ML15126A266

Susquehanna - Final Outlines (Folder 3)

ML15126A266
Person / Time
Site:	Susquehanna
Issue date:	01/19/2015
From:	Susquehanna
To:	Fish T H Operations Branch I
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ML14350A011	List: ML15014A270 ML15049A349 ML15049A350 ML15126A262 ML15126A263 ML15126A264 ML15126A265 ML15126A266 ML15128A470
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TAC U01933
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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 1 2 3 4 5 6 1 2 3 4

• Total A2 G* Total . 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 . . Evolutions Tier 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. 2 2 1 Plant 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, I Rs, 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)

AA2.07 -Ability to determine and/or 295005 Main Turbine Generator x interpret the following as they apply to Trip/ 3 MAIN TURBINE GENERATOR TRIP: Reactor water level AA2.10 -Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and x GENERATOR VOLTAGE AND Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:

Generator overheating and the required actions EA2.06 -Ability to determine and/or 295028 High Drywell interpret the following as they apply to x HIGH DRYWELL TEMPERATURE:

Temperature I 5 Torus/suppression chamber air space temperature:

Plant-Specific 295021 Loss of Shutdown x 2.4.11 -Knowledge of abnormal Coolina 14 condition procedures.

295030 Low Suppression Pool 2.1.25 -Ability to interpret reference x materials, such as graphs, curves, Water Level I 5 tables, etc. 295024 High Drywell Pressure I x 2.4.6 -Knowledge of EOP mitigation 5 strategies.

295003 Partial or Complete x 2.1.20 -Ability to interpret and execute Loss of AC Power I 6 procedure steps. EK2.01 -Knowledge of the interrelations 295026 Suppression Pool High x between SUPPRESSION POOL HIGH Water Temperature I 5 WATER TEMPERATURE and the following:

Suppression pool cooling EK1 .03 -Knowledge of the operational 295030 Low Suppression Pool x implications of the following concepts as Water Level I 5 they apply to LOW SUPPRESSION POOL WATER LEVEL: Heat capacity AK1 .01 -Knowledge of the operational implications of the following concepts as 295018 Partial or Complete x they apply to PARTIAL OR COMPLETE Loss of CCW I 8 LOSS OF COMPONENT COOLING WATER: Effects on component/system operations AK2.02 -Knowledge of the interrelations 295005 Main Turbine Generator x between MAIN TURBINE GENERATOR Trip/ 3 TRIP and the following:

Feedwater temperature 295024 High Drywell Pressure I EK2.18 -Knowledge of the interrelations x between HIGH DRYWELL PRESSURE 5 and the following:

Ventilation AK2.07 -Knowledge of the interrelations 295006 SCRAM I 1 x between SCRAM and the following:

Reactor pressure control EK3.04 -Knowledge of the reasons for 295038 High Off-site Release x the following responses as they apply to Rate/ 9 HIGH OFF-SITE RELEASE RATE: 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:

Circulation/ 1 & 4 Idle loop flow Imp. Q# 3.6 76 3.8 77 3.7 78 4.2 79 4.2 80 4.7 81 4.6 82 3.9 39 3.8 40 3.5 41 2.9 42 3.3 43 4.0 44 3.6 45 2.8 46 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)

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

Drywell pressure EA 1.01 -Ability to operate and/or 295037 SCRAM Condition monitor the following as they apply to Present and Reactor Power x SCRAM CONDITION PRESENT AND Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown/

1 DOWNSCALE OR UNKNOWN:

Reactor Protection System AA 1.08 -Ability to operate and/or 295023 Refueling Accidents I 8 x monitor the following as they apply to REFUELING ACCIDENTS:

Radiation 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 and control systems to be maintained and operated during a fire AA2.06 -Ability to determine and/or 295016 Control Room x interpret the following as they apply to Abandonment I 7 CONTROL ROOM ABANDONMENT:

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

VARs outside capability curve 295025 High Reactor Pressure I x 2.2.40 -Ability to apply technical 3 specifications for a svstem. 2.4.9 -Knowledge of low power I 295004 Partial or Complete shutdown implications in accident (e.g., x loss of coolant accident or loss of Loss of DC Power I 6 residual heat removal) mitigation strategies.

295019 Partial or Complete 2.4.50 -Ability to verify system alarm x setpoints and operate controls identified Loss of Instrument Air I 8 in the alarm response manual. AA 1.02 -Ability to operate and/or 295021 Loss of Shutdown x monitor the following as they apply to Cooling/

4 LOSS OF SHUTDOWN COOLING:

RHR/shutdown cooling EK3.02 -Knowledge of the reasons for 295031 Reactor Low Water x the following responses as they apply to Level/ 2 REACTOR LOW WATER LEVEL: Core coverage KIA Category Totals: 2 4 4 4 3/3 3/4 Group Point Total: Imp. Q# 3.5 47 3.9 48 4.6 49 3.4 50 3.0 51 3.3 52 3.6 53 3.4 54 3.8 55 4.2 56 3.5 57 4.4 58 I 2017 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)

EA2.01 -Ability to determine and/or 295029 High Suppression Pool x interpret the following as they apply to Water Level I 5 HIGH SUPPRESSION POOL WATER 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 x reported to internal organizations or 5 external

agencies, such as the state, the NRC, or the transmission system operator.

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

Area/room coolers AK3.07 -Knowledge of the reasons for 2950201nadvertent the following responses as they apply to Containment Isolation I 5 & 7 x INADVERTENT CONTAINMENT ISOLATION:

Suppression pool temperature response AA 1.01 -Ability to operate and/or 295002 Loss of Main x monitor the following as they apply to Condenser Vacuum I 3 LOSS OF MAIN CONDENSER VACUUM: Condensate system AA2.01 -Ability to determine and/or 295010 High Drywell Pressure I x interpret the following as they apply to 5 HIGH DRYWELL PRESSURE:

Leak rates 295014 Inadvertent Reactivity x 2.1.32 -Ability to explain and apply all Addition/

1 system limits and precautions.

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

KIA Category Totals: 1 1 1 1 1/2 2/1 Group Point Total: Imp. Q# 3.9 83 4.1 84 4.2 85 3.2 59 3.5 60 3.4 61 2.6 62 3.4 63 3.8 64 4.2 65 I 7/3 ES-401 System # I Name K K K 1 2 3 209001 LPCS 262001 AC Electrical Distribution 400000 Component Cooling Water 215005 APRM I LPRM 239002 SRVs 263000 DC Electrical x Distribution 215004 Source Range x Monitor 259002 Reactor Water Level Control 239002 SRVs x Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 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 x on those predictions, use procedures to correct,

control, or 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 x on those predictions, use procedures to correct,

control, or mitigate the consequences of those abnormal conditions or operations:

De-energizing a plant bus 2.1.28 -Knowledge of the x purpose and function of major system components and controls.

x 2.4.18 -Knowledge of the specific bases for EOPs. A2.04 -Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, x use procedures to correct,

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 between D.C. ELECTRICAL DISTRIBUTION and the following:

Battery charger and battery K1 .01 -Knowledge of the physical connections and/or cause-effect relationships between SOURCE RANGE MONITOR (SRM) SYSTEM and the following:

Reactor protection system A 1.02 -Ability to predict and/or monitor changes in parameters x associated with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including:

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

SRV solenoids Imp. Q# 3.6 86 2.9 87 4.1 88 4.0 89 4.1 90 3.2 1 3.6 2 3.6 3 2.8 4 ES-401 System #I Name K K K 1 2 3 262002 UPS (AC/DC) x 261000 SGTS x 400000 Component Cooling Water 209001 LPCS 262001 AC Electrical Distribution 217000 RCIC 205000 Shutdown Cooling 218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 K3.07 -Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)

will have on following:

Movement of control rods: Plant-Specific K3.06 -Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following:

Primary containment oxygen content:

Mark-1&11 K4.01 -Knowledge of CCWS design feature(s) and or x interlocks which provide for the following:

Automatic start of standby pump K4.05 -Knowledge of LOW PRESSURE CORE SPRAY x SYSTEM design feature(s) and/or interlocks which provide for the following:

Pump minimum flow K5.02 -Knowledge of the operational implications of the x following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION:

Breaker control K5.02 -Knowledge of the operational implications of the following concepts as they apply x to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): Flow indication K6.05 -Knowledge of the effect that a loss or malfunction of the following will have on the x SHUTDOWN COOLING 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 x AUTOMATIC 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 x ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including:

SPDS/ERIS/CRIDS/GDS:

Plant-Specific Imp. Q# 2.6 5 3.0 6 3.4 7 2.6 8 2.6 9 3.1 10 3.2 11 3.0 12 2.5 13 ES-401 System # I Name K K K 1 2 3 211000 SLC 215005 APRM I LPRM 264000 EDGs 203000 RHR/LPCI:

Injection Mode 215003 IRM 206000 HPCI 300000 Instrument Air 212000 RPS 211000 SLC Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 A 1.08 -Ability to predict and/or monitor changes in parameters x associated with operating the STANDBY LIQUID CONTROL 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; x and (b) based on those predictions, use procedures to 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 x procedures to correct,

control, or 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 x RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) including:

Reactor water level A3.03 -Ability to monitor automatic operations of the x INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including:

RPS status A4.06 -Ability to manually x operate and/or monitor in the control room: Reactor pressure:

BWR-2,3,4 A4.01 -Ability to manually x operate and/or monitor in the control room: Pressure gauges 2.4.34 -Knowledge of RO tasks performed outside the main x control room during an emergency and the resultant operational effects.

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

Imp. Q# 3.7 14 3.6 15 3.6 16 4.4 17 3.7 18 4.3 19 2.6 20 4.2 21 4.3 22 ES-401 System # I Name K K K 1 2 3 261000 SGTS 400000 Component Cooling Water 262001 AC Electrical Distribution 263000 DC Electrical Distribution KIA Category Totals: 2 1 2 Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A 4 5 6 1 3 4 G K4.04 -Knowledge of STANDBY GAS TREATMENT x SYSTEM design feature(s) and/or interlocks which provide for the following:

Radioactive particulate filtration K6.07 -Knowledge of the effect that a loss or malfunction of the x following will have on the CCWS: Breakers, relays, and disconnects A4.05 -Ability to manually operate and/or monitor in the x control room: Voltage,

current, power, and frequency on A.C. buses K5.01 -Knowledge of the operational implications of the following concepts as they apply x to D.C. ELECTRICAL DISTRIBUTION:

Hydrogen generation during battery charaing.

3 3 3 3 2/3 2 3 2/2 Group Point Total: Imp. Q# 2.7 23 2.7 24 3.3 25 2.6 26 I 26/5 ES-401 K K K System #I Name 1 2 3 239001 Main and Reheat Steam 230000 RHR/LPCI:

Torus/Pool Spray Mode 271000 Off-gas 241000 Reactor/Turbine x Pressure Regulator 239001 Main and Reheat x Steam 230000 RHR/LPCI:

x Torus/Pool Spray Mode 215002 RBM 201001 CRD Hydraulic 290003 Control Room HVAC 233000 Fuel Pool Cooling/Cleanup Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 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 x procedures to correct,

control, 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 x emergency action level thresholds and classifications.

x 2.2.12 -Knowledge of surveillance procedures.

K1 .04 -Knowledge of the physical connections and/or cause-effect relationships between REACTOR/TURBINE PRESSURE REGULATING SYSTEM and the following:

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

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

TORUS/SUPPRESSION POOL SPRAY MODE will have on following:

Suppression pool temperature K4.01 -Knowledge of ROD BLOCK MONITOR SYSTEM x design feature(s) and/or interlocks which provide for the following:

Prevent control rod withdrawal:

BWR-3,4,5 K5.02 -Knowledge of the operational implications of the x following concepts as they apply to CONTROL ROD DRIVE HYDRAULIC SYSTEM: Flow indication K6.02 -Knowledge of the effect that a loss or malfunction of the x following will have on the CONTROL ROOM HVAC: Component cooling water systems A 1.02 -Ability to predict and/or monitor changes in parameters x associated with operating the FUEL POOL COOLING AND CLEAN-UP controls including:

Pool level Imp. Q# 3.9 91 4.6 92 4.1 93 3.7 27 3.2 28 3.3 29 3.4 30 2.6 31 2.7 32 2.9 33 ES-401 System # I Name K K K 1 2 3 201003 Control Rod and Drive Mechanism 201002 RMCS 214000 RPIS 204000 RWCU 286000 Fire Protection x KIA Category Totals: 2 1 1 Form ES-401-1 SSES 2015 Retake Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 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) x based on those predictions, use procedures to correct,

control, 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 x REACTOR MANUAL CONTROL SYSTEM including:

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

K1.08 -Knowledge of the physical connections and/or cause-effect relationships between FIRE PROTECTION SYSTEM and the following:

Intake canals: Plant-Specific 1 1 1 1 1/1 1 1 1/2 Group Point Total: Imp. Q# 3.8 34 3.2 35 3.8 36 3.8 37 3.0 38 I 12/3 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 2.1.7 make operational judgments based on 4.7 100 operating characteristics, reactor behavior, and instrument interpretation.

1. Conduct of Operations 2.1.2 Knowledge of operator responsibilities during 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 2.2.5 Knowledge of the process for making design 3.2 95 or operatinq chanqes to the facility.

2.2.7 Knowledge of the process for conducting 3.6 99 special or infrequent tests. 2. Equipment 2.2.43 Knowledge of the process used to track 3.0 68 Control inoperable alarms 2.2.35 Ability to determine Technical Specification 3.6 69 Mode of Operation.

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

filters, etc. 3. Knowledge of radiation or containment hazards that may arise during normal, Radiation 2.3.14 abnormal, or emergency conditions or 3.8 98 Control activities.

Ability to use radiation monitoring

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

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 2.3.4 Knowledge of radiation exposure limits under 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 2.4.1 Knowledge of EOP entry conditions and 4.6 72 Procedures I immediate action steps. Plan 2.4.13 Knowledge of crew roles and responsibilities 4.0 73 during EOP usage. Subtotal

• . 2 1 Tier 3 Point Total 10 7 ES-401 1 / 1 1 / 2 2 / 1 2 / 1 212 212 212 Record of Rejected Kl As Form ES-401-4 Randomly Selected KIA 295027 High Containment Temperature 295011 High Containment Temperature 207000 Isolation (Emergency)

Condenser 209002 HPCS 201004 RSCS 201005 RCIS 239003 MSIV Leakage Control Reason for Rejection This topic applies to plants with Mark Ill containments only. The facility has a Mark II containment.

This topic applies to plants with Mark 111 containments only. The facility has a Mark II containment.

This system is not installed at the facility.

This system is not installed at the facility.

This system is no longer installed at the facility.

This system is not installed at the facility.

This system is no longer installed at the facility.

1 / 1 1 / 2 1 / 2 2 / 1 Question 50 295023 Refueling Accidents AA 1.08 -Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS:

Containment building ventilation:

Mark-Ill Question 85 295014 Inadvertent Reactivity Addition AA2.03 -Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION:

Cause of reactivity addition Question 63 295010 High Drywell Pressure AA2.05 -Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:

Drywell air cooler drain flow: BWR-6 Question 89 215005 APRM I LPRM 2.4.34 -Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.

Randomly resampled KJA 295023 Refueling Accidents AA 1.04 -Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS:

Radiation monitoring equipment.

A discriminating SRO-level question cannot be developed for the randomly sampled KJA. Additionally, this topic is oversampled (Questions 64 and 85). Randomly resampled KJA 295015 Incomplete SCRAM AA2.02 -Ability to determine and/or interpret the following as they apply to INCOMPLETE SCRAM: Control rod position.

The facility is a BWR-4, not a BWR-6. Randomly resampled KJA 295010 High Drywell Pressure AA2.01 -Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:

Leak rates. The randomly sampled generic KJA does not support developing an SRO-level question for the given system. Randomly resampled KJA 215005 APRM I LPRM 2.4.18 -Knowledge of the specific bases for EOPs.

Question 3 The facility does not have a Feedwater coolant 259002 Reactor Water Level injection mode for the Feedwater system. Control Randomly resampled KIA 259002 Reactor Water Level Control A 1.02 -Ability to predict K2.02 -Knowledge of electrical and/or monitor changes in parameters 2 / 1 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 215005 APRM I LPRM randomly sampled KIA without overlapping 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; MONITOR SYSTEM; and (b) based on those 2 / 1 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 control room: Control rod position.

212 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; 2 / 1 (b) based on those predictions, 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 2.2.41 -Ability to obtain and could not be developed at the RO license level 3 interpret station electrical and for the randomly sampled KIA. 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 2.2.40 -Ability to apply tested on Question

54. Resampling to limit technical specifications for a overlap.

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 2.4.41 -Knowledge of the at the RO license level for the randomly emergency action level sampled KIA. 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 295026 Suppression Pool High for the randomly sampled KIA without testing Water Temperature Generic Fundamentals material.

EK1 .02 -Knowledge of the Randomly resampled KIA 295026 Suppression Pool High Water Temperature EK2.01 -1 / 1 operational implications of the 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 271000 Off-gas for the randomly sampled generic KIA due to a 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* Conduct of Operations S,D Compute Average Drywell Air Temperature 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) Equipment Control R,D Authorize Bypassing Rod Block Monitor 00.AD.1021.101 NDAP-QA-0338, KIA 2.1.37 (4.6) Radiation Control R,D Review and Approve Rad Liq Release Permit OO.AD.2175.001 OP-069-050, KIA 2.3.6 (3.7) Emergency Procedures/Plan R,M Classify an Emergency Condition 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 a. Respond to Multiple Notching Rod (55.0N.2003.151)

b. HPCI Full Flow Test Quarterly Surveillance

( 52.S0.1964.151}

c. Main Steam Line Isolation Recovery (84.0N.003.101}

d. Perform Manual Comp by Comp S/U of Core Spray System IAW OP-151-001 (51.0P.1934.101)

e. Placing RHRSW l/S for Suppression Pool Cooling (16.0P.1354.151}

f. Implement Placing Alternate TBCCW Pump In Service (15.0P.1347.151}

g. Restore Offgas System IAW ON-143-001 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)

j. Establish and Maintain Reactor Vessel Level (RCIC) not injecting}

from U2 RSDP ) k. Start Containment Hydrogen Recombiner (73.0P.011.202)

Type Code* A,D,S A,D,S D,L,S E,N,S A,D,S A,D,S E,N,S D,R D,E,R D,E Safety Function 1 2 3 4 5 8 9 1 2 9 @ 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 Facility:

SSES Units 1 and 2 Scenario No.: 1 Op-Test No.: LOC26R --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 1 N/A R Raise Power with Recirc Flow per RMR SRO,ATC OP-164-002, OP-AD-338 cmfRL01_X c SLC Squib Valve Continuity Loss 2 YC411M600 B SRO AR-107-A03, Technical Specifications cmfRL02_E c RHR Pump 1 B Spurious Start and Suction Flange Leak 3 111K11A mfRH14900 SRO,BOP ON-169-002, E0-100-104, Technical Specifications 4B 4 aiHS10001 c Main Generator Auto Voltage Regulator Failure SRO,ATC ON-198-001 mfHP15200 HPCI Steam Leak into Reactor Building, HPCI Fails to 9 M 5 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 7 cmfPM04_1 I HPCI Room Coolers Fail to Automatically Start V209A(B)

SRO,BOP E0-100-104 8 mfTC19302 c Four Turbine Bypass Valves Fail Closed 3B(C)(D)(E)

SRO,ATC E0-100-102 9 mfHP15200 M HPCI Steam Leak in Second Area of Reactor Building 3 ALL E0-100-104, E0-100-112

• (N)ormal, ( R )eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section 0.5.d) 1. Total malfunctions (5-8) 2. Malfunctions after EOP entry (1-2) 3. Abnormal events (2-4) 4. Major transients (1-2) 5. EOPs entered/requiring substantive actions (1-2) 6. EOP contingencies requiring substantive actions (0-2) 7. Critical tasks (2-3) 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. Scenario Actual Events Attributes 2,3,4,5,6,7,8,9 8 6,7,8 3 3,4 2 5,9 2 E0-100-102 2 E0-100-104 E0-100-112 1 2 Appendix D Scenario Outline Form ES-D-1 Facility:

SSES Units 1 and 2 Scenario No.: 2 Op-Test No.: LOC26R --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 1 B Speed Drifts Low 2 rfRR164020 SRO,ATC OP-164-001, ON-156-001, Technical Specifications 3 mfRD15500 c One Control Rod Drifts Out 52239 SRO,ATC ON-155-001, Technical Specifications 4 mfRR16401 c Coolant Leak in Drywell 1A ALL ON-100-101, E0-100-102, E0-100-103 mfRP15800 5 4A{B)(C)(D)

.M Electrical ATWS mfRP15800 ALL E0-100-102, E0-100-113 3 cmfPM05_1 P208A(B) c SLC Pump Shaft Shear, CRD Pump Trip 6 cmfPM03_1 SRO,BOP E0-100-113 P132A mfEG19800 4 c Main Generator Trip, Loss of All Condensate Pumps 7 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 Target Quantitative Attributes (Per Scenario; See Section D.5.d) 1. Total malfunctions (5-8) 2. Malfunctions after EOP entry (1-2) 3. Abnormal events (2-4) 4. Major transients (1-2) 5. EOPs entered/requiring substantive actions (1-2) 6. EOP contingencies requiring substantive actions (0-2) 7. Critical tasks (2-3) CT-1 Lower Reactor power using one or more of the following methods IAW E0-100-113:

• Trip Recirculation pumps

• Inject boron

• Lower Reactor water level CT-2 Insert control rods IAW E0-100-113 Sht. 2. CT-3 Perform Rapid Depressurization when RPV level drops to -161" IAW E0-100-102.

Scenario Actual Events Attributes 2,3,4,5,6,7,8 7 6,7 2 2,3,4 3 5,8 2 E0-100-102 2 E0-100-103 E0-100-112 2 E0-100-113 3