ML13267A380

Final Outlines (Folder 3)

ML13267A380
Person / Time
Site:	Hope Creek
Issue date:	08/19/2013
From:	Todd Fish Operations Branch I
To:	Public Service Enterprise Group
Jackson D
Shared Package
ML13077A118	List: IR 05000354/2013301 ML13108A195 ML13227A102 ML13227A107 ML13227A117 ML13227A127 ML13227A207 ML13267A380 ML13267A389 ML13267A415 ML13267A422 ML14010A064 ML14070A491 ML14070A492
References
TAC U01872
Download: ML13267A380 (21)

Text

ES-401 BWR Examination Outline Form ES-401-1 Facility: Hope Creek Date of Exam: August 19. 2013 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 2 5 3 2 5 3 20 3 4 7 Emergency &

Abnormal Plant 2 2 1 1 N/A 1 1 N/A 1 7 2 1 3 Evolutions Tier Totals 4 6 4 3 6 4 27 5 5 10 1 4 2 3 2 3 2 2 2 3 2 1 26 2 3 5 2.

Plant 2 0 0 1 2 1 1 3 0 1 2 1 12 1 2 3 Systems Tier Totals 4 2 4 4 4 3 5 2 4 4 2 38 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 2 3 2 2 1 2 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).

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 KIAs 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) 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 KIAs.

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 KIAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions- Tier 1/Group 1 (RO I SRO)

E/APE #I Name I Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 2.4.31 Knowledge of annunciator alarms, 295003 Partial of Complete Loss of AC /6 X indications, or response procedures. 4.1 76 2.4.47 Ability to diagnose and recognize trends in an 295006 SCRAM /1 X accurate and timely manner utilizing the appropriate 4.2 77 control room reference material.

2.2.40 Ability to apply Technical Specifications for a 295018 Partial or Total Loss of CCW /8 X system. 4.7 78 2.4.30 Knowledge of events related to system 295001 Partial or Complete Loss of Forced X operation/status that must be reported to internal 4.1 79 Core Flow Circulation I 1 & 4 organizations or external agencies, such as the State, the NRC, or the transmission system operator.

Ability to determine and/or interpret the following as 295026 Suppression Pool High Water X they apply to SUPPRESSION POOL HIGH WATER 4.2 80 Temp./5 TEMPERATURE: EA2.01 Suppression pool temperature Ability to determine and/or interpret the following as 295031 Reactor Low Water Level/ 2 X they apply to REACTOR LOW WATER LEVEL: 4.6 81 EA2.04 Adequate Core Cooling Ability to determine and/or interpret the following as 700000 Generator Voltage and Electric Grid X they apply to GENERATOR VOLTAGE AND 4.0 82 Disturbances I 6 ELECTRIC GRID DISTURBANCES: AA2.07 Operational status of enqineered safety features Ability to determine and/or interpret the following as 295001 Partial or Complete Loss of Forced X they apply to PARTIAL OR COMPLETE LOSS OF 3.3 1 Core Flow Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION AA2.03 Actual Core Flow Ability to determine and/or interpret the following as 295003 Partial or Complete Loss of AC I 6 X they apply to PARTIAL OR COMPLETE LOSS OF 3.9 2 A. C. POWER AA2.05 Whether a partial or complete loss of A. C. Power has occurred Knowledge of the interrelations between PARTIAL 295004 Partial or Total Loss of DC Pwr /6 X OR COMPLETE LOSS OF D.C. POWER and the 3.3 3 following AK2.03DC Bus Loads Knowledge of the operational implications of the 295005 Main Turbine Generator Trip I 3 X following concepts as they apply to MAIN TURBINE 4.0 4 GENERATOR TRIP AK1.01 Pressure effects on reactor power 2.4.20 Knowledge of the operational implications of 295006 SCRAM I 1 X EOP warninqs, cautions,and notes. 3.8 5 Knowledge of the interrelations between CONTROL 295016 Control Room Abandonment I 7 X ROOM ABANDONMENT and the following AK2.02 4.0 6 Local control stations: Plant-Specific Knowledge of the interrelations between PARTIAL 295018 Partial or Total Loss of CCW I 8 X OR COMPLETE LOSS OF COMPONENT 3.4 7 COOLING WATER and the Following AK2.02 Plant operations Ability to operate and/or monitor the following as 295019 Partial or Total Loss of Ins!. Air I 8 X they apply to PARTIAL OR COMPLETE LOSS OF 3.0 8 INSTRUMENT AIR AA1.03 Instrument Air Compressor power supplies Ability to determine and/or interpret the following as 295021 Loss of Shutdown Cooling I 4 X they apply to LOSS OF SHUTDOWN COOLING 3.5 9 AA2.01 Reactor water heatup/cooldown rate Knowledge of the reasons for the following 295023 Refueling Ace I 8 X responses as they apply to REFUELING 3.6 10 ACCIDENTS AK3.01 Refueling floor evacuation

Ability to determine and/or interpret the following as 295024 High Drywell Pressure I 5 X they apply to HIGH DRYWELL PRESSURE EA2.05 3.6 11 Suppression chamber air-space temperature: Plant-Specific 2.1.28 Knowledge of the purpose and function of 295025 High Reactor Pressure I 3 X major system components and I 4.1 12 controls.

Ability to operate and/or monitor the following as 295026 Suppression Pool High Water X they apply to SUPPRESSION POOL HIGH WATER 3.9 13 Temp./5 TEMPERATURE EA1.03 Temperature monitoring 295027 High Containment Temperature I 5 Suppressed, no Mklll containment at HC. N/A Knowledge of the operational implications of the 295028 High Drywell Temperature /5 X following concepts as they apply to HIGH 3.5 14 DRYWELL TEMPERATURE EK1.01 Reactor water level measurement 2.4.11 Knowledge of abnormal condition 295030 Low Suppression Pool Wtr Lvl/ 5 X procedures. 4.0 15 Ability to determine and/or interpret the following 295031 Reactor Low Water Level I 2 X as they apply to REACTOR LOW WATER LEVEL 4.6 16 EA2.04 Adequate Core Cooling Knowledge of the interrelations between SCRAM 295037 SCRAM Condition Present X CONDITION PRESENT AND REACTOR POWER 4.0 17 and Reactor Power Above APRM ABOVE APRM DOWNSCALE OR UNKNOWN and Downscale or Unknown I 1 the following EK2.02 RRCS: Plant-Specific Knowledge of the reasons for the following 295038 High Off-site Release Rate I 9 X responses as they apply to HIGH OFF-SITE 3.9 18 RELEASE RATE EK3.02 System Isolations Knowledge of the reasons for the following 600000 Plant Fire On Site I 8 X responses as they apply to PLANT FIRE ON SITE: 2.8 19 AK3.04 Actions contained in the abnormal procedure for plant fire on site Knowledge of the interrelations between 700000 Generator Voltage and Electric Grid X GENERATOR VOLTAGE AND ELECTRIC GRID 3.1 20 Disturbances I 6 DISTURBANCES and the following AK2.02 Breakers, relays KIA Category Totals: 2 5 3 2 5 3 Group Point Total: 201 I I 7 3 4

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1/Group 2 (RO I SRO)

E/APE #I Name I Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 2.4.6 Knowledge of EOP Mitigation Strategies.

295009 Low Reactor Water Level I 2 X 4.7 83 Ability to determine and/or interpret the following as 295022 Loss of CRD Pumps I 1 X they apply to LOSS OF CRD PUMPS AA2.02 CRD 3.3 84 system status Ability to determine and/or interpret the following as 295029 High Suppression Pool Wtr Lvl I 5 X they apply to HIGH SUPPRESSION POOL WATER 3.9 85 LEVEL EA2.01 Suppression pool water level Ability to operate and/or monitor the following as 295010 High Drywell Pressure I 5 X they apply to HIGH DRYWELL PRESSURE AA1.02 3.6 21 Drywell floor and equipment drain sumps Knowledge of the operational implications of the 295017 High Off-Site Release Rate I 9 X following concepts as they apply to HIGH OFF-SITE 3.8 22 RELEASE RATE AK1.02 Protection of the general public 295011 High Containment Temp I 5 Suppressed, no Mklll containment at HC. N/A Knowledge of the interrelations between 295020 Inadvertent Cont. Isolation I 5 & 7 X INADVERTENT CONTAINMENT ISOLATION and the 3.6 23 followinq AK2.01 Main steam system.

Knowledge of the reasons for the following responses 295029 High Suppression Pool Wtr Lvl I 5 X as they apply to HIGH SUPPRESSION POOL WATER 3.6 24 LEVEL EK3.02 Lowering suppression pool water level Ability to determine and/or interpret the following as 295032 High Secondary Containment Area X they apply to HIGH SECONDARY CONTAINMENT 3.8 25 Temperature I 5 AREA TEMPERATURE EA2.01 Area temperature 2.2.44 Ability to interpret control room indications to 295035 Secondary Containment High X verify the status and operation of a system, and 4.2 26 Differential Pressure I 5 understand how operator actions and directives affect plant and system conditions.

Knowledge of the operational implications of the 500000 High CTMT Hydrogen Cone. I 5 X following concepts as they apply to HIGH 3.3 27 CONTAINMENT HYDROGEN CONCENTRATIONS EK1.01 Containment integrity KIA Category Point Totals: 2 1 1 1 1 1 Group Point Total: 7/3 I I 2 1

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier 2/Group 1 (RO I SRO)

System #I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to (a) predict the impacts of the 203000 RHRILPCI: Injection X following on the RHR/LPCI: INJECTION 3.4 86 Mode MODE (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.11 Motor operated valve failures Ability to (a) predict the impacts of the 206000 HPCI X following on the HIGH PRESSURE 3.4 87 COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations A2.14 Flow controller failure:

BWR-2,3,4 2.2.25 Knowledge of the bases in Technical 215004 Source Range Monitor X Specifications for limiting conditions for 4.2 88 operations and safety limits.

2.4.18 Knowledge of the specific bases for 218000ADS X EOPs. 4.0 89 2.4.9 Knowledge of low power/shutdown 264000 EDGs X implications in accident (e.g., loss of coolant 4.2 90 accident or loss of residual heat removal) mitigation strategies.

Ability to manually operate and/or monitor in 203000 RHR/LPCI: Injection X the control room A4.01 Pumps 4.3 28 Mode Ability to (a) predict the impacts of the 205000 Shutdown Cooling X following on the SHUTDOWN COOLING 3.5 29 SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations A2.05 System Isolation Knowledge of the operational implications of 206000 HPCI X the following concepts as they apply to HIGH 3.3 30 PRESSURE COOLANT INJECTION SYSTEM K5.01 Turbine operation: BWR-2,3,4 Suppressed, system does not exist at HC.

207000 Isolation (Emergency) N/A Condenser Knowledge of LOW PRESSURE CORE 209001 LPCS X SPRAY SYSTEM design feature(s) and/or 3.2 31 interlocks which provide for the following K4.01 Prevention of over pressurization of core spray piping.

209002 HPCS Suppressed, system does not exist at HC. N/A Ability to predict and/or monitor changes in 211000SLC X parameters associated with operating the 3.6 32 STANDBY LIQUID CONTROL SYSTEM controls including A1.01 Tank Level Knowledge of the physical connections and/or 212000 RPS X cause effect relationships between 3.6 33 REACTOR PROTECTION SYSTEM and the following K1.14 Main Steam system

Knowledge of the physical connections and/or 215003 IRM X cause effect relationships between 3.6 34 INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM and the following K1.02 Reactor manual control Knowledge of the effect that a loss or 215004 Source Range Monitor X malfunction of the following will have on the 2.9 35 SOURCE RANGE MONITOR (SRH)

SYSTEM K6.04 Detectors Knowledge of AVERAGE POWER RANGE 215005 APRM I LPRM X MONITOR/LOCAL POWER RANGE 2.6 36 MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following:

K4.01 Rod withdrawal blocks Knowledge of the effect that a loss or 217000 RCIC X malfunction of the following will have on the 3.5 37 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) K6.04 Condensate storage and transfer svstem Ability to monitor automatic operations of the 218000 ADS X AUTOMATIC DEPRESSURIZATION 4.1 38 SYSTEM including A3.09 Reactor vessel water level Knowledge of the physical connections and/or 223002 PCIS/Nuclear Steam X cause effect relationships between PRIMARY 3.8 39 Supply Shutoff CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the Following K1.01 Main Steam System Knowledge of electrical power supplies to the 239002 SRVs X Following K2.01 SRV solenoids 2.8 40 Ability to predict and/or monitor changes in 259002 Reactor Water Level X parameters associated with operating the 3.8 41 Control REACTOR WATER LEVEL CONTROL SYSTEM controls including A4.01 Reactor water level Ability to (a) predict the impacts of the 261000 SGTS X following on the STANDBY GAS 3.1 42 TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations A2.1 0 Low reactor water level: Plant-Specific Knowledge of the operational implications of 262001 AC Electrical X the following concepts as they apply to A.C. 2.6 43 Distribution ELECTRICAL DISTRIBUTION K5.02 Breaker control Ability to manually operate and/or monitor in 262002 UPS (AC/DC) X the 2.8 44 control room:A4.01 Transfer from alternative source to preferred source Knowledge of electrical power supplies to the 263000 DC Electrical X following: K2.01: Major D.C. loads 3.1 45 Distribution 2.1.28 Knowledge of the purpose and function 264000 EDGs X of major system components and controls. 4.1 46 Knowledge of the operational implications of 300000 Instrument Air X the following concepts as they apply to the 2.5 47 INSTRUMENT AIR SYSTEM K5.01 Air compressors Ability to monitor automatic operations of the 400000 Component Cooling X CCWS including A3.01 Setpoints on 3.0 48 Water instrument signal levels for normal operations, warnings, and trips that are applicable to the ccws

Ability to monitor automatic operations of the 206000 HPCI X HIGH PRESSURE COOLANT INJECTION 3.9 49 SYSTEM including A3.07 Lights and alarms:

BWR-2,3,4 Knowledge of the effect that a loss or 215004 Source Range Monitor X malfunction of the SOURCE RANGE 3.4 50 MONITOR (SRM) SYSTEM will have on following K3.01 RPS Knowledge of the effect that a loss or 259002 Reactor Water Level X malfunction of the REACTOR WATER LEVEL 3.8 51 Control CONTROL SYSTEM will have on followina: K3.01: Reactor water level Knowledge of the effect that a loss or 263000 DC Electrical X malfunction of the D.C. ELECTRICAL 3.4 52 Distribution DISTRIBUTION System will have on the following: K3.01 Emergency Generators:

Plant-Specific Knowledge of the connections and I or cause 300000 Instrument Air X effect relationships between INSTRUMENT 2.8 53 AIR SYSTEM and the following K1.04 Coolinq water to compressor KIA Category Point Totals: 4 2 3 2 3 2 2 2 3 2 1 Group Point Total: 261 I I 5 2 3

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems- Tier 2/Group 2 (RO I SRO)

System # I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to (a) predict the impacts of the 290001 Secondary CNTMT X following on the SECONDARY 3.7 91 CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.02 Excessive outleaka_g_e.

2.4.11 Knowledge of abnormal condition 239001 Main and Reheat Steam X procedures. 4.2 92 2.2.22 Knowledge of limiting conditions 21600 Nuclear Boiler lnst. X 4.0 93 for operations and safEltj' limits Knowledge of CONTROL ROD AND 201003 Control Rod and Drive X 3.8 54 Mechanism DRIVE MECHANISM design feature(s) and/or interlocks which provide for the following K4.02 Reed Switch Position 201004 RSCS Suppressed, system does not exist at N/A HC.

201005 RCIS Suppressed, system does not exist at N/A HC.

2.1. 7 Ability to evaluate plant 202002 Recirculation Flow Control X 4.4 55 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Ability to manually operate and/or 214000 RPIS X 3.8 56 monitor in the control room: A4.02 Control rod position Ability to predict and/or monitor changes 215001 Traversing In-core Probe X 2.5 57 in parameters associated with operating the TRAVERSING IN-CORE PROBE controls including A1.02 Detector Position Knowledge of the effect that a loss or 219000 RHR/LPCI: Torus/Pool Cooling X 3.9 58 Mode malfunction of the RHRILPCI:

TORUS/SUPPRESSION POOL COOLING MODE will have on following K3.01 Suppression pool temperature control Knowledge of the operational 223001 Primary CTMT and Aux. X 3.1 59 implications of the following concepts as they apply to PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES K5.01 Vacuum breaker/relief e>g_eration Knowledge of RHRILPCI:

226001 RHR/LPCI: CTMT Spray Mode X 2.9 60 CONTAINMENT SPRAY SYSTEM MODE design feature(s) and/or interlocks which provide for the following K4.12 Prevention of inadvertent containment spray activation.

Ability to predict and/or monitor changes 234000 Fuel Handling Equipment X 3.3 61 in parameters associated with operating the FUEL HANDLING EQUIPMENT controls including: A1.02 Refuel floor radiation levels/ airborne levels 239003 MSIV Leakage Control Suppressed, system does not exist at N/A HC.

Ability to predict and/or monitor changes 241000 Reactor/Turbine Pressure X 2.8 62 Regulator in parameters associated with operating the REACTORrrURBINE PRESSURE REGULATING SYSTEM controls lncludiJ"lfl_ A1.23 Main turbine vibration Ability to monitor automatic operations of 259001 Reactor Feedwater X 3.2 63 the REACTOR FEEDWATER SYSTEM including A3.11 Reactor feedpump runbacks: Plant-Sj:lecific Knowledge of the effect that a loss or 272000 Radiation Monitoring X 3.0 64 malfunction of the following will have on the RADIATION MONITORING SYSTEM K6.01 Reactor protection system Ability to manually operate and/or 286000 Fire Protection X 3.3 65 monitor from the control room A4.01 System alarms and indicating lights.

KIA Category Point Totals: 0 0 1 2 1 1 2 1 1 2 1 Group Point Total: 1213 I I 1 2 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

Facility: Hope Creek Date of Exam: August 19,2013 Category K/A# Topic RO SRO-Only IR # IR #

2.1.1 Knowledge of conduct of operations requirements. 3.8 66 Ability to interpret reference materials, such as graphs, curves, 2.1.25 3.9 67

1. tables. etc.

Conduct Knowledge of the refueling process.

2.1.41 3.7 94 of Operations Knowledge of individual licensed operator responsibilities related 2.1.4 to shift staffing. such as medical requirements. "no-solo" 3.8 95 operation, maintenance of active license status. 10CFR55, etc.

Subtotal 2 '  ;, ..;, 2 Knowledge of limiting conditions for operations and safety limits.

2.2.22 4.0 68 2.2.42 Ability to recognize system parameters that are entry-level 3.9 69 conditions for Technical Specifications.

2.

Equipment 2.2.13 Knowledge of tagging and clearance procedures. 4.1 70 Control Knowledge of the process for making design or operating 3.2 2.2.5 96 changes to the facility.

Ability to determine operability and/or availability of safety related 2.2.37 equipment.

4.6 97 Subtotal 3

,, 2 Knowledge of radiological safety principles pertaining to licensed 2.3.12 operator duties. such as containment entry requirements. fuel 3.2 71 handling responsibilities, access to locked high-radiation areas.

aligning filters. etc.

3. Ability to control radiation releases.

2.3.11 3.8 72 Radiation Knowledge of radiation exposure limits under normal or Control 2.3.4 3.7 98 emerqency conditions.

Subtotal 2 < ::i 1 2.4.17 Knowledge of EOP terms and definitions. 3.9 73 Ability to identify post-accident instrumentation.

2.4.3 3.7 74 4.

Knowledge of abnormal condition procedures.

Emergency 2.4.11 4.0 75 Procedures I Knowledge of operator response to loss of all annunciators.

Plan 2.4.32 4.0 99 2.4.45 Ability to prioritize and interpret the significance of each 4.3 100 annunciator or alarm.

Subtotal 3 ,,_ 2

( (,'i'*

Tier 3 Point Total 10 ,, 7

ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA T1/G1 295023 AK3.01 Changed to AK3.03- could not write suitable 0 for original KA. (0#10)

T2/G1 262002 A 1.02 Changed to A4/01- could not write suitable 0 for original KA.

(0#44)

T2/G2 226001 K4.04 Changed to K4.12 - could not write suitable 0 for original KA.

(Prevention of water hammer KIA @ 2.6) (0 #60)

T2/G2 286000 K6.06 Changed to A4.01 - could not write suitable 0 for original KA.

(0#65)

T1/G1 600000 A 1.05 Changed to K3.04- could not write suitable 0 for original KA.

(0#19)

T2/G2 214000 A2.03 Changed to A4.02- could not write suitable 0 for original KA.

(0#56)

T2/G2 234000 A4.01 Changed to A 1.02 - could not write suitable 0 for original KA.

(0#61)

T2/G1 263000 A2.02 Could not write a 0 with sufficient level of difficulty for selected KA (0#52)

T1/G1 295038 A2.03 Changed to 295031 EA2.01- Could not write suitable 0 for original KA. (0#81)

Gen 2.4.22 Generic KA unsuitable for RO level question (0#75)

T2/G1 2.2.12 Changed to 2.1.28 could not write suitable 0 for original KA.

(0#46)

Gen 2.4.32 Generic KA overlaps with Admin JPMs and scenarios (0#99)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: HoQe Creek Date of Examination: 8/19/13 Examination Level: Ro xD SRO D Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Monitor, Log and Control the Drywell and Suppression R,D Chamber Purge System Valves RO A-1 Conduct of Operations (Bank- HC ZZ001)

Perform a Reactor Recirculation Pump Quick Restart S,D RO A-2 Conduct of Operations (Bank- HC ZZ011)

Identify Core Spray Leak Isolation, Vent & Drain Paths RO A-3 Equipment Control R,N (New- NRC Generated)

Radiation Control N/A N/A Respond to an Abnormal Release of Gaseous RO A-4 Emergency S,D Radioactivity - Calculate Noble Gas Release Rates Procedures/Plan (Bank- HC ZZ019)

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

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

(N)ew or (M)odified from bank (<:: 1)

(P)revious 2 exams (s 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Ho12e Creek Date of Examination: 8/19/13 Examination Level: ROD SRO xD Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Verify Compliance With Gaseous Release Permit R,D (Bank- HC ZZ003)

SRO A-1 Conduct of Operations Initiate and Review System Lineup Sheets R,D SRO A-2 Conduct (Modified- HC ZZ031) of Operations Identify Core Spray Leak Isolations, Vent & Drain Paths R,N and Determine Applicable Tech Spec Requirements SRO A-3 Equipment Control (New- NRC Generated)

Determine Liquid Radwaste Rad Monitor CTB Weir S,D Flow SRO A-4 Radiation Control (Bank- HC ZZ038)

Utilize the ECG to Determine the Emergency R,N Classification and/or Reportability of an Event and/or SRO A-5 Emergency Plant Condition Procedures/Plans (Bank - HC ECG005)

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

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:53 for ROs; :54 for SROs & RO retakes)

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

(P)revious 2 exams (:5 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Ho(2e Creek Date of Examination: 8/19/2013 Exam Level: Ro xD SR0-1 D SRO-U D Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function S-1 Reset the Reactor Recirc 'B' Scoop Tube Positioner (Ait Path) A,D,S 1 (Reactivity Control)

(Bank- HC JPM BB003)

S-2 Manually Start the Core Spray System (Ait Path) A,D,E,EN,L,S 2 (Reactor Water Inventory (Bank- HC JPM BE005) Control)

S-3 Place HPCI In Full Flow Recirc D,E,L,S 3 (Reactor Pressure Control)

(Bank- HC JPM BJ006)

S-4 Transfer Shutdown Cooling to the Standby Shutdown Cooling A,D,L,S 4 (Heat Removal Loop (Ait Path) From the Core)

(Bank- HC JPM BCO 15)

S-5 Suppression Chamber Makeup From Service Water Loop B N,S,E 5 (Containment Integrity)

(New)

S-6 Synchronize and Load Main Generator to the Grid (Ait Path) N,A,S 6 (Electrical)

(New)

S-7 Defeat RPS Interlocks D,E,EN,L,S 7 (Instrumentation)

(Bank- HC JPM SB012)

S-8 Vent the Containment via the Hard Torus Vent (Ait Path) A,D,EN,L,S 9 (Radioactivity Release)

(Bank- HCJPM GS005)

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P-1 Line up for Alternate Injection Using Fire Water D,E,EN,L 8 (Plant Service Systems)

(Bank- HC JPM BC007)

P-2 Manually Start 'A' EDG From the Local Panel D,E,EN,L,P 6 (Electrical)

(Bank- HC JPM KJ002)

P-3 Isolate and Vent the SCRAM Air Header R,L,D,E 4 (Heat Removal From the Core)

(Bank-HC JPM BD0004)

@ All RO and SR0-1 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 SR0-1 I SRO-U (A}Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank S91S81S4 (E)mergency or abnormal in-plant <:11<:11<:1 (EN)gineered safety feature - I - I <:1 (control room system)

(L)ow-Power I Shutdown <:11<:11<:1 (N)ew or (M}odified from bank including 1(A) <:21<:21<:1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

(R)CA <:11<:11<:1 (S )imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Ho(2e Creek Date of Examination: 8/19/2013 Exam Level: ROD SR0-1 xD SRO-U D Operating Test Number: 1 Control Room Systems@ (8 for RO); {7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function S-1 Reset the Reactor Recirc 'B' Scoop Tube Positioner {Ait Path) A,D,S 1 (Reactivity Control)

(Bank- HC JPM BB003)

S-2 Manually Start the Core Spray System (Ait Path) A,D,E,EN,L,S 2 (Reactor Water Inventory (Bank- HC JPM B£005)

Control)

S-3 Place HPCI into Full Flow Recirc D,E,L,S 3 (Reactor Pressure Control)

(Bank- HC JPM BJ006)

S-4 Transfer Shutdown Cooling to the Standby Shutdown Cooling A,D,L,S 4 (Heat Removal Loop {Ait Path) From the Core)

(Bank- HC JPM BCOJ5)

S-5 Suppression Chamber Makeup From Service Water Loop B N,S,E 5 (Containment Integrity)

(New)

S-6 Synchronize and Load Main Generator to the Grid {Ait Path) N,A,S 6 (Electrical)

(New)

S-8 Vent the Containment via the Hard Torus Vent {Ait Path) A,D,EN,L,S 9 (Radioactivity Release)

(Bank- HCJPM GS005)

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P-1 Line up for Alternate Injection Using Fire Water D,E,EN,L 8 (Plant Service Systems)

(Bank- HC JPM BC007)

P-2 Manually Start 'A' EDG From the Local Panel D,E,EN,L,P 6 (Electrical)

(Bank- HC JPM KJ002)

P-3 Isolate and Vent the SCRAM Air Header R,L,D,E 4 (Heat Removal From the Core)

(Bank-HC JPM BD0004)

@ All RO and SR0-1 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 SR0-11 SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :591:581:54 (E)mergency or abnormal in-plant 2!:112!:112!:1 (EN)gineered safety feature - I - I 2!:1 (control room system)

(L)ow-Power I Shutdown 2!:11<!:112!:1 (N)ew or (M)odified from bank including 1(A) <!:21<!:212!:1 (P)revious 2 exams :5 31 :5 31 :52 (randomly selected)

(R)CA 2!:11<!:112!:1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Ho(2e Creek Date of Examination: 8/19/2013 Exam Level: ROD SR0-1 D SRO-U x0 Operating Test Number: 1 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function S-2 Manually Start the Core Spray System (Ait Path) A,D,E,EN,L,S 2 (Reactor Water Inventory (Bank- HC JPM BE005)

Control)

S-5 Suppression Chamber Makeup From Service Water Loop B N,S,E 5 (Containment Integrity)

(New)

S-6 Synchronize and Load Main Generator to the Grid (Ait Path) N,A,S 6 (Electrical)

(New)

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P-1 Line up for Alternate Injection Using Fire Water D,E,EN,L 8 (Plant Service Systems)

(Bank- HC JPM BC007)

P-3 Isolate and Vent the SCRAM Air Header R,L,D,E 4 (Heat Removal From the Core)

(Bank-HC JPM BD0004)

@ All RO and SR0-1 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 SR0-11 SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank  :'591:581:54 (E)mergency or abnormal in-plant ~11~11~1 (EN)gineered safety feature - I - I ~1 (control room system)

(L)ow-Power I Shutdown ~11~11~1 (N)ew or (M)odified from bank including 1(A) ~21~21~1 (P)revious 2 exams $ 3 I$ 3 I :52 (randomly selected)

(R)CA ~11~11~1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: .L Op-Test No.: NRC2013 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 100% reactor power, RCIC CIT for a leak on the steam line drain pot.

Turnover: RAGS pumped are to be swapped to support an oil change on the 'B' RAGS pump.

Lower power to 90% using recirc pumps to support rod pattern adjustment.

Event Malf. No. Event Event No. Type* Description See SEG

1. N-BOP Swap 'A' and 'B' RAGS pumps See SEG

2. C-BOP Loss of RBVS TS-CRS See SEG

3. C-All Loss of 10A120 R-ATC TS-CRS See SEG

4. C-All Recirc Pump High Vibrations See SEG

5. M-All Feedwater Line Break Inside Containment See SEG

6. C-BOP RHR pumps fail to auto start See SEG

7. C-BOP BPV jack failure See SEG

8. C-All DW spray valve failure

• (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.:£_ Op-Test No.: NRC2013 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 100% power, 'A' EHC Pump out of service for planned maintenance.

Turnover: N2 Makeup to Primary Containment is Required.

Event Malf. No. Event Event No. Type* Description

1. See SEG N-BOP N2 Makeup to Primary Containment See SEG

2. R-ATC Lower power using recirculation flow See SEG

3. C-BOP 1CD481 Inverter Failure w/ TAGS failure to Auto swap TS-SRO See SEG

4. C-ATC 'A' Recirc Pump Seal Failure TS-SRO See SEG

5. C-ATC Power Oscillations See SEG

6. M-All Electrical ATWS/ARI Failure See SEG C-ATC

7. RWCU Failure to Isolate Upon SLC Initiation See SEG C-All

8. 'B' EHC Pump Trip See SEG

9. C-BOP RHR Torus Cooling Valve failure

• (N)ormal, (R)eactivity, (l)nstrument, (C )om ponent, (M)ajor

Appendix 0 Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: ~ Op-Test No.: NRC2013 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The scenario begins with the plant at 75% power and TACS on the 'B' SACS loop.

The DK111 Turbine Chiller is CIT for a freon leak and CP161 is CIT for a bearing oil leak Turnover: Raise power 5% using recirculation flow.

Event Malf. No. Event Event No. Type* Description

1. See SEG R-ATC Raise Power Using Recirculation Flow See SEG

2. 1-ATC APRM Channel C Upscale w/Single Rod Scram TS-CRS See SEG

3. C-BOP Loss of TB Chilled Water/DI}'Well Coolinq See SEG

4. C-ATC Loss of 108430 TS-CRS See SEG

5. C-BOP HPCI Inadvertent Actuation/HPCI Steam Leak TS-CRS See SEG

6. M-ALL HPCI Steam Leak w/Failure to Isolate See SEG

7. C-BOP "A" FRVS fan trip See SEG

8. C-ATC Mode Switch & RPS Failure to SCRAM (ARI successful)

See SEG

9. C-BOP FW Htr #2 isolation post-scram See SEG

10. C-All RCIC Pump Room high temperature

• {N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M}ajor