ML090720629

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Final Outlines (Folder 3)
ML090720629
Person / Time
Site: Hope Creek 
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

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1 D.1.b KAs KIAs KIA D.1.b KIA

  1. I SRO-KIA
IRs, ES-401-3.

KIAs 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 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).

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 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 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 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) in Tiers 1 and 2 shall be selected from Section 2 of the Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section of ES-401 for the applicable KIA's On the following pages, enter the 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 does not apply). Use duplicate pages for RO and only exams.

For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the numbers, descriptions, and point totals (#) on Form Limit SRO selections to that are linked to 10CFR55.43

76 77 80 82 4,

/

/

/

/

/

/

Drywell

/

1 I 8

deterrnine heatup/cooldown rate determine the conclitions Emergency cletermine ir~terpret the AIR Status safety-2.1.23 perform integrated dunng 2.1.7 Condiict rnake

/

they DRYWELL AKI.01 -

C001-ING componenVsystem AKI AKI GRID 3,

4,6 3,3 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 78 79 81 39 40 42 43 295021 Loss o f Shutdown Cooling 4 295023 Refueling Accidents 8

295019 Partial o r Total Loss o f lnst. Air 8 295025 High Reactor Pressure 3 295026 Suppression Pool High Water Temp. 5 295031 Reactor Low Water Level 2 295028 High Temperature 5 295018 Partial or Total Loss of CCW 18 295006 SCRAM 295001 Partial or Complete Loss of Forced Core Flow Circulation 11 4

700000 Generator Voltage and Electric Grid Disturbances 295030 Low Suppression Pool Water Level 15 X

X X

X X

X X

X X

X AA2.01 - Ability to and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING :

Reactor water AA2.05 Ability to and/or interpret following as they apply to REFUELING ACCIDENTS : Entry of plan AA2.02 Ability to and/or following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT of related instrument air system loads

- Conduct of Operations: Ability to specrfic system and plant procedures all modes of operation.

of Operations: Ability to evaluate plant performance and operational judgments based on operating characterrsbcs, reactor behavior, and instrument interpretation.

2.4.3 - Emergency Procedures Plan:

Ability to identify post-accident instrumentation EA2.03-Ability to determine and/or interpret the following as apply to HIGH TEMPERATURE :

Reactor water level Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT WATER : Effects on operations

.03 - Knowledge of the operational implications of the following concepts as they apply to SCRAM : Reactivity control

.02 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : Powerlflow distribution AK2.02 Knowledge of the interrelations between GENERATOR VOLTAGE AND ELECTRIC DISTURBANCES and the following:

Breakers, relays.

EK2.02 - Knowledge of the interrelations between LOW SUPPRESSION POOL WATER LEVEL and the following: RCIC: Plant-Specific 3.7 4.4 4.7 3.9 3.9 3.5 3.7 3.1 3.7

45 46 47 48 51 52 53 5q 57 3,7 3,6 4,2 3.5 3,1 4,,

3,7 1 I I 5 12 Inst.

I I 9 1 3 TripIRunback HIGH HIGH RCIC EK3.05 -

andlor EAI andlor HIGH andior and/or MAIN TRIP andlor

/

DRYWELL Drywell Mark-l&ll 1

1 4 Drywell 15 1

Drywell 15 18 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 44 49 50 55 56 58 3.1 3.0 3.7 4.6 4.2 3.0 X

X 295004 Partial or Total Loss of DC Pwr 1 6 295023 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown 295026 Suppression Pool High Water Temp.

295025 High Reactor Pressure 13 295031 Reactor Low Water Level 295019 Partial or Total Loss of Air 8 295038 High Off-site Release Rate 295003 Partial or Complete Loss of AC 1 6 295005 Main Turbine Generator Trip AK2.01 - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following: Battery charger AK3.01 - Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Recirc Pump EK3.04 - Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL WATER TEMPERATURE: SBLC injection EK3.05 - Knowledge of the reasons for the following responses as they apply to REACTOR PRESSURE :

operation: Plant-Specific Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL:

Emergency depressurization AA1.03 - Ability to operate monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : Instrument air compressor power supplies

.03 - Ability to operate monitor the following as they apply to OFF-SITE RELEASE RATE:

Process liquid radiation monitoring system AA2.04 - Ability to determine interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER : System lineups AA2.03 - Ability to determine interpret the following as they apply to TURBINE GENERATOR EA2.02 -Ability to determine X

X X

X X

interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

Reactor water level 2.1.28 - Conduct of Operations:

Knowledge of the purpose and function of major system components and controls.

2.4.1 - Emergency Procedures IPlan:

Knowledge of EOP entry conditions and immediate action steps.

2.4.46 - Emergency Procedures Plan:

Ability to verify that the alarms are consistent with the plant conditions.

EK2.01 Knowledge of the interrelations between HlGH TEMPERATURE and the following:

spray:

AA1.06 - Ability to operate and I or X

X X

X 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown 1 295021 Loss of Shutdown Cooling 295024 High Pressure 295016 Control Room Abandonment 7 295028 High Temperature 600000 Plant Fire On-site X

X X

KIA 313 FIRE 2017 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 ON SITE: Fire Alarm 4

Category Totals:

3 4

3 314 Group Point Total:

/

Offsite

/

/

Drywell 1

I Drywell I 5 1

112 117 O f -

cfetermine and/or rnferprct lhe followrng as kfI(;H Radiatton

/Plan-statirs ir?tegrity,

/

operation/statos tl-~nt niusl rnternal the triir,srr?rss!orl AKI HIGH DRYWELL Mark-18.11 HIGH EAI andlor HIGH

,442.02 andlor HIGH DRYWELL Drywell HIGH 60 3,4 62 3,9 63 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 295033 High Secondary Containment Area Radiation Levels 9 295017 High Release Rate 9 295015 Incomplete SCRAM 1 X

1 X

1 X

X 2

X 1

X X

X M 2.

Ability to they apply to SECONDARY CONTAINMENT 3.9 83 AREA RADIATION LEVELS. Area levels 2.4.21 Emergency Procedures Knowledge of the parameters and logrc used to assess the of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system containment conditions, radioactivity release control, etc.

2.4.30 - Emergency Procedures Plan:

Knowledge of evenls related to system be reported to organizations or external agencies, such as State, the NRC, or system operator

.O1 Knowledge of the operational implications of the following concepts as they apply to PRESSURE : Downcomer submergence:

AK2.03 - Knowledge of the interrelations between LOSS OF CRD PUMPS the following: Accumulator pressure EK3.02 - Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT AREA TEMPERATURE : Reactor SCRAM

.O1 - Ability to operate monitor the following as they apply to SUPPRESSION POOL WATER LEVEL : HPCI: Plant-Specific

- Ability to determine interpret the following as they apply to TEMPERATURE :

pressure 2.1.20 - Conduct of Operations: Ability to interpret and execute procedure steps.

AK3.02 - Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL TEMPERATURE : Limiting heat additions Group Point Total:

84 3.0 3.4 3.6 4.6 3.6 295010 High Pressure 5 295022 Loss of CRD Pumps 295032 High Secondary Containment Area Temperature 5 295029 High Suppression Pool Water Level 1 5 295012 High Temperature 295009 Low Reactor Water Level 2 295013 High Suppression Pool Temperature 1 5 WA Category Totals:

85 59 61 64 65 713

HPCl SRVs RClC HPCl Equipn~ent determine availabil~ty 2.2.40 to

/Plan.

lecognize manner cor~trol room r-nater~al lirnitrng lilnits.

impacts the (b) tk~e abnormal inop and/or andlor channelsldetectors HIGH BWR-2.3,4 3'5 3,4 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 206000 X

2 2.37 -

Control:

Ability to operability and/or of safety related equipment.

4 6 86 209001 LPCS X

- Ability apply Technical Specifications for a system.

4.7 87 21 1000 SLC 2.4.4 7 - Emergency Procedures Ability to diagnose and trends in an accurafe and firnely utilizing the appropriate reference 4 2 88 205000 Shutdown Cooling X

2.2.22 Equipment Control:

Knowledge of conditions for operations and safety 4.7 89 275004 Source Range Monitor X

A2.02 Ability to (a) predict the of following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and based on those predictions, use procedures to correct, control, or mitigate consequences of those conditions or operations: SRM condition 3.7 90 205000 Shutdown Cooling X

K1.04 - Knowledge of the physical connections cause-effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: Fuel pool cooling assist: Plant-Specific 2.7 1

21 8000 ADS X

K1.02 - Knowledge of the physical connections cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: Low Pressure Core Spray 4.0 2

215004 Source Range Monitor X

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

SRM 2.6 3

239002 X

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

SRV solenoids 2.8 4

217000 X

K3.03 - Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will have on following: Decay Heat removal 206000 X

K3.03 - Knowledge of the effect that a loss or malfunction of the PRESSURE COOLANT INJECTION SYSTEM will have on following: Suppression pool level control:

EDGs IRM 1000 feature(s) feature(s) and/or K6.05 and/or RHRILPCI:

andlor LIQUID 3,4 3.3 4,2 13 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 300000 Instrument Air X

K4.02 - Knowledge of (INSTRUMENT AIR SYSTEM) design and or interlocks which provide for the following: Cross-over to other air systems 3.0 7

262001 AC Electrical Distribution X

K4.05 - Knowledge of A.C.

ELECTRICAL DISTRIBUTION design interlocks which provide for the following: Paralleling of A.C.

sources 3.4 8

264000 X

K5.06 - Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET) :

Load Sequencing 212000 RPS X

K5.02 - Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM : Specific logic arrangements 263000 DC Electrical Distribution X

K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the D.C.

ELECTRICAL DISTRIBUTION :

A.C. electrical distribution 3.2 11 21 5003 X

- Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM : Trip units 3.1 12 203000 RHRILPCI:

Injection Mode X

A1.O1 - Ability to predict monitor changes in parameters associated with operating the INJECTION MODE (PLANT SPECIFIC) controls including: Reactor water level 261 000 SGTS X

A1.04 - Ability to predict monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including:

Secondary containment differential pressure 3.0 14 21 SLC X

A2.04 Ability to (a) predict the impacts of the following on the STANDBY CONTROL SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow 3.1 15

PClSlNuclear SRVs RHRILPCI:

WA 3

2 2

3 3

2 2

1 1

1 3'0 2,8 andlor SYSTEMINUCLEAR A3.01 UNINTERRUPTABLE (A.C.1D.C.)

and/or andlor I

and/or feature(s) and/or l6 17 3.1 3'9 25 26 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 223002 Steam Supply Shutoff 262002 UPS (ACIDC) 209001 LPCS 21 5005 APRM I LPRM 400000 Component Cooling Water 21 8000 ADS 239002 203000 Injection Mode 209001 LPCS X

X X

X X

X X

X 3.5 3.2 3.1 3.2 4.2 4.1 3.3 K1.03 - Knowledge of the physical connections cause effect relationships between PRIMARY CONTAINMENT ISOLATION STEAM SUPPLY SHUT-OFF and the following: Plant ventilation

- Ability to monitor automatic operations of the POWER SUPPLY including:

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

System pressure A4.03 -Ability to manually operate monitor in the control room: APRM back panel switches, meters and indicating lights A4.01 - Ability to manually operate monitor in the control room: CCW indications and control 2.2.25 - Equipment Control:

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

2.4.31 - Emergency Procedures Plan: Knowledge of annunciator alarms, indications.

or response procedures.

A4.02 - Ability to manually operate monitor in the control room: System valves K4.09 Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design interlocks which provide for the following: Load Sequencing 18 19 20 21 22 23 24 259002 Reactor Water Level Control 261000 SGTS Category Totals:

X X

3 3 2 1 4 operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM :Water level measurement A3.02 Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including: Fan start K5.03-Knowledge of the Group Point Total:

2615

l TIPS RHfULPCI:

RPlS

- Abil~ty those or mitigate abnormal or 011

/Plan. Ab111ty perform witlioc~t that

~mmediate pred~ct irnpacts

[nibgate abnornial operatior~s:

acoderit conditiorts K1 andlor RHRILPCI:

feature(s)

MAIN 3,0 30 Form ES-401-1 Hope Creek Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 245000 Main Turbine Gen.

Aux.

202001 Recirculation 215001 201003 Control Rod and Drive Mechanism 226001 CTMT Spray Mode 234000 Fuel Handling Equipment 214000 245000 Main Turbine Generator and Auxiliary Systems A2.02 to (a) predicf the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS ;

and (b)based on predictions, use procedures to correct,

control, the consequences of those conditions operations. Loss of lube 2.4.49 Emergency Procedures to reference to procedures those actions require operation of system coniponents arid confrols.

A2.07 Ability to (a) the of the following on ttie TIPS; and (b) based on those predictions, use procedures to correct, control. or the consequences of those conditions or Failure to refract during

.O1 - Knowledge of the physical connections cause-effect relationships between CONTROL ROD AND DRIVE MECHANISM and the following: CRD Hydraulic system A3.01 Ability to monitor automatic operations of the CONTAINMENT SPRAY SYSTEM MODE including: Valve operation K3.03 - Knowledge of the effect that a loss or malfunction of the FUEL HANDLING EQUIPMENT will have on following: Fuel handling operations K4.01 Knowledge of (ROD POSITION INFORMATION SYSTEM) design and or interlocks which provide for the following: Reed switch locations K5.07-Knowledge of the operational implications of the following concepts as they apply to TURBINE GENERATOR AND AUXILIARIES SYTEMS:

Generator operations and limitations X

3.5 4.4 3.7 3.2 3.0 3.1 2.6 X

91 92 93 27 28 29 31 X

X X

X

ReactorlTurbine KIA

. I 0 andlor MAIN SYSTEM BWR-3,4,5 andlor stoplthrottle andlor 3,5 36 2,7 38 1213 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

- Ability to predict 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 AND REHEAT STEAM SYSTEM and (b) based on 239001 Main and Reheat Steam X

those predictions, use procedures to correct, control, 4.2 34 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 including: Four rod display:

A4.07 - Ability to manually 241000 Pressure Regulator X

operate monitor in the control room: Main valves (operation) 2.2.39 - Equipment Control:

223001 Primary CTMT and Aux.

Knowledge of less than or equal to one hour Technical 3.4 37 Specifications for a system A1.06 - Ability to predict monitor changes in parameters 259001 Reactor Feedwater X

associated with operating the REACTOR FEEDWATER SYSTEM controls including:

Feedwater heater level Category Totals:

1 0

1 1

1 1

2 1

1 2

2 1

111 Group Point Total:

K/A1s IR 2'

2.7.35 2.1.3 2.1-4 2'1.30 Q#

IR SROs I

"no-(

10CFR55, Q#

I00 2'2'18 2'2'6 2'2'13 condi~cting requirer??ents, ES-401 Record of Rejected Form ES-401-4 Facility:

Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control Hope Creek Written Exam Date:

KIA Topic Knowledge of primary and secondary plant chemistry limits.

Knowledge of fuel-handling responsibilities of Knowledge of shift or short-term relief turnover practices Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, solo" operation, maintenance of active license status, etc.

Ability to locate and operate components, including local controls.

Subtotal Knowledge of the process for 2.2.7 special or infrequent tests.

Knowledge of the process for managing maintenance activities during shutdown operations. such as risk assessments. work prioritization, etc.

Knowledge of the process for making changes to procedures 2.2.12 Knowledge of surveillance procedures Knowledge of tagging an clearance procedures Subtotal Knowledge of Radiological Safety Principles pertaining to licensed operator duties such as containment entry fuel handling responsibilities, access to high radiation areas, aligning filters, etc.

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

RO SRO-Only 3.5 3.9 3.6 3.9 3.7 3.7 3.3 4.4 3.0 3.7 4.1 3.2 71 67 66 3

68 69 74 3

70 94 2

95 96 2

99

WA's 1

2'3'13 3.3 73 10

/

2.4.40 2'4m18 2m4'43 plan EOPs.

DW 0

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

3.4 75 Subtotal 2

4.

Emergency Procedures Plan 2.4.6 Knowledge of EOP mitigation strategies.

4.7 97 Knowledge of SRO responsibilities in emergency implementation 4.5 98 Knowledge of the specific bases for (terminating spray at psig)

Knowledge of emergency communications systems and techniques.

3.2 72 Subtotal 2

2 Tier 3 Point Total 7

WA's

  1. 8
  1. 30)

ES-401 Record of Rejected Form ES-401-4

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

WA's 1

and/or HlGH Drywell APRMs

.21 determine and/or HlGH DRYWELL Drywell

(#21)

(#45)

(#29, #94).

(#58)

AAI

(#28)

(#60)

SAGS

(#26)

  1. 19).

(#67)

& #69).

(#74) 2.2.1

(#83)

Record of Rejected Form ES-401-4 Ability to operate plant equipment in the event of low RPV level is tested frequently in the operating exam.

Randomly selected EK3.05 Refueling topic is oversampled Randomly selected 295037 K3.01 Ability to operate monitor the following as they apply to REACTOR LOW WATER LEVEL Feedwater Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS : Interlocks associated with fuel handling equipment Guidance is contained in for this event. Could not write an operational valid question for this topic at the RO level. Randomly selected 295022 AK2.03 600000 12.2.38 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

This is an SRO function at HC. Randomly selected

.06 Knowledge of electrical power supplies to the 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 CONTAINMENT HYDROGEN CONCENTRATIONS the following:

nitrogen purge system

- Ability to use plant computers to System (Nls)

Topic oversampled (see evaluate system or Randomly selected 261 000 A3.02 component status.

2.1

- Ability to verify the controlled Topic oversampled (see #68 Randomly procedure copy.

selected 2.1.4 2.2.43 - Knowledge of the process to track Could not write a discriminating question for the inoperable alarms topic. Randomly selected 3

Ability to interpret the following as they apply Same WA as # 63. Randomly selected 295033 to EA2.01 TEMPERATURE :

Pressure

WA's

(#84) 1 the AUTOMA DEPRESSUR17A TION besed tttose

(#90) mifrgate those D.

(#93)

ES-401 Record of Rejected Form ES-401-4 Topic did not lend itself to a discriminating SRO level question. Randomly selected 295017 218000 A2.05 Ability to (a) predict the impacts of the following on TIC SYSTEM and (b) on Double jeopardy with #4. Randomly selected 215004 control, or the consequences of abnormal conditions or operations: Loss of A C.

or C power to ADS Does not apply at HC. Randomly selected 21 5001

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

I (D)irect (s

ROs; s SROs &

(N)ew (M)odified (21)

(P)revious

(<I; (A)lternate HC ILT 2009 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Hope Creek Date of Examination:

from bank 3 for 4 for RO retakes) or from bank 2 exams randomly selected)

Path RO: 3.1 SRO: 4.6 Equipment Control Radiation Control Emergency Plan

1 2/2/09 Exarr~ination minimum 22009 Administrative

( Type 1

Note)

. I I

1 1

0 1

I 1

22032 D, R N7 I

ECGOOG 4T1 ST.ZZ-0001 Inoperable SROs. RO

!I admin~strative (C)ontrol (S)imulator, Class(R)oom (D)irect (I

ROs; 5 (N)ew (M)odified (21)

(P)revious (51 ;

(A)lternate HC ILT 2009 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Hope Creek Date of Examination:

Level:

RO SRO Operating Test Number:

NRC 2009 Describe activity to be performed (See Code*

2.1.5 Ability to use procedures related to shift staffing, such as crew complement, overtime limitations, etc.

Conduct of Operations RO: 2.9 SRO: 3.9 Ensure Shift is Adequately Manned (RO will exceed guidelines. Requires Authorization Form) 2.1 8 Ability to make accurate, clear and concise logs, records, status boards, and reports.

RO: 3.9 SRO: 4.0 22017 Initiate the Daily Surveillance Log (Shiftly Routine. Due to Plant Conditions, three optional attachments are required) 2.2.1 2 Knowledge of surveillance procedures RO: 3.7 SRO:

Equipment Control Authorize the Start of a Surveillance Test Conduct of Operations (One Hour for EDG) 2.3.11 Ability to control radiation releases RO: 3.8 SRO: 4.3 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 Emergency Plan emergency coordinator if required RO: 2.4 SRO: 4.4 Classify Loss of All Barriers Determine PAR NOTE: All items (5 total) are required for applicants require only 4 items unless they are retaking only the topics, when 5 are required.

  • Type Codes Criteria:
Room, or from bank 3 for 4 for SROs RO retakes) or from bank 2 exams randomly selected)

Path

ES-301. lb (XJ NRC2009 systems@

1 1

1 (BE005)

I A, C, D, EN. rl 2-(

(BC009) systems@

(SM002)

(BF013)

A, C, N, L, S A/B (SB015)

C (A)lternate (C)ontrol (D)irect (E)mergency (EN)gineered (L)ow-Power I (N)ew (M)odified 1(A)

(P)revious (S)imulator I

s 9 1 5 8 1 5 4 2 1 1 2 1 1 2 1 1

1 2 l l ~ l l r l 2 2 1 r 2 1 r I 5 15 1 5 2 1 1 ~ 1 1 2 1 ES-301 Control Roomlln-Plant Svstems Outline Form Facility: Hope Creek Date of Examination: 2/2/09 Exam Level: RO SRO-I SRO-U Operating Test No.:

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

System JPM Title Type Code*

Safety Function

b. Manually Start The Core Spray System
d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP)

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

I

e. Respond To A Containment Isolation
i. Conduct Emergency Makeup To The RPV Using Two CRD Pumps
k. Transfer RPS Bus Power From Alternate Source To RPS MG Set 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 tested in the control room.
  • Type Codes path room from bank or abnormal in-plant safety feature Shutdown or from bank including 2 exams Criteria for RO SRO-I I SRO-U 4-6 14-6 12-3 21 (control room system) 3 3

2 (randomly selected)

I ES-~O<&

Hope NRC2009

/

C, D, S KO0 (BE005)

MSlVs

(>200 (AB006)

II (BC009) 11 (SM002)

I A. C, N, L, S 1

5 1 11 I

(BE002)

(KJ008)

(ED002)

I 1

I A, C, D, P, S AIB (SB015)

(A)lternate (C)ontrol (D)irect (E)mergency (EN)gineered (L)ow-Power /

(N)ew (M)odified (P)revious (S)imulator I

A, D 5 9 / 5 8 / 5 4

~ I I P I I ~ I

/

/ 21 2 2 / s z / r 5

1 5 (BF013)

D, E, R I

ES-301 Control Roomlln-Plant Svstems Outline Form Facility:

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

Control Room systems Q (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 (G
1)

A, C, D, EN, L, S 2

b. Manually Start The Core Spray System
c. Open The With The Reactor Pressurized Psig)

C, N, S

d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP)
e. Respond To A Containment Isolation
f. Perform Non-Emergency Operation Of The Diesel Generator C, D, S 6
g. Respond To A Reactor Auxiliary Cooling Malfunction (NRC 2005) 8
h. NA In-Plant systems Q (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Conduct Emergency Makeup To The RPV Using Two CRD Pumps 1
j. Perform Torus Makeup Via Core Spray System k.Transfer RPS Bus Power From Alternate Source To RPS MG Set 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 SRO-I SRO-U path room from bank or abnormal in-plant safety feature (control room system)

Shutdown 2 1 / 2 1 / 2 1 or from bank including 1(A)

I 2 exams 3 1 5 3 2 (randomly selected) 2 1 / 2 1 / 2 1

Roomlln-Plant ES-301&

i-NRC2009 11 systemsQ I1 1

I(

(BE005) 1 I

j (GK001) 1 D.

1 1

11 MSlVs

(>200 (AB006)

I N.

1 C, D, S I

(BC009) 9 L

(

(SM002)

I (KJ008)

/ C.

I 1

6 1

(ED002)

(1 (BB002)

(

11 systemsQ 11 11 (BF013)

I 1

I 11 A/B I

1 (SB015)

(BE002)

I I

(A)lternate (C)ontrol (D)irect (E)mergency (EN)gineered (L)ow-Power I (N)ew (M)odified 1(A)

(P)revious (R)CA (S)imulator D, E, R 5 9 / 5 8 / 5 4

/

/

s

/ s

/ 5 5

i ES-301 Control Systems Outline Form Facility: Hope Creek Exam Level: RO SRO-I SRO-U Date of Examination: 2/2/09 Operating Test No.:

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

System JPM Title Type Code*

b. Manually Start The Core Spray System Safety Functiori
a. Place The Control Room Emergency Filter Unit System In Standby A. C, EN. L, S 2
c. Open The With The Reactor Pressurized Psig)

C, S

d. Place B RHR Loop In Suppression Pool Cooling From The Remote Shutdown Panel (RSP)
e. Respond To A Containment Isolation
h. Perform Scoop Tube Positioner Lockup Operation RO ONLY C, D, S
f. Perform Non-Emergency Operation Of The Diesel Generator D, S
g. Respond To A Reactor Auxiliary Cooling Malfunction (NRC 2005)

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

i. Conduct Emergency Makeup To The RPV Using Two CRD Pumps
k. Transfer RPS Bus Power From Alternate Source To RPS MG Set 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.
j. Perform Torus Makeup Via Core Spray System
  • Type Codes I

Criteria for RO SRO-I SRO-U path room from bank or abnormal in-plant safety feature Shutdown or from bank including 2 exams 2 1 / 2 1 / 2 1 21 (control room system) 2 1 / 2 1 / 2 1 2 2 / 2 2 / 2 1 3

3 2 (randomly selected) 2 1 / 2 1 / 2 1 i

1 NRC2009 DIAntonio

6.

(SRO)

(RO)

(BOP)

Inert 1

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NIA NIA CD033843 RM9511 ED09A2 RR31Al RHO7 ADO1 R (RO) c (RO)

C C

C 1AD482 LOCAIRHR Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.:

Op-Test No.:

Examiners:

J.

Operators:

Fuller G. Johnson Initial Conditions:

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

Turnover:

Withdraw Control Rods.

the Containment.

Continue startup.

Event No.

Malf.

No.

Event Type*

Event Description I

1 N (SRO)

Raise Reactor Power with Control Rods 2

N (BOP) lnerting the Containment 3

(SRO)

Stuck Control Rod 4

I (SRO)

Main Steam Line RMS "C" failure (TS) 5 (SRO Loss of inverter (TS) 6 MS04 (ALL)

Steam leak in the steam tunnel 7

M (ALL)

Small break pump room flooding (Failure to isolate) 8 --

Emergency Depressurization SRV Failure to open APPENDIX D, Page 38 of 39

2 NRC2009 1

D'Antonio

5.

FRO)

(RO)

R (RO)

NIA NIA CDl 110 1A175 TC07A TC07B TCOI SL04A SLOl c (RO)

C C

C C

Rx EHCl TBVs Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.:

Op-Test No.:

Examiners:

J.

Fuller G. Johnson Initial Conditions:

Plant is operating at 51% power.

Operators:

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 No.

1 2

3 Event Type*

N (BOP)

Malf.

No.

4 5

6 7

Event Description Start D Circ Water Pump.

Raise power with control rods.

OA TC16

-1 0 RP07 B

N (SRO)

CRD Pump Trip (TS)

(SRO)

C (BOP)

(SRO)

(ALL)

M (All)

(BOP)

Building Ventilation Supply Damper fails. (TS)

Place FRVS in service Trip of EHC Pump EHC Filter Clogging Manual Scram Loss of fail closed ATWS A SLC Pump Auto Start Failure B SLC Pump Trip APPENDIX D, Page 38 of 39

A ~ ~ e n d i x I

NRC2009 11 D'Antonio (SRO)

HC.OP-SO.EG-0001.

NIA RZ02A CUl l A RZ03A RZO3C B1 RR31B2 R (RO) c (RO)

PC03E 1

PCO3G c (RO)

C TCV's TBVs PT-N094EIG Drywell PT-N403A D

Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 3 Op-Test No.:

Examiners:

J.

Operators:

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

I I Turnover:

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 Event Description Reduce power with control rods.

Event No.

1 2

3 4

TC02-1 TC02-2 TC02-3 TC02-4 Malf.

No.

NIA CU03 RR31 PC04 Event Type*

N (BOP)

I (SRO)

(SRO)

EHC logic failure.

drift closed.

fail closed.

I (ALL)

M (All) will fail to respond to High Pressur Swap TACS to B SACS Loop RRCS Pressure Transmitter will fail downscale. (TS)

RWCU leak.

Automatic isolation valve failure. (TS)

RPS and RRCS High Pressure logic failures.

Manual Scram due to rising RPV pressure.

LOCA with downcomer failure.

APPENDIX D, Page 38 of 39

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