANDBY GAS TREATMENT I",* SYSTEM: A.C. electrical distribution K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the 217000 RCIC X REACTOR CORE ISOLATION 3.5 12 COOLING SYSTEM (RCIC):

Condensate storage and transfer system AI.07 - Ability to predict andior monitor changes in parameters associated with operating the AVERAGEPO\VERRANGE 215005 APRM I LPRM X 3.0 13 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including; APRM (gain adjustment factor)

ES-401 6 Form ES-401-1 Hope Creek Station Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G 1 2 3 4 5 6 1 3 4 AI,03 - Ability to predict and/or J monitor changes in parameters associated with operating the LOW 209001 LPCS X "

3.8 14 PRESSURE CORE SPRAY

~

SYSTEM controls including:

I'ii!'i":: " Reactor water level A2.06 - Ability to (a) predict the

" I,

"', impacts of the following on the

.~ INTERMEDIATE RANGE 1 .'

's,; MONITOR (IRM) SYSTEM; and 2150031RM X (b) based on those predictions, use 3.0 15

,~~'~~ procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations:

Il Faulty Range Switch i7 , "":"'~:"

A2,0 I - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based on 215004 Source Range Monitor 5< those predictions, use procedures to 2.7 16

""'" conect, control, or mitigate the consequences of those abnonnal

"', conditions or operations: Power I"""~ supply degraded I,':,' A3.06 Ability to monitor

• .*. , automatic operations of the 203000 RHRlLPCI: Injection '

X RHRlLPCI: INJECTION MODE 3.7 17 Mode

,: I**** ",' * '*.* (PLANT SPECIFIC) including:

I ** ", ,.' Indicating lights and alanns I""'" A3,01 - Ability to monitor

~:s automatic operations of the CCWS 400000 Component Cooling including: Setpoints on instrument X 3.0 18 Water signal levels for nonnal operations, Ii,' warnings, and trips that are t,~::: applicable to the CCWS

,t\\~~'~fu'.l A4,02 - Ability to manually operate 223002 PCIS/Nuclear

,., X and/or morutor in the control room: 3.9 19 H

Steam Supply Shutoff

",*7: Manually initiate the system

~,~ MOl Abilily,"m,"~lly"p="

212000 RPS X I**** and/or monitor in the control room: 4.6 20 ProVIde manual SCRAM si2:Tlal(s)

I'h/ 2.1 30 - Conduct of Operations:

259002 Reactor Water Ability to locate and operate Level Control

.X' components, including local 4.4 21

"; controls.

2.1.32 ~ Ability to explain system 211000 SLC XF and apply system limits and 3.8 22 precautions.

fci~~

2.4,11 - Emergency Procedures I 212000 RPS Plan: Knowledge of abnonnal 4.0 23 condition procedures.

A4,04 Ability to manually operate 264000 Emergency X I~~i+ and/or monitor in the Control Room: Manual start, loading, and 3.7 24 Generators (Diesel/Jet) stopping of emergency generator.

Plant Specific

ES-401 7 Form ES-401-1 Hope Creek Station Written Examination Outline Plant Systems - Tier 2 Group 1 A3.0 I - Ability to monitor automatic operations of tbe 239002 SRVs RELIEFiSAFETY VALVES 3.8 25 including: SRV operation after ADS actuation K3.04 - Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION 217000 RCIC 3.6 26 COOLING SYSTEM (RCIC) will have on following: Adequate core KJA Category Totals: 2 1 Group Point Total:

ES-401 8 Form ES-401-1 Hope Creek Station Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # / Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A2.03 - Ability to (a) predict the impacts of the following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use 259001 Reactor Feedwater X 3.6 91 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of condensate pump(s) 2.2.42 - Equipment Control:

Ability to recognize system 226001 RHR/LPCI: CTMT X parameters that are entry-level 4.6 92 Spray Mode conditions for Technical Specifications.

2.2.37 - Equipment Control:

223001 Primary CTMT and Ability to determine operability X 4.6 93 Aux. and / or availability of safety related equipment.

K1.08 - Knowledge of the physical connections and/or cause- effect relationships 215001 Traversing In-core X between TRAVERSING IN 2.5 27 Probe CORE PROBE and the following: Reactor pressure vessel: (Not-BWR!l K2.02 - Knowledge of electrical 286000 Fire Protection X power supplies to the following: 2.9 28 Pumps K3.02 - Knowledge of the effect that a loss or malfunction of the 204000 RWCU X REACTOR WATER CLEANUP 3.1 29 SYSTEM will have on following:

Reactor water level K4.06 - Knowledge of RECIRCULATION FLOW CONTROL SYSTEM design 202002 Recirculation Flow X feature(s) and/or interlocks 3.1 30 Control which provide for the following:

Recirculation pump adequate NPSH: Plant-Specific K5.04 - Knowledge of the operational Implications of the following concepts as they apply 241000 ReactorlTurbine X to REACTORITURBINE 3.3 31 Pressure Regulator PRESSURE REGULATING SYSTEM: Turbine inlet pressure vs. reactor pressure K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the 201002 RMCS X 2.5 32 REACTOR MANUAL CONTROL SYSTEM: Select matrix power A 1.08 - Ability to predict and/or monitor changes in parameters 239001 Main and Reheat associated with operating the X 3.8 33 Steam MAIN AND REHEAT STEAM SYSTEM controls including:

Reactor pressure

ES-401 9 Form ES-401-1 Hope Creek Station Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A2.05 - Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEMS; and (b) based on those predictions, use 288000 Plant Ventilation X procedures to correct, control, 2.6 34 or mitigate the consequences of those abnormal conditions or operations: Extreme outside weather conditions: Plant-Specific A3.03 - Ability to monitor automatic operations of the 201001 CRD Hydraulic X CONTROL ROD DRIVE 2.7 35 HYDRAULIC SYSTEM including: System pressure A4.15 - Ability to manually 226001 RHR/LPCI: CTMT operate and/or monitor in the X 3.6 36 Spray Mode control room: Suppression chamber pressure: Mark-I-II 2.4.2 - Emergency Procedures I Plan: Knowledge of system set 259001 Reactor Feedwater X points, interlocks and automatic 4.5 37 actions associated with EOP entry conditions.

A 1.04 - Ability to predict and/or monitor changes in parameters associated with operating the 216000 Nuclear Boiler Inst. X 2.6 38 NUCLEAR BOILER INSTRUMENTATION controls including: System venting KIA Category Totals: 1 1 1 1 1 1 2 iii 1 1 1/2 Group Point Total: 12/3 I

ES-401 10 Form ES-401-3 Hope Creek Station Written Examination Outline Generic Knowledge and Abilities Outline (Tier 3)

Facility: Hope Creek Station Date: 03/05/12 RO SRO-Only Category KIA # Topic IR Q# IR Q#

Ability to use procedures to determine the effects on reactivity of plant changes, such as 2.1.43 4.3 94 RCS temperature, secondary plant, fuel depletion, etc.

Knowledge of the fuel-handling 2.1.35 3.9 98 responsibilities of SRO's.

1. Knowledge of industrial safety procedures Conduct (such as rotating equipment, electrical, high of Operations 2.1.26 3.4 66 temperature, high pressure, caustic, chlorine, oX)lgen and hydrogen).

Knowledge of how to conduct system 2.1.29 lineups, such as valves, breakers, switches, 4.1 67 etc.

Subtotal 2 2 Knowledge of the process for managing maintenance activities during power 2.2.17 operations, such as risk assessments, work 3.8 95 prioritization, coordination with the transmission system operator.

2.

Equipment Knowledge of the process for making Control 2.2.6 3.0 68 changes to procedures.

Knowledge of less than or equal to one hour 2.2.39 Technical Specification action statements for 3.9 69 systems.

Subtotal ". 2 1 Knowledge of radiation or containment 3.

hazards that may arise during normal, Radiation 2.3.14 3.8 96 abnormal, or emergency conditions or Control activities.

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.15 3.1 100 portable survey instruments, personnel monitoring equipment, etc.

ES-401 11 Form ES-401-3 Hope Creek Station Written Examination Outline Generic Knowledge and Abilities Outline (Tier 3) 2.3.11 Ability to control radiation releases. 3.8 70 Knowledge of Radiological Safety Principles I

pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 71 responsibilities, access to locked high-I radiation areas, aligning filters, etc. I Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 74 conditions. I Subtotal ~i ~ 3 ';%',!lii' 2 Knowledge of RO tasks performed outside 2.4.34 the main control room during an emergency 4.1 97 and the resultant operational effects.

Ability to take actions called for in the facility 2.4.38 emergency plan, including supporting or 4.4 99 acting as emergency coordinator if required.

4.

Emergency Proced u res / Knowledge of the bases for prioritizing safety Plan 2.4.22 functions during abnormal/emergency 3.6 72 operations.

Knowledge of procedures relating to a 2.4.28 3.2 : 73 security event.

2.4.18 Knowledge of the specific bases for EOPs. 3.3 75

~

I Subtotal 2 I Tier 3 Point Total 7

ES-401 12 Form ES-401-4 Record of Rejected KIA's

(:1roup Randomly Tic.. I Reason for Rejection Selected KIA Question #41 - Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS:

Shutdown margin. Over-sampled topic, see question #40, almost identical subject matter.

1 /1 295023/ AK1.02 Randomly selected AK1.03 - Knowledge of the operational implications of the following concepts as they apply to

• RE::FUELING ACCIDENTS: Inadvertent criticality.

Question #45, - Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Initiation of isolation condenser: Plant-Specific 1/1 295003/ AK.307 Hope Creek does not have isolation condensers.

Randomly selected AK3.01 - Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Manual and auto bus transfer Question #50, - Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: RPIS Control Rod Position Indication (RPIS) is not available outside of the Control Room.

1 /1 295016/ AA1.03 Randomly selected AA1.02 - Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT:

Reactor/turbine pressure regulating system Question #83, - Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment pressure:

Plant-Specific. Over-sampled topic, see question #62 - almost identical subject matter.

1 /2 2950351 EA2.01 Randomly selected 201 003/A2.1 0 Ability to (a) predict the impacts of the following on the CONTROL ROD At\ID DRIVE MECHANSIM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Excessive SCRAM time for a given drive mechanism Question #5 - Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following:

Uninterruptible power supply. Over-sampled topic, see question 2/1 262001 I K3.04 #8 - almost identical subject matter.

Randomly selected K3.01 Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following: Major system loads.

ES-401 13 Form ES-401-4 Record of Rejected KIA's Question #4, - Knowledge of electrical power supplies to the II following: ADS logic. Over-sampled topic, see question #3 2/1 218000 / K2.01 almost identical subject matter.

Randomly selected K3.02 - Ability to rapidly depressurize the reactor Question #24, - Ability to manually operate and/or monitor in the Control Room: TDRFP lockout reset. TDRFP Over-sampled topic, see questions #21 and #89 very similar subject matter.

2/1 259002/ A4.09

. Randomly selected 264000/A4.04 Emergency Generators

! (Diesel/Jet) Manual start, loading, and stopping of emergency

• generator. Plant Specific Question #91, - Ability to (a) predict the impacts of the following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of D.C. electrical power. Unable to write an SRO discriminating question for this topic.

2/2 259001 / A2.08 Randomly selected 259001/A2.03 - Ability to (a) predict the impacts of the following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of condensate pump(s).

Question #69, - Ability to track Technical Specification limiting conditions for operations. Reactor Operators are not responsible for this task.

3 2.2.23 Randomly selected 2.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements for systems.

Question #54 Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. Unable to write a discriminating question to 1 / 1 295005/2.1.7

! adequately address all the attributes of the selected KIA.

Randomly selected 2.1.31 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

Question #89 - Emergency Procedures / Plan: Ability to verify that the alarms are consistent with the plant conditions. Topic is over 2 / 1 259002 I 2.4.46 sampled, see Q's #60 and #76 Randomly selected 215004 SRMs and 2.2.38 - Knowledge of conditions and limitations in the facility license. II

E8-401 15 Form E8-401-4 Record of Rejected KIA's Question # 80, - Emergency Procedures I Plan: Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. After review of question selected, question

1. 78 is very similar in nature and will be retained, however #80 will 1 11 2950041 2.4.4 be reselected.

Randomly selected 295004/2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation (Partial or Complete Loss of DC power)

Question #22, - Equipment Control: Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. Determining the

! status of limiting conditions for operations (LCOs) is an SRO task 2/1 211000 / 2.2.36 at Hope Creek and is an unsuitable KIA for the RO section of the exam.

I Randomly selected 211000/2.1.32 - Ability to explain system and II apply system limits and precautions. (SLC)

ES-401 14 Form ES-401-4 Record of Rejected KIA's Question #83, - Had randomly selected: Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANSIM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Excessive SCRAM time for a given drive mechanism. This was chosen in error and was rejected due to being in the Tier 2 Group 2 NOT Tier 2 Group 1 as required by the outline. The original KIA, 2950351 EA2.01, Ability to determine and/or interpret the following as they apply to 1 12 201003/A2.10 SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment pressure: Plant-Specific.

Was an over-sampled topic, see question #62 - almost identical subject matter.

Randomly selected 295013/A2.01 High Suppression Pool

! Temperature, Ability to determine and/or interpret the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE:

Suppression Pool Temperature Question #87, - A2.1 0 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions Changes in void concentration. Due to a heavy concentration of Nuclear Instrumentation topics. Rejected this KIA and reselected an 2/1 215005/ A2.10 additional topic.

Randomly selected 262001/A2.04 - Ability to (a) predict the impacts of the following on the AC. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Types of loads that, if de-energized, would hinder plant operation.

Question #88, - Equipment Control: 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. Due to a heavy concentration of Nuclear Instrumentation topics. Reselected a different system and retained the original generic part of the KIA. This was done to 2/1 215003/2.2.44 maintain the balance of the outline.

Randomly selected 261000/2.2.44 Ability to interpret control room indications to verify the status and operation of a system, i and understand how operator actions and directives affect plant I and system conditions. (SGTS)

HC ILT 2012 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility: Hope Creek Date of Examination: 3/5/2012 Examination Level: ~ RO D SRO Operating Test Number: NRC 2012 Administrative Topic Type Describe activity to be performed (See Note) Code*

Conduct of Operations S,D 2.1.31 ZZ024 Perform power distribution lineup.

2.1.18 ZZ016 Complete the Daily Logs Conduct of Operations S,D,P (Complete Att 1A for 609,611, MSLRMS)

(2009 NRC) 2.2.40 ZZ011 Re-start Reactor Recirc Pump lAW Equipment Control S,M Attachment 2.

Radiation Control S,M 2.3.5 ZZ019 Calculate Noble Gas Release Rate.

Emergency Plan N/A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• 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)

HC ILT 2012 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility: Creek Date of Examination: - - -3/5/2012 Examination Level: 0 RO ~ SRO o perating Test Number: _:....::N:....::R:....;:C_2_0:....::1:....::2_

Administrative Topic

• Type Describe activity to be performed (See Note)

I Code" Conduct of Operations

• R,N i 2.1.25 ZZ045 Perform On-Line Risk Controls Evaluation Conduct of Operations R,D,P 2.1.18 ZZ017 Review DL-26 (2009 NRC) 2.2.12 ZZ027 Review OP-IS.ZZ-0003 for Completeness Equipment Control R,M and Compliance with Acceptance Criteria.

Radiation Control R,D 2.3.6 ZZ003 Approve Containment Purge permit.

• 2.4.38 ECG003 Utilize the ECG to Classify an Event Emergency Plan R,M (Barrier Table General Emergency/PAR) I NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• 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 (::;1; randomly selected)

(A)lternate Path

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Date of Examination: 3/5/2012 Exam Level: RO [8] SRO-I 0 SRO-U 0 Operating Test No.: NRC2012 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function I

a. AE004 Respond To Rising Drywell Pressure (KIA 223001 A2.01) S,A, L, D 2

b. BC015 Transfer Shutdown Cooling to the Standby Shutdown Cooling S, A, L, N 4 Loop (KIA 205000 A4.03)

c. CG003 Respond to Main Condenser Low Vacuum (KIA 271000 A4.04) S, M 9

d. GS005 Vent To Control Containment Pressure With Suppression Pool S,A,D, E, L 5 Level Less Than 180 Inches (KIA 295024 EA1.19)

e. BF011 Respond To An Uncoupled Control Rod (KIA 201003 A2.02) S,A,D 1

f. SB010 Respond To A Reactor Protection System Malfunction (KIA S,D,EN 7 212000 A2.02)

g. ED002 Respond To A Reactor Auxiliary Cooling Malfunction (KIA S,A,D, P 8 295018 M2.02) (NRC 2009)

• h. AB001 Bypass MSIV Isolation Interlocks With MSIVs Closed/Open (KIA S,D,E 3 239001 A2.03)

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

i. EG003 Respond To A Safety Auxiliaries Cooling Water Malfunction D,R 8 (KIA 400000 A2.01)

• j. AB003 Respond To A Failed Open Safety Relief Valve (KIA 239002 D,E 3 A2.03)

k. PK001 Respond To A Station Blackout (KIA 295003 M 1.04) D,E,R 6

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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-II SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant  ;::1/;::1/;::1 (EN)gineered safety feature - I - I ;::1 (control room system)

(L)ow-Power 1Shutdown  ;::1/::=1/::=1 (N)ew or (M)odified from bank including 1(A)  ;::2/;::2/::::1

• (P)revious 2 exams s 3/ s 31 s 2 (randomly selected)

(R}CA  ::::1/::::1/::::1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Date of Examination: 3/5/2012 Exam Level: RO D SRO-I ~ SRO-U D Operating Test No.: NRC2012 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. AE004 Respond To Rising Drywell Pressure (KIA 223001 A2.01) S,A, L, D 2

b. BC015 Transfer Shutdown Cooling to the Standby Shutdown Cooling S, A. L, N 4 Loop (KIA 205000 A4.03)

c. CG003 Respond to Main Condenser Low Vacuum (KIA 271000 A4.04) IS, E, M 9

d. GS005 Vent To Control Containment Pressure With Suppression Pool S, A. D, E, L 5 Level Less Than 180 Inches (KIA 295024 EA 1.19)

e. BF011 Respond To An Uncoupled Control Rod (KIA 201003 A2.02) S,A,D 1

f. SB010 Respond To A Reactor Protection System Malfunction (KIA S,D,EN 7 212000 A2.02)

g. ED002 Respond To A Reactor Auxiliary Cooling Malfunction (KIA S,A,D,P 8 295018 M2.02) (NRC 2009)

h. NA - -

I =

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

i. EG003 Respond To A Safety Auxiliaries Cooling Water Malfunction (KIA D,R 8 400000 A2.01)

I

j. AB003 Respond To A Failed Open Safety Relief Valve (KIA 239002 D,E 3 A2.03)

k. PK001 Respond To A Station Blackout (KIA 295003 M1.04) D,E,R 6

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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 1 SRO-I / SRO-U (A)lternate path 4-6 1 4-6 12-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant 2!1/2!1/2!1 (EN)gineered safety feature - / - 1 2!1 (control room system)

(L)ow-Power / Shutdown 2!1/2!1/2!1 (N)ew or (M)odified from bank including 1(A) 2!2/2!21?:.1 (P)revious 2 exams :5 3 / :5 3 / :5 2 (randomly selected)

(R)CA 2!1/?:.1/2!1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Date of Examination: 3/5/2012 Exam Level: RO 0 SRO-I 0 SRO-U [R] Operating Test No.: NRC2012 i Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title Type Code* Safety Function

a. AE004 Respond To Rising Drywell Pressure (KIA 223001 A2.01) S,A,L, ° 2 I b. BC015 Transfer Shutdown Cooling to the Standby Shutdown Cooling S,A,L,N 4

. Loop (KIA 205000 A4.03)

c. NA - -

I d. NA - -

e. NA - i -

i f. SB010 Respond To A Reactor Protection System Malfunction (KIA S,D,EN 7 212000 A2.02)

g. NA - -

h. NA - -

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

i. NA - -

j. AB003 Respond To A Failed Open Safety Relief Valve (KIA 239002 D,E 3 A2.03)

k. PK001 Respond To A Station Blackout (KIA 295003 M1.04) D,E,R 6

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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 1 SRO-II SRO-U (A)lternate path 4-6/4-6 12-3 (C)ontrol room (D)irect from bank  :;;9/:;;8/:;;4 (E)mergency or abnormal in-plant  ;:;1/;:;1/;:;1 (EN)gineered safety feature - I - 1 ;:;1 (control room system)

(L)ow-Power I Shutdown  ;:;1/;:;1/;::1 (N)ew or (M)odified from bank including 1(A)  ;:: 2/?:. 2/;:: 1 (P)revious 2 exams :s 3 / :s 3 / :s 2 (randomly selected)

! (R)CA  ;:;1/?:.1/;::1

• (S)imulator il I I

Appendix 0 Scenario Outline Form ES-O-1 Facility: Hope Creek Scenario No.: J.... Op-Test No.: NRC2012 Examiners: Operators: (SRO)

(ATC)

(BOP)

Initial Conditions: 93% power.

Turnover: Raise reactor power to 98% per Load Dispatcher request.

Event Malf. Event Type* Event No. No. Description 1 N/A R (ATC) Raise power to 98% with recirculation flow.

N (SRO) 2 MS09A I (SRO) PT-N076A MSL Pressure Fails Upscale (TS) 3 CD10A C (ATC) "AI> CRD Pump Trip C (SRO) 4 PC07A C (All) OBE Earthquake wi 10A403 Bus Fault & Lockout ED16 (TS) 5 RR31A1 C (All) Small break LOCA / Manual Scram 6 PC07B M (All) Aftershock wi LOP, Main Generator Lockout, "B" EG12 EDG Start Failure (recoverable), "A" & "0" EDG fail resulting in unrecoverable loss of 10A401 & 10A404 DG08B Buses DG02A DG02C DG02D I 7 HP01 C (BOP) i HPCI & RCIC auto start failure (RCIC recoverable)

HP06M RC02 RC05 I

• (N}ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX 0, Page 38 of 39

Appendix 0 Scenario Outline Form ES-O-1 Facility: Hope Creek Scenario No.:.£ Op-Test No.: NRC2012 Examiners: Operators: (SRO)

(ATe)

(BOP)

Initial Conditions: 84.5% power Turnover: Power ascension in progress. Raise power 84.5% to 90% using control rods.

Place C RFPT in service.

il Lve' ,v,alf. Event Type* Event No. No. Description 1 NA R (ATC) . Raise power 84.5% to 90% using control rods.

N (BOP)

• Place C RFPT in service.

N (SRO) 2 CD032631 C (ATe) Stuck Control Rod. (TS SRO) I C (SRO) 3 NM12B I (ATe) Flow Unit Fails Downscale w/half scram. (TS SRO)

I (SRO) 4 TC07A C (ATC) A EHC Pump trip C (SRO) 5 TC16 C (All) Loss of EHC due to Filter Clogging wI Manual Scram i

I 6 RP07 M (All) ATWS i

7 CU11A C (ATC) Failure of RWCU to auto isolate.

CU11B 8 HP06E C (BOP) HPCI components failure to auto initiate HP14 HP15 il i HP16 i

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 4-LP Op-Test No.: NRC2012 Examiners: Operators: (SRO)

(ATC)

(BOP)

Initial Conditions: 3% power.

Turnover: Continue Reactor Startup using control rods.

Swap SSW pump alignment to remove D SSW Pump from service for planned maintenance.

Event Malf. Event Type* Event No. No. Description 1 NA R (ATC) Raise Reactor power with control rods.

N (SRO) I 2 CD022603 C (ATC) Rod drifts out. (TS SRO)

C (SRO) 3 NA N (BOP) Swap Service Water Pumps 4 CW05A C (BOP) Service Water Pump Malfunction (TS SRO)

C (SRO) i 5 RR08B C (ATC) Single Reactor Recirc Pump Runaway (TS SRO)

C(SRO) Recirc Pump Vibrations I

6 CR01 I C (ALL) Fuel Failure With Scram 7 PC06 M (ALL) Torus Leak/Emergency Depressurization 8 RH03B C (BOP) RHR HX inlet valve F047B fails closed

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39