ML090720629

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Final Outlines (Folder 3)
ML090720629
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 11/28/2008
From: Parrish M
Public Service Enterprise Group
To: D'Antonio J
Operations Branch I
Hansell S
Shared Package
ML082600269 List:
References
50-354/09-301, ES-401, ES-401-1, TAC U01693 50-354/09-301
Download: ML090720629 (24)
v • d • e


Text

ES-401 Written Examination Outline Form ES-401-1 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 (i.e., 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).

'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 f1 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.

Systemslevolutions 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.1.b of ES-401, for guidance regarding elimination of inappropriate KIA statements.

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.

Absent a plant specific priority, only those KAs 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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

The generic (G) KIAs 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 KIA's 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 #I does not apply). Use duplicate pages for RO and SRO-only exams.

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 KIAs that are linked to 10CFR55.43

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AA2.01 - Ability to deterrnine and/or 295021 Loss o f Shutdown interpret the following as they apply to X 3, 76 Cooling / 4 LOSS OF SHUTDOWN COOLING :

Reactor water heatup/cooldown rate AA2.05 - Ability to determine and/or 295023 Refueling Accidents / interpret the following as they apply to X 4,6 77 8 REFUELING ACCIDENTS : Entry conclitions of Emergency plan AA2.02 - Ability to cletermine and/or ir~terpretthe following as they apply to 295019 Partial o r Total Loss X PARTIAL OR COMPLETE LOSS OF 3.7 78 o f lnst. Air / 8 INSTRUMENT AIR : Status of safety-related instrument air system loads 2.1.23- Conduct of Operations: Ability 295025 High Reactor to perform specrfic system and 4.4 79 Pressure / 3 integrated plant procedures dunng all modes of operation.

2.1.7 - Condiict of Operations: Ability to evaluate plant performance and rnake 295026 Suppression Pool X operational judgments based on 4.7 80 High Water Temp. / 5 operating characterrsbcs, reactor behavior, and instrument interpretation.

2.4.3 - Emergency Procedures / Plan:

295031 Reactor L o w Water X Ability to identify post-accident 3.9 81 Level / 2 instrumentation EA2.03- Ability to determine and/or interpret the following as they apply to 295028 High Drywell X HIGH DRYWELL TEMPERATURE : 3.9 82 Temperature / 5 Reactor water level AKI .01 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE 295018 Partial o r Total Loss LOSS OF COMPONENT C001-ING 3.5 39 of CCW 1 8 WATER : Effects on componenVsystem operations AKI .03 - Knowledge of the operational implications of the following concepts as 295006 SCRAM 1 I X they apply to SCRAM : Reactivity 3.7 40 control AKI .02 - Knowledge of the operational implications of the following concepts as 295001 Partial or Complete they apply to PARTIAL OR COMPLETE Loss of Forced Core Flow X 3,3 4, LOSS OF FORCED CORE FLOW Circulation 1 1 8 4 CIRCULATION : Powerlflow distribution AK2.02 - Knowledge of the interrelations between GENERATOR 700000 Generator Voltage VOLTAGE AND ELECTRIC GRID and Electric Grid X 3.1 42 DISTURBANCES and the following:

Disturbances Breakers, relays.

EK2.02 - Knowledge of the interrelations between LOW 295030 Low Suppression X SUPPRESSION POOL WATER LEVEL 3.7 43 Pool Water Level 1 5 and the following: RCIC: Plant-Specific

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AK2.01 - Knowledge of the 295004 Partial or Total Loss interrelations between PARTIAL OR 44 X 3.1 of DC Pwr 1 6 COMPLETE LOSS OF D.C. POWER and the following: Battery charger AK3.01 - Knowledge of the reasons for 295023 SCRAM Conditions the following responses as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND 45 X REACTOR POWER ABOVE APRM Above APRM Downscale or Unknown 1 I DOWNSCALE OR UNKNOWN : Recirc Pump TripIRunback EK3.04 - Knowledge of the reasons for 295026 Suppression Pool the following responses as they apply to X 3,7 46 High Water Temp. I 5 SUPPRESSION POOL HIGH WATER TEMPERATURE: SBLC injection EK3.05 - Knowledge of the reasons for 295025 High Reactor the following responses as they apply to 47 X 3,6 Pressure 1 3 HIGH REACTOR PRESSURE : RCIC operation: Plant-Specific EK3.05 - Knowledge of the reasons for 295031 Reactor Low Water the following responses as they apply to 4,2 48 X REACTOR LOW WATER LEVEL:

Level 1 2 Emergency depressurization AA1.03 - Ability to operate andlor monitor the following as they apply to 295019 Partial or Total Loss X PARTIAL OR COMPLETE LOSS OF 3.0 49 o f Inst. Air I 8 INSTRUMENT AIR : Instrument air compressor power supplies EAI.03 - Ability to operate andlor monitor the following as they apply to 295038 High Off-site Release X HIGH OFF-SITE RELEASE RATE: 3.7 50 Rate I 9 Process liquid radiation monitoring system AA2.04 - Ability to determine andior 295003 Partial or Complete interpret the following as they apply to X 3.5 51 Loss of AC 1 6 PARTIAL OR COMPLETE LOSS OF A.C. POWER : System lineups AA2.03 - Ability to determine and/or 295005 Main Turbine interpret the following as they apply to 52 X 3,1 Generator Trip 1 3 MAIN TURBINE GENERATOR TRIP :

EA2.02 -Ability to determine andlor 295037 SCRAM Conditions interpret the following as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND X 4,, 53 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown 1 1 DOWNSCALE OR UNKNOWN :

Reactor water level 2.1.28 - Conduct of Operations:

295021 Loss of Shutdown Knowledge of the purpose and function

, 5q Cooling 1 4 of major system components and controls.

2.4.1 - Emergency Procedures I Plan:

295024 High Drywell X Knowledge of EOP entry conditions and 4.6 55 Pressure 1 5 immediate action steps.

2.4.46 - Emergency Procedures / Plan:

295016 Control Room X Ability to verify that the alarms are 4.2 56 Abandonment 1 7 consistent with the plant conditions.

EK2.01 - Knowledge of the 295028 High Drywell interrelations between HlGH DRYWELL X 3,7 57 Temperature 15 TEMPERATURE and the following:

Drywell spray: Mark-l&ll 600000 Plant Fire On-site 18 X AA1.06 - Ability to operate and I or 3.0 58

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 monitor the following as they apply to PLANT FIRE ON SITE: Fire Alarm KIA Category Totals: 3 4 4 3 314 313 Group Point Total: 2017

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 M 2 . O f - Ability to cfetermine and/or 295033 High Secondary rnferprct lhe followrng as they apply to Containment Area Radiation X kfI(;H SECONDARY CONTAINMENT 3.9 83 Levels / 9 AREA RADIATION LEVELS. Area Radiatton levels 2.4.21 - Emergency Procedures /Plan-Knowledge of the parameters and logrc used to assess the statirs of safety 295017 High Offsite Release functions, such as reactivity control, core 84 Rate / 9 cooling and heat removal, reactor coolant system ir?tegrity,containment conditions, radioactivity release control, etc.

2.4.30 - Emergency Procedures / Plan:

Knowledge of evenls related to system 295015 Incomplete SCRAM / 1 operation/statos tl-~ntniusl be reported to rnternal organizations or external

, 85 agencies, such as State, the NRC, or the triir,srr?rss!orlsystem operator AKI .O1 - Knowledge of the operational implications of the following concepts as 295010 High Drywell X they apply to HIGH DRYWELL 3.0 59 Pressure 1 5 PRESSURE : Downcomer submergence: Mark-18.11 AK2.03 - Knowledge of the interrelations between LOSS OF CRD 3.4 295022 Loss of CRD Pumps X 60 PUMPS the following: Accumulator pressure EK3.02 - Knowledge of the reasons for 295032 High Secondary the following responses as they apply to Containment Area X HIGH SECONDARY CONTAINMENT 3.6 61 Temperature I 5 AREA TEMPERATURE : Reactor SCRAM EAI .O1 - Ability to operate andlor 295029 High Suppression monitor the following as they apply to X 3,4 62 Pool Water Level 1 5 HIGH SUPPRESSION POOL WATER LEVEL : HPCI: Plant-Specific

,442.02 - Ability to determine andlor 295012 High Drywell interpret the following as they apply to X 3,9 63 Temperature I 5 HIGH DRYWELL TEMPERATURE :

Drywell pressure 2.1.20 - Conduct of Operations: Ability 295009 Low Reactor Water X to interpret and execute procedure 4.6 64 Level 12 steps.

AK3.02 - Knowledge of the reasons for the following responses as they apply to 295013 High Suppression X HIGH SUPPRESSION POOL 3.6 65 Pool Temperature 1 5 TEMPERATURE : Limiting heat additions WA Category Totals: 1 1 2 1 117 112 Group Point Total: 713

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 2 2.37 - Equipn~entControl:

Ability to determine operability 206000 HPCl X and/or availabil~tyof safety 46 86 related equipment.

2.2.40 - Ability to apply 209001 LPCS X Technical Specifications for a 4.7 87 system.

2.4.47 - Emergency Procedures

/Plan. Ability to diagnose and lecognize trends in an accurafe 21 1000 SLC 42 88 and firnely manner utilizing the appropriate cor~trolroom reference r-nater~al 2.2.22 - Equipment Control:

205000 Shutdown Cooling X Knowledge of lirnitrng conditions 4.7 89 for operations and safety lilnits.

A2.02 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based 275004 Source Range Monitor X on those predictions, use 3.7 90 procedures to correct, control, or mitigate tk~econsequences of those abnormal conditions or operations: SRM inop condition K1.04 - Knowledge of the physical connections and/or cause- effect relationships between SHUTDOWN 205000 Shutdown Cooling X 2.7 1 COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: Fuel pool cooling assist: Plant-Specific K1.02 - Knowledge of the physical connections andlor cause- effect relationships 218000 ADS X between AUTOMATIC 4.0 2 DEPRESSURIZATION SYSTEM and the following: Low Pressure Core Spray 215004 Source Range K2.01 - Knowledge of electrical Monitor X power supplies to the following: 2.6 3 SRM channelsldetectors K2.01 - Knowledge of electrical 239002 SRVs X power supplies to the following: 2.8 4 SRV solenoids K3.03 - Knowledge of the effect that a loss or malfunction of the 217000 RClC REACTOR CORE ISOLATION X 3'5 COOLING SYSTEM (RCIC)will have on following: Decay Heat removal K3.03 - Knowledge of the effect that a loss or malfunction of the 206000 HPCl HIGH PRESSURE COOLANT X 3,4 INJECTION SYSTEM will have on following: Suppression pool level control: BWR-2.3,4

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K4.02 - Knowledge of (INSTRUMENT AIR SYSTEM) 300000 Instrument Air design feature(s) and or X 3.0 7 interlocks which provide for the following: Cross-over to other air systems K4.05 - Knowledge of A.C.

ELECTRICAL DISTRIBUTION 262001 AC Electrical design feature(s) and/or X 3.4 8 Distribution interlocks which provide for the following: Paralleling of A.C.

sources K5.06 - Knowledge of the operational implications of the 264000 EDGs following concepts as they apply X 3,4 to EMERGENCY GENERATORS (DIESEUJET) :

Load Sequencing K5.02 - Knowledge of the operational implications of the following concepts as they apply 212000 RPS X 3.3 to REACTOR PROTECTION SYSTEM : Specific logic arrangements K6.01 - Knowledge of the effect that a loss or malfunction of the 263000 DC Electrical X following will have on the D.C. 3.2 11 Distribution ELECTRICAL DISTRIBUTION :

A.C. electrical distribution K6.05 - Knowledge of the effect that a loss or malfunction of the 215003 IRM following will have on the X 3.1 12 INTERMEDIATE RANGE MONITOR (IRM) SYSTEM : Trip units A1.O1 - Ability to predict and/or monitor changes in parameters 203000 RHRILPCI: associated with operating the X 4,2 13 Injection Mode RHRILPCI: INJECTION MODE (PLANT SPECIFIC) controls including: Reactor water level A1.04 - Ability to predict andlor monitor changes in parameters associated with operating the 261000 SGTS X STANDBY GAS TREATMENT 3.0 14 SYSTEM controls including:

Secondary containment differential pressure A2.04 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on those predictions, use 21 1000 SLC X 3.1 15 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K1.03 - Knowledge of the physical connections andlor cause effect relationships 223002 PClSlNuclear X between PRIMARY Steam Supply Shutoff 3'0 l6 CONTAINMENT ISOLATION SYSTEMINUCLEAR STEAM SUPPLY SHUT-OFF and the following: Plant ventilation A3.01 - Ability to monitor automatic operations of the UNINTERRUPTABLE POWER 262002 UPS (ACIDC) X 2,8 17 SUPPLY (A.C.1D.C.)including:

Transfer from preferred to alternate source A3.03 - Ability to monitor automatic operations of the 209001 LPCS X LOW PRESSURE CORE 3.5 18 SPRAY SYSTEM including:

System pressure A4.03 -Ability to manually operate and/or monitor in the 215005 APRM I LPRM X control room: APRM back panel 3.2 19 switches, meters and indicating lights A4.01 - Ability to manually 400000 Component operate andlor monitor in the X 3.1 20 Cooling Water control room: CCW indications and control 2.2.25 - Equipment Control:

Knowledge of bases in technical 218000 ADS X specifications for limiting 3.2 21 conditions for operations and safety limits. -

2.4.31 - Emergency Procedures I Plan: Knowledge of 239002 SRVs 4.2 22 annunciator alarms, indications.

or response procedures.

A4.02 - Ability to manually 203000 RHRILPCI: operate and/or monitor in the X 4.1 23 Injection Mode control room: System valves K4.09 - Knowledge of LOW PRESSURE CORE SPRAY 209001 LPCS SYSTEM design feature(s)

X 3.3 24 and/or interlocks which provide for the following: Load Sequencing K5.03- Knowledge of the operational implications of the 259002 Reactor Water following concepts as they apply X 3.1 25 Level Control to REACTOR WATER LEVEL CONTROL SYSTEM :Water level measurement A3.02 - Ability to monitor 261000 SGTS automatic operations of the X STANDBY GAS TREATMENT 3'9 26 SYSTEM including: Fan start WA Category Totals: 3 2 2 3 3 2 2 1 1 1 3 3 2 1 4 Group Point Total: 2615

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 A2.02 - Abil~tyto (a) predicf the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS ;

and 245000 Main Turbine Gen.

X (b) based on those predictions, 3.5 91 l Aux.

use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations. Loss of lube 011 2.4.49 Emergency Procedures

/Plan. Ab111tyto perform witlioc~t reference to procedures those 202001 Recirculation 4.4 92 actions that require ~mmediate operation of system coniponents arid confrols.

A2.07 - Ability to (a) pred~ctthe irnpacts of the following on ttie TIPS; and (b) based on those predictions, use procedures to 215001 TIPS X correct, control. or [nibgate the 3.7 93 consequences of those abnornial conditions or operatior~s:Failure to refract during acoderit conditiorts K1.O1 - Knowledge of the physical connections andlor cause- effect relationships 201003 Control Rod and between CONTROL ROD AND 3.2 27 Drive Mechanism DRIVE MECHANISM and the following: CRD Hydraulic system A3.01 - Ability to monitor automatic operations of the 226001 RHfULPCI: CTMT RHRILPCI: CONTAINMENT 3.0 28 Spray Mode X SPRAY SYSTEM MODE including: Valve operation K3.03 - Knowledge of the effect that a loss or malfunction of the 234000 Fuel Handling X FUEL HANDLING EQUIPMENT 3.1 29 Equipment will have on following: Fuel handling operations K4.01 - Knowledge of (ROD POSITION INFORMATION 214000 RPlS X SYSTEM) design feature(s) and 3,0 30 or interlocks which provide for the following: Reed switch locations K5.07- Knowledge of the operational implications of the following concepts as they apply 245000 Main Turbine to MAIN TURBINE Generator and Auxiliary X 2.6 31 GENERATOR AND Systems AUXILIARIES SYTEMS:

Generator operations and limitations

Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K6.08 - Knowledge of the effect that a loss or malfunction of the 204000 RWCU X following will have on the 3.5 32 REACTOR WATER CLEANUP SYSTEM : PCISINSSSS A1 . I 0 - Ability to predict andlor monitor changes in parameters associated with operating the 201001 CRD Hydraulic X CONTROL ROD DRIVE 2.8 33 HYDRAULIC SYSTEM controls including: CRD cooling water flow A2.12 -Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM ; and (b) based on 239001 Main and Reheat those predictions, use Steam X 4.2 34 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: PCISINSSSS actuation A3.01 - Ability to monitor automatic operations of the 215002 RBM X ROD BLOCK MONITOR 3.1 35 SYSTEM including: Four rod display: BWR-3,4,5 A4.07 - Ability to manually 241000 ReactorlTurbine operate andlor monitor in the X 3,5 36 Pressure Regulator control room: Main stoplthrottle valves (operation) 2.2.39 - Equipment Control:

223001 Primary CTMT Knowledge of less than or equal and Aux. 3.4 37 to one hour Technical Specifications for a system A1.06 - Ability to predict andlor monitor changes in parameters 259001 Reactor associated with operating the Feedwater X 2,7 38 REACTOR FEEDWATER SYSTEM controls including:

Feedwater heater level KIA Category Totals: 1 0 1 1 1 1 2 1 1 2 2 1 111 Group Point Total: 1213

ES-401 Record of Rejected K/A1s Form ES-401-4 Facility: Hope Creek Written Exam Date:

RO SRO-Only Category KIA # Topic IR Q# IR Q#

Knowledge of primary and secondary plant 2' 3.5 I00 chemistry limits.

Knowledge of fuel-handling responsibilities of 2.7.35 3.9 94 SROs Knowledge of shift or short-term relief 2.1 .3 3.7 71 turnover practices

1. Knowledge of individual licensed operator Conduct responsibilities related to shift I of Operations 2.1-4 staffing, such as medical requirements, "no- 3.3 67 solo" operation, maintenance (

of active license status, 10CFR55, etc.

Ability to locate and operate components, 2'1.30 4.4 66 including local controls.

Subtotal 3 2 Knowledge of the process for condi~cting 2.2.7 special or infrequent tests. 3.6 95 Knowledge of the process for managing maintenance activities during shutdown 2'2'18 3.9 96 operations. such as risk assessments. work prioritization, etc.

2.

Equipment Control Knowledge of the process for making 2'2'6 3.0 68 changes to procedures 2.2.12 Knowledge of surveillance procedures 3.7 69 Knowledge of tagging an clearance 2'2'13 4.1 74 procedures Subtotal 3 2 3.

Radiation Knowledge of Radiological Safety Principles Control pertaining to licensed operator duties such as 2.3.12 containment entry requirer??ents,fuel handling 3.7 99 responsibilities, access to high radiation areas, aligning filters, etc.

Knowledge of radiation exposure limits under 2.3.4 3.2 70 normal or emergency conditions.

Record of Rejected WA's Form ES-401-4 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, 2'3'13 3.4 75 containment entry requirements. fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 2 1 2.4.6 Knowledge of EOP mitigation strategies. 4.7 97 Knowledge of SRO responsibilities in 2.4.40 4.5 98 emergency plan implementation

4. Knowledge of the specific bases for EOPs.

Emergency 2'4m18 3.3 73 (terminating DW spray at 0 psig)

Procedures / Knowledge of emergency communications Plan 2m4'43 3.2 72 systems and techniques.

Subtotal 2 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected WA's Form ES-401-4

  1. 9) Same topic as #8 (parallel of AC sources). Randomly elected K5.06 ctuation logic). Randomly selected K1.03 ystem. Randomly selected K4.09
  1. 30) Not applicable at HC. Randomly selected K4.01

Record of Rejected WA's Form ES-401-4 1 Ability to operate and/or monitor the following as (#21) Ability to operate plant equipment in the event of low they apply to REACTOR RPV level is tested frequently in the operating exam.

LOW WATER LEVEL :

Feedwater Randomly selected EK3.05 Knowledge of the reasons for the following responses as they apply (#45) Refueling topic is oversampled (#29, #94). Randomly to REFUELING selected 295037 K3.01 ACCIDENTS : Interlocks associated with fuel handling equipment 600000 12.2.38 Ability to analyze the effect of maintenance activities, such as (#58) This is an SRO function at HC. Randomly selected degraded power sources, on the status of AAI .06 limiting conditions for operations.

Knowledge of electrical power supplies to the (#28) Not a discriminating topic at the RO level (pump following: Knowledge of electrical power supplies power supply) reselected A3.03 to the following: Valves Knowledge of the interrelations between HlGH CONTAINMENT (#60) Guidance is contained in SAGS for this event. Could HYDROGEN not write an operational valid question for this topic at the CONCENTRATIONS the following: Drywell RO level. Randomly selected 295022 AK2.03 nitrogen purge system APRMs - Ability to use plant computers to (#26) System (Nls) & Topic oversampled (see #19).

evaluate system or Randomly selected 261000 A3.02 component status.

2.1 .21 - Ability to verify the controlled (#67) Topic oversampled (see #68 & #69). Randomly procedure copy. selected 2.1.4 2.2.43 Knowledge of the process to track (#74) Could not write a discriminating question for the inoperable alarms topic. Randomly selected 2.2.13 Ability to determine and/or interpret the following as they apply (#83) Same WA as # 63. Randomly selected 295033 to HlGH DRYWELL EA2.01 TEMPERATURE :

Drywell Pressure

ES-401 Record of Rejected WA's Form ES-401-4

(#84) Topic did not lend itself to a discriminating SRO level question. Randomly selected 295017 218000 1 A2.05 Ability to (a) predict the impacts of the following on the AUTOMA TIC DEPRESSUR17ATION SYSTEM ;and (b) besed on tttose (#90) Double jeopardy with #4. Randomly selected 215004 control, or mifrgate the consequences of those abnormal conditions or operations: Loss of A C.

or D.C power to ADS

(#93) Does not apply at HC. Randomly selected 21 5001

Record of Rejected KIA's Form ES-401-4 ssoaated with plant

HC ILT 2009 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 I Facility: Hope Creek Date of Examination:

RO: 3.1 SRO: 4.6 Equipment Control Radiation Control Emergency Plan (D)irect from bank (s 3 for ROs; s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (21)

(P)revious 2 exams (<I; randomly selected)

(A)lternate Path

HC ILT 2009 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 1 Facility: Hope Creek Date of Examination: 2/2/09 Exarr~inationLevel: RO SRO Operating Test Number: NRC 2009 Administrative (See Note)

( Type Code*

1 Describe activity to be performed 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Conduct of Operations RO: 2.9 SRO: 3.9 22009 Ensure Shift is Adequately Manned (RO will exceed guidelines. Requires Authorization Form) 2.1 . I8 Ability to make accurate, clear and concise logs, I 1 records, status boards, and reports. 1 0

RO: 3.9 SRO: 4.0 Conduct of Operations 22017 Initiate the Daily Surveillance Log (Shiftly Routine. Due to Plant Conditions, three optional attachments are required) 1 I 1 RO:

2.2.12 Knowledge of surveillance procedures 3.7 SRO: 4T1 Equipment Control N7 Authorize the Start of a Surveillance Test (One Hour ST.ZZ-0001 for Inoperable EDG) 2.3.11 Ability to control radiation releases RO: 3.8 SRO: 4.3 22032 Determine RCS Pressure Boundary Leak Rate Radiation Control (Review of completed surveillance determines math error made and actual leakage exceeds Tech Spec.

Determine reauired actions) 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as I

Emergency Plan D, R emergency coordinator if required RO: 2.4 SRO: 4.4 ECGOOG Classify Loss of All Barriers & Determine PAR ,

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the admin~strativetopics, when 5 are required.

!I

  • Type Codes & Criteria: (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (I 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (21)

(P)revious 2 exams (51 ; randomly selected)

(A)lternate Path

ES-301 Control Roomlln-Plant Svstems Outline Form ES-301.lb Facility: Hope Creek Date of Examination: 2/2/09 Exam Level: RO SRO-I SRO-U (XJ Operating Test No.: NRC2009 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* 1 Safety Function 1

I rl

b. Manually Start The Core Spray System (BE005) A, C, D, EN. 2- (
d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) (BC009)
e. Respond To A Containment Isolation (SM002) A, C, N, L, S In-Plant systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) I
i. Conduct Emergency Makeup To The RPV Using Two CRD Pumps (BF013)
k. Transfer RPS Bus A/B Power From Alternate Source To RPS MG Set (SB015)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those C

tested in the control room.

  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank s9158154 (E)mergency or abnormal in-plant 21121121 (EN)gineered safety feature 1 21 (control room system)

(L)ow-Power I Shutdown 2 l l ~ l l r l (N)ew or (M)odified from bank including 1(A) 221r21r I (P)revious 2 exams 5 3 1 5 3 1 5 2 (randomly selected) 211~1121 (S)imulator

I I

ES-301 Control Roomlln-Plant Svstems Outline Form E S - ~ O < &

Facility: Hope Creek Date of Examination: 2/2/09 Exam Level: RO SRO-I SRO-U Operating Test No.: NRC2009 Q

Control Room systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

a. Place The Control Room Emergency Filter Unit System In Standby C, D, S (G KO01)
b. Manually Start The Core Spray System (BE005) A, C, D, EN, L, S 2
c. Open The MSlVs With The Reactor Pressurized (>200 Psig) (AB006) C, N, S I d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) (BC009) 1 e. Respond To A Containment Isolation (SM002) I A. C, N, L, S 1 5 11
f. Perform Non-Emergency Operation Of The Diesel Generator (KJ008) 6 I

C, D, S

g. Respond To A Reactor Auxiliary Cooling Malfunction (ED002) A, C, D, P, S 8 (NRC 2005)
h. NA Q

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

i. Conduct Emergency Makeup To The RPV Using Two D, E, R 1 CRD Pumps (BF013)

I j. Perform Torus Makeup Via Core Spray System (BE002)

k. Transfer RPS Bus AIB Power From Alternate Source To A, D RPS MG Set (SB015)

I

@ 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-I 1 SRO-U (A)lternate path (C)ontrol room (D)irect from bank 59/58/54 (E)mergency or abnormal in-plant ~ I I P I I ~ I (EN)gineered safety feature - / - / 21 (control room system)

(L)ow-Power / Shutdown 21/21/21 (N)ew or (M)odified from bank including 1 (A) 22/sz/rI (P)revious 2 exams 5 3 1 5 3 1 5 2 (randomly selected) 21/21/21 (S)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301&

i-Facility: Hope Creek Date of Examination: 2/2/09 Exam Level: RO SRO-I SRO-U Operating Test No.: NRC2009 1 Control Room systemsQ (8 for RO); (7 for SRO-I): (2 or 3 for SRO-U. including 1 ESF) 1 1I System 1 JPM Title

a. Place The Control Room Emergency Filter Unit System In Standby Type Code* Safety I Functiori j 9 '

C, D, S (GK001)

-L I(b. Manually Start The Core Spray System (BE005) 1 A. C, D. EN. L, S 1 2 1 1 c. Open The MSlVs With The Reactor Pressurized (>200 Psig) (AB006) I C, N. S 1 I( d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP) (BC009)

e. Respond To A Containment Isolation (SM002)

I f. Perform Non-Emergency Operation Of The Diesel Generator (KJ008) / C. D, S 1 6 1 I

g. Respond To A Reactor Auxiliary Cooling Malfunction (ED002)

(NRC 2005)

(1 h. Perform Scoop Tube Positioner Lockup Operation (BB002) RO ONLY ( C, D, S  !

1 In-Plant systemsQ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) 1 i. Conduct Emergency Makeup To The RPV Using Two 1 CRD Pumps (BF013) I 1 I I j. Perform Torus Makeup Via Core Spray System (BE002) 1 D, E, R 5 i i

1 k. Transfer RPS Bus A/B Power From Alternate Source To RPS MG Set (SB015)

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 I Criteria for RO I SRO-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank 59/58/54 (E)mergencyor abnormal in-plant 21/21/21 (EN)gineeredsafety feature - / - / 21 (control room system)

(L)ow-PowerI Shutdown 21/21/21 (N)ew or (M)odifiedfrom bank including 1(A) 22/22/21 (P)revious2 exams s 3 / s 3 / 5 2 (randomly selected)

(R)CA 21/21/21 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 1 Op-Test No.: NRC2009 Examiners: J. DIAntonio Operators: (SRO)

6. Fuller (RO)

G. Johnson (BOP)

Initial Conditions:

Plant is operating at 4% power. Startup in progress.

Turnover:

Withdraw Control Rods.

Inert the Containment.

Continue startup.

Event No.

1 Malf.

No.

NIA Event Type*

R (RO)

N (SRO)

Event Description Raise Reactor Power with Control Rods I

2 NIA N (BOP) lnerting the Containment c (RO) 1 3 CD033843 Stuck Control Rod C (SRO) 4 RM9511 I (SRO) Main Steam Line RMS "C" failure (TS) 5 ED09A2 Loss of 1AD482 inverter (TS)

C (SRO 6 MS04 C (ALL) Steam leak in the steam tunnel 7 RR31Al Small break LOCAIRHR pump room flooding M (ALL)

RHO7 (Failure to isolate) 8 ADO1 Emergency Depressurization

- - SRV Failure to open

  • (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.: 2 Op-Test No.: NRC2009 1 Examiners: J. D'Antonio Operators: FRO) 5.Fuller (RO)

G. Johnson Initial Conditions:

Plant is operating at 51% power.

Turnover:

Place D Circ Water Pump in service.

Raise power to 60% by withdrawing control rods and Recirc IAW 10-3 and RE guidance.

Event Malf. Event Type* Event No. No. Description 1 NIA N (BOP) Start D Circ Water Pump.

2 NIA R (RO) Raise power with control rods.

N (SRO) 3 CDl OA c (RO) CRD Pump Trip (TS)

C (SRO) 4 110 1A175 C (BOP) Rx Building Ventilation Supply Damper fails. (TS)

C (SRO) Place FRVS in service 5 TC07A C (ALL) Trip of EHC Pump TC16 EHC Filter Clogging TC07B Manual Scram TCOI -10 Loss of EHCl TBVs fail closed 6 RP07 M (All) ATWS 7 SL04A C (BOP) A SLC Pump Auto Start Failure SLOlB B SLC Pump Trip APPENDIX D, Page 38 of 39

A ~ ~ e n dDix Scenario Outline Form ES-D-1 I Facility: Hope Creek Scenario No.: 3 Op-Test No.: NRC2009 11 Examiners: J. D'Antonio Operators: (SRO)

B. Fuller G. Johnson Initial Conditions: Reactor power is 90%.

Turnover:

I Reduce power from 90% to 84.5% by inserting control rods IAW 10-6 and RE guidance to remove A RFPT from service.

Swap TACS to the B SACS Loop IAW HC.OP-SO.EG-0001.

Event Malf. Event Type* Event No. No. Description 1 NIA R (RO) Reduce power with control rods.

2 NIA N (BOP) Swap TACS to B SACS Loop 3 RZ02A I (SRO) PT-N403A RRCS Pressure Transmitter will fail downscale. (TS) 4 CU03 c (RO) RWCU leak.

CUl l A C (SRO) Automatic isolation valve failure. (TS)

TC02-1 c (RO) EHC logic failure.

TC02-2 TCV's drift closed.

TC02-3 TBVs fail closed.

TC02-4 RZ03A I (ALL) RPS and RRCS High Pressure logic failures.

RZO3C Manual Scram due to rising RPV pressure.

RR31 B1 M (All) LOCA with downcomer failure.

RR31B2 PC04 1 PC03E PCO3G PT-N094EIG will fail to respond to High Drywell Pressur APPENDIX D, Page 38 of 39

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