ML15126A266

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Final Outlines (Folder 3)
ML15126A266
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 01/19/2015
From:
Susquehanna
To: Todd Fish
Operations Branch I
Shared Package
ML14350A011 List:
References
TAC U01933
Download: ML15126A266 (24)
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ES-401 Written Examination Outline Form ES-401-1 Facility: Susquehanna Date of Exam: January 2015 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • 1 2 3 4 ,. 4 3 3 20 3 4 7
1. .\ ..

Emergency **:.!* \!!*!

& 2 1 1 1 <* .* 1 1 2 7 2 1 3 Plant Tier Evolutions 3 5 5 5 4 5 27 5 5 10 Totals 1 2 1 2 3 3 3 3 2 2 3 2 26 3 2 5 2.

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

3. Generic Knowledge & Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 2 3 2 2 2 2 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).
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 NRG revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding 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 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.
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 KIA's

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 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 10CFR55.43

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

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

3.6 76 Reactor water level AA2.10 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and GENERATOR VOLTAGE AND Electric Grid Disturbances x ELECTRIC GRID DISTURBANCES:

3.8 77 Generator overheating and the required actions EA2.06 - Ability to determine and/or interpret the following as they apply to 295028 High Drywell Temperature I 5 x HIGH DRYWELL TEMPERATURE: 3.7 78 Torus/suppression chamber air space temperature: Plant-Specific 295021 Loss of Shutdown 2.4.11 - Knowledge of abnormal Coolina 14 x condition procedures.

4.2 79 2.1.25 - Ability to interpret reference 295030 Low Suppression Pool Water Level I 5 x materials, such as graphs, curves, 4.2 80 tables, etc.

295024 High Drywell Pressure I 2.4.6 - Knowledge of EOP mitigation 5

x strategies.

4.7 81 295003 Partial or Complete 2.1.20 - Ability to interpret and execute Loss of AC Power I 6 x procedure steps.

4.6 82 EK2.01 - Knowledge of the interrelations 295026 Suppression Pool High between SUPPRESSION POOL HIGH Water Temperature I 5 x WATER TEMPERATURE and the 3.9 39 following: Suppression pool cooling EK1 .03 - Knowledge of the operational 295030 Low Suppression Pool implications of the following concepts as Water Level I 5 x they apply to LOW SUPPRESSION 3.8 40 POOL WATER LEVEL: Heat capacity AK1 .01 - Knowledge of the operational implications of the following concepts as 295018 Partial or Complete they apply to PARTIAL OR COMPLETE Loss of CCW I 8 x LOSS OF COMPONENT COOLING 3.5 41 WATER: Effects on component/system operations AK2.02 - Knowledge of the interrelations 295005 Main Turbine Generator between MAIN TURBINE GENERATOR Trip/ 3 x TRIP and the following: Feedwater 2.9 42 temperature EK2.18 - Knowledge of the interrelations 295024 High Drywell Pressure I 5

x between HIGH DRYWELL PRESSURE 3.3 43 and the following: Ventilation AK2.07 - Knowledge of the interrelations 295006 SCRAM I 1 x between SCRAM and the following: 4.0 44 Reactor pressure control EK3.04 - Knowledge of the reasons for 295038 High Off-site Release the following responses as they apply to Rate/ 9 x HIGH OFF-SITE RELEASE RATE:

3.6 45 Emergency depressurization AK3.03 - Knowledge of the reasons for the following responses as they apply to 295001 Partial or Complete PARTIAL OR COMPLETE LOSS OF Loss of Forced Core Flow x FORCED CORE FLOW CIRCULATION: 2.8 46 Circulation/ 1 & 4 Idle loop flow

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AK3.03 - Knowledge of the reasons for 295003 Partial or Complete the following responses as they apply to Loss of AC Power I 6 x PARTIAL OR COMPLETE LOSS OF 3.5 47 A.C. POWER: Load sheddinQ EA 1.04 - Ability to operate and/or 295028 High Drywell monitor the following as they apply to Temperature I 5 x HIGH DRYWELL TEMPERATURE:

3.9 48 Drywell pressure EA 1.01 - Ability to operate and/or 295037 SCRAM Condition monitor the following as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND Above APRM Downscale or x REACTOR POWER ABOVE APRM 4.6 49 Unknown/ 1 DOWNSCALE OR UNKNOWN: Reactor Protection System AA 1.08 - Ability to operate and/or monitor the following as they apply to 295023 Refueling Accidents I 8 x REFUELING ACCIDENTS: Radiation 3.4 50 monitorinQ equipment AA2.16 - Ability to determine and interpret the following as they apply to 600000 Plant Fire On-site I 8 x PLANT FIRE ON SITE: Vital equipment 3.0 51 and control systems to be maintained and operated during a fire AA2.06 - Ability to determine and/or 295016 Control Room interpret the following as they apply to Abandonment I 7 x CONTROL ROOM ABANDONMENT:

3.3 52 Cooldown rate AA2.04 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and Electric Grid Disturbances x GENERATOR VOLTAGE AND 3.6 53 ELECTRIC GRID DISTURBANCES:

VARs outside capability curve 295025 High Reactor Pressure I 2.2.40 - Ability to apply technical 3

x specifications for a svstem.

3.4 54 2.4.9 - Knowledge of low power I shutdown implications in accident (e.g.,

295004 Partial or Complete Loss of DC Power I 6 x loss of coolant accident or loss of 3.8 55 residual heat removal) mitigation strategies.

2.4.50 - Ability to verify system alarm 295019 Partial or Complete Loss of Instrument Air I 8 x setpoints and operate controls identified 4.2 56 in the alarm response manual.

AA 1.02 - Ability to operate and/or 295021 Loss of Shutdown monitor the following as they apply to Cooling/ 4 x LOSS OF SHUTDOWN COOLING:

3.5 57 RHR/shutdown cooling EK3.02 - Knowledge of the reasons for 295031 Reactor Low Water the following responses as they apply to Level/ 2 x REACTOR LOW WATER LEVEL: Core 4.4 58 coverage KIA Category Totals: 2 4 4 4 3/3 3/4 Group Point Total: 2017 I

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

EA2.01 - Ability to determine and/or 295029 High Suppression Pool interpret the following as they apply to Water Level I 5 x HIGH SUPPRESSION POOL WATER 3.9 83 LEVEL: Suppression pool water level 2.4.30 - Knowledge of events related to system operation I status that must be 295010 High Drywell Pressure I reported to internal organizations or 5

x external agencies, such as the state, the 4.1 84 NRC, or the transmission system operator.

AA2.02 - Ability to determine and/or interpret the following as they apply to 295015 Incomplete SCRAM/ 1 x INCOMPLETE SCRAM: Control rod 4.2 85 position AK1 .03 - Knowledge of the operational 295008 High Reactor Water implications of the following concepts as Level/ 2 x they apply to HIGH REACTOR WATER 3.2 59 LEVEL : Feed flow/steam flow mismatch EK2.01 - Knowledge of the interrelations 295032 High Secondary between HIGH SECONDARY Containment Area Temperature x CONTAINMENT AREA 3.5 60 15 TEMPERATURE and the following:

Area/room coolers AK3.07 - Knowledge of the reasons for the following responses as they apply to 2950201nadvertent Containment Isolation I 5 & 7 x INADVERTENT CONTAINMENT 3.4 61 ISOLATION: Suppression pool temperature response AA 1.01 - Ability to operate and/or 295002 Loss of Main monitor the following as they apply to Condenser Vacuum I 3 x LOSS OF MAIN CONDENSER 2.6 62 VACUUM: Condensate system AA2.01 - Ability to determine and/or 295010 High Drywell Pressure I interpret the following as they apply to 5

x HIGH DRYWELL PRESSURE: Leak 3.4 63 rates 295014 Inadvertent Reactivity 2.1.32 - Ability to explain and apply all Addition/ 1 x system limits and precautions.

3.8 64 295029 High Suppression Pool 2.4.46 - Ability to verify that the alarms Water Level I 5 x are consistent with the plant conditions.

4.2 65 KIA Category Totals: 1 1 1 1 1/2 2/1 Group Point Total:

I 7/3

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A2.05 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use 209001 LPCS x procedures to correct, control, or 3.6 86 mitigate the consequences of those abnormal conditions or operations: Core spray line break A2.06 - Ability to (a) predict the impacts of the following on the AC. ELECTRICAL DISTRIBUTION; and (b) based 262001 AC Electrical on those predictions, use Distribution x procedures to correct, control, or 2.9 87 mitigate the consequences of those abnormal conditions or operations: De-energizing a plant bus 2.1.28 - Knowledge of the 400000 Component Cooling purpose and function of major Water x system components and 4.1 88 controls.

2.4.18 - Knowledge of the 215005 APRM I LPRM x specific bases for EOPs.

4.0 89 A2.04 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, 239002 SRVs x use procedures to correct, 4.1 90 control, or mitigate the consequences of those abnormal conditions or operations: ADS actuation K1 .02 - Knowledge of the physical connections and/or cause-effect relationships 263000 DC Electrical Distribution x between D.C. ELECTRICAL 3.2 1 DISTRIBUTION and the following: Battery charger and battery K1 .01 - Knowledge of the physical connections and/or cause-effect relationships 215004 Source Range Monitor x between SOURCE RANGE 3.6 2 MONITOR (SRM) SYSTEM and the following: Reactor protection system A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the 259002 Reactor Water Level x REACTOR WATER LEVEL 3.6 3 Control CONTROL SYSTEM controls including: Reactor Feedwater flow K2.01 - Knowledge of electrical 239002 SRVs x power supplies to the following: 2.8 4 SRV solenoids

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System #I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 K3.07 - Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER 262002 UPS (AC/DC) x SUPPLY (A.C./D.C.) will have 2.6 5 on following: Movement of control rods: Plant-Specific K3.06 - Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT 261000 SGTS x SYSTEM will have on following:

3.0 6 Primary containment oxygen content: Mark-1&11 K4.01 - Knowledge of CCWS design feature(s) and or 400000 Component Cooling Water x interlocks which provide for the 3.4 7 following: Automatic start of standby pump K4.05 - Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design feature(s) 209001 LPCS x and/or interlocks which provide 2.6 8 for the following: Pump minimum flow K5.02 - Knowledge of the operational implications of the 262001 AC Electrical Distribution x following concepts as they 2.6 9 apply to A.C. ELECTRICAL DISTRIBUTION: Breaker control K5.02 - Knowledge of the operational implications of the following concepts as they apply 217000 RCIC x to REACTOR CORE 3.1 10 ISOLATION COOLING SYSTEM (RCIC): Flow indication K6.05 - Knowledge of the effect that a loss or malfunction of the following will have on the 205000 Shutdown Cooling x SHUTDOWN COOLING 3.2 11 SYSTEM (RHR SHUTDOWN COOLING MODE): Component coolina water systems K6.05 - Knowledge of the effect that a loss or malfunction of the following will have on the 218000 ADS x AUTOMATIC 3.0 12 DEPRESSURIZATION SYSTEM: A.C. power: Plant-Specific A 1.03 - Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT 223002 PCIS/Nuclear Steam ISOLATION Supply Shutoff x SYSTEM/NUCLEAR STEAM 2.5 13 SUPPLY SHUT-OFF controls including:

SPDS/ERIS/CRIDS/GDS:

Plant-Specific

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A 1.08 - Ability to predict and/or monitor changes in parameters associated with operating the 211000 SLC x STANDBY LIQUID CONTROL 3.7 14 SYSTEM controls including:

RWCU system lineup A2.03 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those 215005 APRM I LPRM x predictions, use procedures to 3.6 15 correct, control, or mitigate the consequences of those abnormal conditions or operations: Inoperative trip (all causes)

A2.05 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET); and (b) based on those predictions, use 264000 EDGs x procedures to correct, control, or 3.6 16 mitigate the consequences of those abnormal conditions or operations: Synchronization of the emergency generator with other electrical supplies A3.05 - Ability to monitor automatic operations of the 203000 RHR/LPCI: Injection Mode x RHR/LPCI: INJECTION MODE 4.4 17 (PLANT SPECIFIC) including:

Reactor water level A3.03 - Ability to monitor automatic operations of the 215003 IRM x INTERMEDIATE RANGE 3.7 18 MONITOR (IRM) SYSTEM including: RPS status A4.06 - Ability to manually operate and/or monitor in the 206000 HPCI x control room: Reactor pressure:

4.3 19 BWR-2,3,4 A4.01 - Ability to manually 300000 Instrument Air x operate and/or monitor in the 2.6 20 control room: Pressure gauges 2.4.34 - Knowledge of RO tasks performed outside the main 212000 RPS x control room during an 4.2 21 emergency and the resultant operational effects.

2.1.23 - Ability to perform specific system and integrated 211000 SLC x plant procedures during all 4.3 22 modes of plant operation.

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 K4.04 - Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) 261000 SGTS x and/or interlocks which provide 2.7 23 for the following: Radioactive particulate filtration K6.07 - Knowledge of the effect that a loss or malfunction of the 400000 Component Cooling Water x following will have on the 2.7 24 CCWS: Breakers, relays, and disconnects A4.05 - Ability to manually operate and/or monitor in the 262001 AC Electrical Distribution x control room: Voltage, current, 3.3 25 power, and frequency on A.C.

buses K5.01 - Knowledge of the operational implications of the following concepts as they apply 263000 DC Electrical Distribution x to D.C. ELECTRICAL 2.6 26 DISTRIBUTION: Hydrogen generation during battery charaing.

KIA Category Totals: 2 1 2 3 3 3 3 2/3 2 3 2/2 Group Point Total:

I 26/5

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A System #I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A2.07 - Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use 239001 Main and Reheat Steam x procedures to correct, control, 3.9 91 or mitigate the consequences of those abnormal conditions or operations: Main steam area high temperature or differential temperature hiah 2.4.41 - Knowledge of the 230000 RHR/LPCI:

Torus/Pool Spray Mode x emergency action level 4.6 92 thresholds and classifications.

2.2.12 - Knowledge of 271000 Off-gas x surveillance procedures.

4.1 93 K1 .04 - Knowledge of the physical connections and/or cause-effect relationships 241000 Reactor/Turbine Pressure Regulator x between REACTOR/TURBINE 3.7 27 PRESSURE REGULATING SYSTEM and the following:

Reactor steam flow K2.01 - Knowledge of electrical 239001 Main and Reheat power supplies to the following:

Steam x Main steam isolation valve 3.2 28 solenoids K3.02 - Knowledge of the effect that a loss or malfunction of the RHR/LPCI:

230000 RHR/LPCI:

Torus/Pool Spray Mode x TORUS/SUPPRESSION POOL 3.3 29 SPRAY MODE will have on following: Suppression pool temperature K4.01 - Knowledge of ROD BLOCK MONITOR SYSTEM design feature(s) and/or 215002 RBM x interlocks which provide for the 3.4 30 following: Prevent control rod withdrawal: BWR-3,4,5 K5.02 - Knowledge of the operational implications of the following concepts as they apply 201001 CRD Hydraulic x to CONTROL ROD DRIVE 2.6 31 HYDRAULIC SYSTEM: Flow indication K6.02 - Knowledge of the effect that a loss or malfunction of the 290003 Control Room following will have on the HVAC x CONTROL ROOM HVAC:

2.7 32 Component cooling water systems A 1.02 - Ability to predict and/or monitor changes in parameters 233000 Fuel Pool associated with operating the Cooling/Cleanup x FUEL POOL COOLING AND 2.9 33 CLEAN-UP controls including:

Pool level

ES-401 Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A System # I Name A2 G Imp. Q#

1 2 3 4 5 6 1 3 4 A2.08 - Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) 201003 Control Rod and based on those predictions, use Drive Mechanism x procedures to correct, control, 3.8 34 or mitigate the consequences of those abnormal conditions or operations: Low HCU accumulator pressure/high level A3.03 - Ability to monitor automatic operations of the 201002 RMCS x REACTOR MANUAL 3.2 35 CONTROL SYSTEM including:

Rod drift alarm A4.02 - Ability to manually operate and/or monitor in the 214000 RPIS x control room: Control rod 3.8 36 position 2.4.35 - Knowledge of local auxiliary operator tasks during 204000 RWCU x emergency and the resultant 3.8 37 operational effects.

K1.08 - Knowledge of the physical connections and/or cause-effect relationships 286000 Fire Protection x between FIRE PROTECTION 3.0 38 SYSTEM and the following:

Intake canals: Plant-Specific KIA Category Totals: 2 1 1 1 1 1 1 1/1 1 1 1/2 Group Point Total: 12/3 I

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Susquehanna Date: January 2015 RO SRO-Only Category KIA# Topic IR Q# IR Q#

Knowledge of criteria or conditions that 2.1.14 require plant-wide announcements, such as 3.1 94 pump starts, reactor trips, mode chanqes, etc.

Ability to evaluate plant performance and make operational judgments based on 2.1.7 4.7 100 operating characteristics, reactor behavior, and instrument interpretation.

1.

Conduct of Operations Knowledge of operator responsibilities during 2.1.2 4.1 66 all modes of plant operation.

2.1.21 Ability to verify the controlled procedure copy. 3.5 67 Ability to use procedures related to shift 2.1.5 staffing, such as minimum crew complement, 2.9 75 overtime limitations, etc.

Subtotal 3 2 Knowledge of the process for making design 2.2.5 3.2 95 or operatinq chanqes to the facility.

Knowledge of the process for conducting 2.2.7 3.6 99 special or infrequent tests.

2.

Equipment Knowledge of the process used to track 2.2.43 3.0 68 Control inoperable alarms Ability to determine Technical Specification 2.2.35 3.6 69 Mode of Operation.

Subtotal 2 2 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, 2.3.13 3.8 96 containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligninq filters, etc.

Knowledge of radiation or containment

3. hazards that may arise during normal, Radiation 2.3.14 3.8 98 abnormal, or emergency conditions or Control activities.

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

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of radiation exposure limits under 2.3.4 3.2 71 normal or emergency conditions.

2.3.11 Ability to control radiation releases. 3.8 74 Subtotal 3 2 2.4.6 Knowledge of EOP mitigation strategies. 4.7 97 4.

Emergency Knowledge of EOP entry conditions and 2.4.1 4.6 72 Procedures I immediate action steps.

Plan Knowledge of crew roles and responsibilities 2.4.13 4.0 73 during EOP usage.

Subtotal *. 2 1 Tier 3 Point Total 10 7

ES-401 Record of Rejected KlAs Form ES-401-4 Randomly Selected KIA Reason for Rejection 295027 High Containment This topic applies to plants with Mark Ill Temperature containments only. The facility has a Mark II 1/ 1 containment.

295011 High Containment This topic applies to plants with Mark 111 Temperature containments only. The facility has a Mark II 1/2 containment.

207000 Isolation (Emergency) This system is not installed at the facility.

2/1 Condenser 209002 HPCS This system is not installed at the facility.

2/1 201004 RSCS This system is no longer installed at the facility.

212 201005 RCIS This system is not installed at the facility.

212 239003 MSIV Leakage Control This system is no longer installed at the facility.

212

Question 50 295023 Refueling Accidents Randomly resampled KJA 295023 Refueling AA 1.08 - Ability to operate Accidents AA 1.04 - Ability to operate and/or 1/ 1 and/or monitor the following as monitor the following as they apply to they apply to REFUELING REFUELING ACCIDENTS: Radiation ACCIDENTS: Containment monitoring equipment.

building ventilation: Mark-Ill Question 85 A discriminating SRO-level question cannot be developed for the randomly sampled KJA.

295014 Inadvertent Reactivity Additionally, this topic is oversampled Addition (Questions 64 and 85).

AA2.03 - Ability to determine 1/2 Randomly resampled KJA 295015 Incomplete and/or interpret the following as SCRAM AA2.02 - Ability to determine and/or they apply to INADVERTENT interpret the following as they apply to REACTIVITY ADDITION:

INCOMPLETE SCRAM: Control rod position.

Cause of reactivity addition Question 63 The facility is a BWR-4, not a BWR-6.

295010 High Drywell Pressure Randomly resampled KJA 295010 High Drywell Pressure AA2.01 - Ability to determine and/or AA2.05 - Ability to determine interpret the following as they apply to HIGH 1/2 and/or interpret the following as DRYWELL PRESSURE: Leak rates.

they apply to HIGH DRYWELL PRESSURE: Drywell air cooler drain flow: BWR-6 Question 89 The randomly sampled generic KJA does not support developing an SRO-level question for 215005 APRM I LPRM the given system.

2.4.34 - Knowledge of RO tasks Randomly resampled KJA 215005 APRM I 2/1 performed outside the main LPRM 2.4.18 - Knowledge of the specific bases control room during an for EOPs.

emergency and the resultant operational effects.

Question 3 The facility does not have a Feedwater coolant injection mode for the Feedwater system.

259002 Reactor Water Level Control Randomly resampled KIA 259002 Reactor Water Level Control A 1.02 - Ability to predict K2.02 - Knowledge of electrical 2/1 and/or monitor changes in parameters power supplies to the following:

associated with operating the REACTOR Feedwater coolant injection WATER LEVEL CONTROL SYSTEM controls (FWCI) initiation logic:

including: Reactor Feedwater flow.

FWCl/HPCI Question 15 A question could not be developed for t~e randomly sampled KIA without overlapping 215005 APRM I LPRM GFE material.

A2.1 O - Ability to (a) predict the Randomly resampled KIA 215005 APRM I impacts of the following on the LPRM A2.03 - Ability to (a) predict the impacts AVERAGE POWER RANGE of the following on the AVERAGE POWER MONITOR/LOCAL POWER RANGE MONITOR/LOCAL POWER RANGE RANGE MONITOR SYSTEM; 2/1 MONITOR SYSTEM; and (b) based on those and (b) based on those predictions, use procedures to correct, control, predictions, use procedures to or mitigate the consequences of those .

correct, control, or mitigate the abnormal conditions or operations: Inoperative consequences of those trip (all causes).

abnormal conditions or operations: Changes in void concentration Question 36 The facility does not have RCIS.

214000 RPIS Randomly resampled KIA 214000 RPIS A4.02 -

Ability to manually operate and/or monitor in the A4.01 - Ability to manually 212 control room: Control rod position.

operate and/or monitor in the control room: RCIS rod action control bypass switches Question 83 An acceptable question could not be developed for the randomly sampled KIA without 295029 High Suppression Pool overlapping the previous NRC exam's Question Water Level 65.

EA2.03 - Ability to determine Randomly resampled KIA 295029 High ..

1/ 2 and/or interpret the following as Suppression Pool Water Level EA2.01 .- Ability they apply to HIGH to determine and/or interpret the following as SUPPRESSION POOL WATER they apply to HIGH SUPPRESSION POOL LEVEL: Drywell/containment WATER LEVEL: Suppression pool water level.

water level

Question 90 An acceptable question could not be written at the SRO license level for the randomly sampled 239002 SRVs KIA.

A2.05 - Ability to (a) predict the Randomly resampled KIA 239002 SRVs A2.04 impacts of the following on the

- Ability to (a) predict the impacts of the RELIEF/SAFETY VALVES; and following on the RELIEF/SAFETY VALVES; (b) based on those predictions, 2/ 1 and (b) based on those predictions, use use procedures to correct, procedures to correct, control, or mitigate the control, or mitigate the consequences of those abnormal conditions or consequences of those operations: ADS actuation.

abnormal conditions or operations: Low reactor pressure Question 21 An acceptable question could not be developed at the RO license level for the randomly 212000 RPS sampled KIA.

2.2.36 - Ability to analyze the Randomly resampled KIA 212000 RPS 2.4.34 -

2/ 1 effect of maintenance activities, Knowledge of RO tasks performed outside the such as degraded power main control room during an emergency and sources, on the status of limiting the resultant operational effects.

conditions for operations.

Question 40 An acceptable question could not be developed for the randomly sampled KIA without 295030 Low Suppression Pool overlapping Question 80 (SRO Question 5).

Water Level Randomly resampled KIA 295030 Low EK1 .02 - Knowledge of the Suppression Pool Water Level EK1 .03 -

1/ 1 operational implications of the Knowledge of the operational implications of the following concepts as they following concepts as they apply to LOW apply to LOW SUPPRESSION SUPPRESSION POOL WATER LEVEL: Heat POOL WATER LEVEL: Pump capacity.

NPSH Question 53 An acceptable question could not be developed for the randomly sampled KA due to lack of 700000 Generator Voltage and documented system or procedural limitations Electric Grid Disturbances for Generator frequency limitations.

AA2.06 - Ability to determine Randomly resampled KIA 700000 Generator 1/ 1 and/or interpret the following as Voltage and Electric Grid Disturbances AA2.04 they apply to GENERATOR

- Ability to determine and/or interpret the VOLTAGE AND ELECTRIC following as they apply to GENERATOR GRID DISTURBANCES:

VOLTAGE AND ELECTRIC GRID Generator frequency limitations DISTURBANCES: VARs outside capability curve.

Question 68 An acceptable and discriminating question could not be developed at the RO license level 2.2.41 - Ability to obtain and for the randomly sampled KIA.

3 interpret station electrical and mechanical drawings. Randomly resampled KIA 2.2.43 - Knowledge of the process used to track inoperable alarms.

Question 69 The randomly sampled KIA has already been tested on Question 54. Resampling to limit 2.2.40 - Ability to apply overlap.

technical specifications for a 3 system. Randomly resampled KIA 2.2.35 - Ability to determine Technical Specification Mode of Operation.

Question 73 An acceptable question could not be developed at the RO license level for the randomly 2.4.41 - Knowledge of the sampled KIA.

emergency action level 3 thresholds and classifications. Randomly resampled KIA 2.4.13 - Knowledge of crew roles and responsibilities during EOP usage.

Question 39 An acceptable question could not be developed for the randomly sampled KIA without testing 295026 Suppression Pool High Generic Fundamentals material.

Water Temperature Randomly resampled KIA 295026 Suppression EK1 .02 - Knowledge of the Pool High Water Temperature EK2.01 -

operational implications of the 1/ 1 Knowledge of the interrelations between following concepts as they SUPPRESSION POOL HIGH WATER apply to SUPPRESSION POOL TEMPERATURE and the following:

HIGHWATER Suppression pool cooling.

TEMPERATURE: Steam condensation Question 93 An acceptable question could not be developed for the randomly sampled generic KIA due to a 271000 Off-gas lack of significant design, procedural, or 2.2.3 - (multi-unit license) operational differences between units for the 212 Knowledge of the design, Offgas system.

procedural, and operational Randomly resampled KIA 271000 Off-gas differences between units. 2.2.12 - Knowledge of surveillance procedures.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SSES Units 1 and 2 Date of Examination: January 19-30, 2015 Exam Level: RO 0 SRO. Operating Test No.: Loc26 NRC Retake Administrative Topic Type Describe activity to be performed (see Note) Code*

Compute Average Drywell Air Temperature Conduct of Operations S,D 00.S0.2103.101 S0-100-007, KIA 2.2.12 (3.4)

Determine Estimated Time to 200 °F and Conduct of Operations R,D Required T.S. Action 49.0N.1869.103 ON-149-001, KIA 2.1.25 (4.2)

Authorize Bypassing Rod Block Monitor Equipment Control R,D 00.AD.1021.101 NDAP-QA-0338, KIA 2.1.37 (4.6)

Review and Approve Rad Liq Release Permit Radiation Control R,D OO.AD.2175.001 OP-069-050, KIA 2.3.6 (3.7)

Classify an Emergency Condition Emergency Procedures/Plan R,M OO.EP.1132.180 EP-PS-100, KIA 2.4.41 (4.6)

NOTE: All items (5 total) are required for SR Os. 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; :S 4 for SROs & RO retakes)

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: SSES Units 1 and 2 Date of Examination: January 19-30, 2014 Exam Level: RO D SRO-I

  • SRO-U D Operating Test No.: Loc26 NRC Retake Control Room Systems (8 for RO); (7 for SRO-I}; (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. Respond to Multiple Notching Rod (55.0N.2003.151) A,D,S 1
b. HPCI Full Flow Test Quarterly Surveillance A,D,S 2 (52.S0.1964.151}
c. Main Steam Line Isolation Recovery (84.0N.003.101} D,L,S 3
d. Perform Manual Comp by Comp S/U of Core Spray E,N,S 4 System IAW OP-151-001 (51.0P.1934.101)
e. Placing RHRSW l/S for Suppression Pool Cooling A,D,S 5 (16.0P.1354.151}
f. Implement Placing Alternate TBCCW Pump In Service A,D,S 8 (15.0P.1347.151}
g. Restore Offgas System IAW ON-143-001 E,N,S 9 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Shifting CRD Drive Water Filters (55.0P.2016.001) D,R 1
j. Establish and Maintain Reactor Vessel Level (RCIC)

D,E,R 2 not injecting} from U2 RSDP

)

k. Start Containment Hydrogen Recombiner D,E 9 (73.0P.011.202)

@ 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 / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant  ;::11;::1/;::1 (EN)gineered safety feature - I - I <::1 (control room system)

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

(R)CA  ;::1/<::1/<::1 (S)imulator

Appendix D Scenario Outline Form ES-D-1

'\

Op-Test No.: LOC26R Facility: SSES Units 1 and 2 Scenario No.:

Examiners: Operators:

Initial Conditions Unit 1 87% power after control rod pattern adjustment, EOL EHC pump 1 B OOS for maintenance Turnover Raise power to 95% using recirc flow Event Malf. Event Event No. No. Type* Description R Raise Power with Recirc Flow per RMR 1 N/A SRO,ATC OP-164-002, OP-AD-338 cmfRL01_X c SLC Squib Valve Continuity Loss 2 YC411M600 SRO B AR-107-A03, Technical Specifications cmfRL02_E 111K11A c RHR Pump 1B Spurious Start and Suction Flange Leak 3 mfRH14900 SRO,BOP 4B ON-169-002, E0-100-104, Technical Specifications c Main Generator Auto Voltage Regulator Failure 4 aiHS10001 SRO,ATC ON-198-001 mfHP15200 HPCI Steam Leak into Reactor Building, HPCI Fails to 9

5 M Automatically Isolate cmfMV06 HV ALL 155F002(3) E0-100-113 HPCI Isolation Valve Power Loss When Manual Closure 6 cmfMV01 HV I Attempted 155F002(3)

SRO,BOP E0-100-104, E0-100-112 cmfPM04_1 I HPCI Room Coolers Fail to Automatically Start 7 V209A(B) SRO,BOP E0-100-104 mfTC19302 c Four Turbine Bypass Valves Fail Closed 8 3B(C)(D)(E) SRO,ATC E0-100-102 mfHP15200 M HPCI Steam Leak in Second Area of Reactor Building 9 3 ALL E0-100-104, E0-100-112

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

Scenario Actual Target Quantitative Attributes (Per Scenario; See Section 0.5.d)

Events Attributes

1. Total malfunctions (5-8) 2,3,4,5,6,7,8,9 8
2. Malfunctions after EOP entry (1-2) 6,7,8 3
3. Abnormal events (2-4) 3,4 2
4. Major transients (1-2) 5,9 2
5. EOPs entered/requiring substantive actions (1-2) E0-100-102 2

E0-100-104

6. EOP contingencies requiring substantive actions (0-2) E0-100-112 1
7. Critical tasks (2-3) 2 CT-1 Manually scram the reactor when any Secondary Containment Area temperature approaches or exceeds Max Safe temperature.

CT-2 Rapidly depressurize the reactor when two Secondary Containment Areas exceed Max Safe Temperature levels.

Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Op-Test No.:

LOC26R Scenario No.:

Examiners: Operators:

Initial Conditions Unit 1100% power, EOL CRD pump B out of service for maintenance Turnover None Event Malf. Event Event

o. No. Type* Description Power Reduction Due to Minimum Generation 1 Report R Emergency Notification SRO,ATC Ol-AD-029, G0-100-012 rfRR164018 I Reactor Recirculation Pump 1B Speed Drifts Low 2 SRO,ATC rfRR164020 OP-164-001, ON-156-001, Technical Specifications 3 mfRD15500 52239 c One Control Rod Drifts Out SRO,ATC ON-155-001, Technical Specifications 4 mfRR16401 1A c Coolant Leak in Drywell ALL ON-100-101, E0-100-102, E0-100-103 mfRP15800 4A{B)(C)(D) .M Electrical ATWS 5 ALL mfRP15800 E0-100-102, E0-100-113 3

cmfPM05_1 6

P208A(B) c SLC Pump Shaft Shear, CRD Pump Trip cmfPM03_1 SRO,BOP E0-100-113 P132A mfEG19800 7

4 c Main Generator Trip, Loss of All Condensate Pumps mfFW14400 ALL E0-100-113 3A(B)(C)(D) mfRC15001 HPCI and RCIC Trip, Coolant Leak in Drywell Degrades, 1

ADS Fails to Automatically Initiate; Rapid 8 mfHP15201 M Depressurization Required Due to Low Reactor Water 5 ALL Level mfAD18300 1 E0-100-102, E0-100-112

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

Scenario Actual Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Events Attributes

1. Total malfunctions (5-8) 2,3,4,5,6,7,8 7
2. Malfunctions after EOP entry (1-2) 6,7 2
3. Abnormal events (2-4) 2,3,4 3
4. Major transients (1-2) 5,8 2
5. EOPs entered/requiring substantive actions (1-2) E0-100-102 2

E0-100-103

6. EOP contingencies requiring substantive actions (0-2) E0-100-112 2

E0-100-113

7. Critical tasks (2-3) 3 CT-1 Lower Reactor power using one or more of the following methods IAW E0-100-113:
  • Trip Recirculation pumps

CT-3 Perform Rapid Depressurization when RPV level drops to -161" IAW E0-100-102.

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