ML20058H622

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GG-2020-02 Final Outlines
ML20058H622
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 02/10/2020
From: Greg Werner
Operations Branch IV
To:
Entergy Operations
References
Download: ML20058H622 (35)
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ES-401 BWR Examination Outline Form ES-401-1 Facility: Grand Gulf Nuclear Station Date of Exam: February 2020 Tier Group RO K/A Category Points SRO-Only Points 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 4 4 3 3 3 3 20 4 3 7 Emergency & N/A N/A 2 1 1 1 1 1 2 7 1 2 3 Abnormal Plant Evolutions Tier Totals 5 5 4 4 4 5 27 5 5 10 1 3 3 2 2 2 2 2 2 2 3 3 26 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 Categories 10 2 3 2 3 2 1 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. 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 K/A 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 K/As having an importance rating (IR) of 2.5 or higher. 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 K/A categories.
7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A 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 K/As.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics 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 a category 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

  • These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

Rev 1

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)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

2.2.22 Knowledge of limiting conditions for operations 4.0 1 295001 Partial or Complete Loss of Forced and safety limits.

Core Flow Circulation / 1 & 4 AK3.05 Knowledge of the reasons for the following responses or actions as they apply to partial or complete 3.7 2 295003 Partial or Complete Loss of AC / 6 loss of AC power: AK3.05 Reactor SCRAM AA1.03 Ability to operate and/or monitor the following as 3.4 3 295004 Partial or Total Loss of DC Pwr / 6 they apply to PARTIAL OR COMPLETE LOSS OF D.C.

POWER : A.C. electrical distribution AA2.04 Ability to determine and/or interpret the following 3.7 4 295005 Main Turbine Generator Trip / 3 as they apply to MAIN TURBINE GENERATOR TRIP :

Reactor Pressure AK1.02 Knowledge of the operational implications of the 3.4 5 295006 SCRAM / 1 following concepts as they apply to SCRAM : Shutdown Margin AK2.02 Knowledge of the interrelations between 4.0 6 295016 Control Room Abandonment / 7 CONTROL ROOM ABANDONMENT and the following:

Local control stations AA2.02Ability to determine and/or interpret the following 3.1 7 295018 Partial or Total Loss of CCW / 8 as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Cooling Water Temperatures AK2.09 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR 3.3 8 295019 Partial or Total Loss of Inst. Air / 8 and the following: Containment AK3.01 Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN 3.3 9 295021 Loss of Shutdown Cooling / 4 COOLING : Raising reactor water level 2.4.41 Knowledge of the emergency action level 2.9 10 295023 Refueling Acc / 8 thresholds and classifications EA1.05 Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE: RPS 3.9 11 295024 High Drywell Pressure / 5 EK1.03 Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR 3.6 12 295025 High Reactor Pressure / 3 PRESSURE : Safety/relief valve tailpipe Temperature/pressure relationships EK3.04 Knowledge of the reasons for the following 3.7 13 295026 Suppression Pool High Water Temp. / responses as they apply to SUPPRESSION POOL HIGH 5 WATER TEMPERATURE: SBLC injection EK1.03 Knowledge of the operational implications of the following concepts as they apply to HIGH 3.8 14 295027 High Containment Temperature / 5 CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) : Containment integrity: Mark-III EK3.04 Knowledge of the reasons for the following 3.6 15 295028 High Drywell Temperature / 5 responses as they apply to HIGH DRYWELL TEMPERATURE : Increased drywell cooling EK2.08 Knowledge of the interrelations between LOW 3.5 16 295030 Low Suppression Pool Wtr Lvl / 5 SUPPRESSION POOL WATER LEVEL and the following: SRV discharge submergence 2.4.3 Ability to identify post-accident instrumentation 3.7 17 295031 Reactor Low Water Level / 2 EA2.03 Ability to determine and/or interpret the following 4.3 18 295037 SCRAM Condition Present and as they apply to SCRAM CONDITION PRESENT AND Reactor Power Above APRM Downscale or REACTOR POWER ABOVE APRM DOWNSCALE OR Unknown / 1 UNKNOWN : SBLC tank level Rev 1

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

EK2.10 Knowledge of the interrelations between HIGH 3.2 19 295038 High Off-site Release Rate / 9 OFF-SITE RELEASE RATE and the following:

Condenser air removal system 600000 Plant Fire On Site / 8 AK1.01 Knowledge of the operational implications of the l 3.3 20 700000 Generator Voltage and Electric Grid following concepts as they apply to GENERATOR Disturbances / 6 VOLTAGE AND ELECTRIC GRID DISTURBANCES:

Definition of terms: volts, watts, amps, VARs, power factor K/A Category Totals: 4 4 3 3 3 3 Group Point Total: 20 Rev 1

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 AA1.06 Ability to operate and/or monitor the following 2.8 21 as they apply to HIGH REACTOR WATER LEVEL :

HPCS 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 AK1.03 Knowledge of the operational implications of 3.2 22 the following concepts as they apply to HIGH DRYWELL PRESSURE : Temperature Increases 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. /

5 295014 Inadvertent Reactivity Addition /

1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & AK3.03 Knowledge of the reasons for the following 3.2 23 7 responses as they apply to INADVERTENT CONTAINMENT ISOLATION: Drywell/containment temperature response 295022 Loss of CRD Pumps / 1 EA2.03 Ability to determine and/or interpret the 295029 High Suppression Pool Wtr Lvl / 3.4 24 following as 5 they apply to HIGH SUPPRESSION POOL WATER LEVEL: Drywell/containment water level 295032 High Secondary Containment 2.4.47 Ability to diagnose and recognize trends in an 4.2 25 Area Temperature / 5 accurate and timely manner utilizing the appropriate control room reference material.

295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High EK2.01 Knowledge of the interrelations between 3.6 26 Differential Pressure / 5 SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE and the following:

Secondary containment ventilation 295036 Secondary Containment High 2.1.30 Ability to locate and operate components, 4.4 27 Sump/Area Water Level / 5 including local controls.

500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 1 1 1 1 1 2 Group Point Total: 7 Rev 1

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

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 A2.03 Ability to (a) predict the impacts of the following 3.2 28 on the RHR/LPCI: INJECTION MODE (PLANT 203000 RHR/LPCI: Injection Mode SPECIFIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: valve Closures K3.01 Knowledge of the effect that a loss or 3.3 29 malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following: Reactor Pressure _ _

205000 Shutdown Cooling K6.08 Knowledge of the effect that a loss or malfunction of the following will have on the 3.5 30 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) : RHR Service Water 206000 HPCI 20700 Isol Condenser K5.05Knowledge of the operational implications of the 2.5 31 following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM : System Venting 209001 LPCS 2.2.40 Ability to apply Technical Specifications for a system. 3.4 32 K5.04 Knowledge of the operational implications of the 3.8 33 following concepts as they apply to HIGH PRESSURE CORE SPRAY SYSTEM (HPCS): Adequate core cooling 209002 HPCS K1.02 Knowledge of the physical connections and/or cause effect relationships between HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) and the following: 3.5 53 Suppression Pool: BWR-5,6 A1.06 Ability to predict and/or monitor changes in 3.8 34 211000 SLC parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: Flow Indication K3.02 Knowledge of the effect that a loss or 3.7 35 malfunction of the REACTOR PROTECTION SYSTEM will have on following: Primary containment isolation system/nuclear steam supply shut-off: Plant-Specific __ __

212000 RPS A4.08 Ability to manually operate and/or monitor in thecontrol room: Individual system relay status 3.4 36 K2.01 Knowledge of electrical power supplies to the 2.5 37 215003 IRM following: IRM channels/detectors K4.04 Knowledge of SOURCE RANGE MONITOR 2.8 38 215004 Source Range Monitor (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following: Changing detector position Rev 1

ES-401 6 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 K2.02 Knowledge of electrical power supplies to the 2.6 39 following: APRM Channels __ __

215005 APRM / LPRM A4.04 Ability to manually operate and/or monitor in the control room: LPRM back panel switches, meters and indicating lights 3.2 40 2.4.34 Knowledge of RO tasks performed outside the 4.2 41 217000 RCIC main control room during an emergency and the resultant operational effects.

A1.01 Ability to predict and/or monitor changes in 3.4 42 218000 ADS parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including: ADS valve tail pipe temperatures K1.14 Knowledge of the physical connections and/or 2.8 43 223002 PCIS/Nuclear Steam causeeffect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR Supply Shutoff STEAM SUPPLY SHUT-OFF and the following:

Containment drainage system K4.02 Knowledge of RELIEF/SAFETY VALVES design 3.4 44 feature(s) and/or interlocks which provide for the 239002 SRVs following: Minimizes containment fatigue duty cycles resulting from relief valve cycling during decay-heat-dominant period late in an isolation transient (LLS logic)

A3.04 Ability to monitor automatic operations of the 3.2 45 259002 Reactor Water Level REACTOR WATER LEVEL CONTROL SYSTEM Control including: Changes in reactor feedwater flow K1.08 Knowledge of the physical connections and/or 2.8 46 cause effect relationships between STANDBY GAS 261000 SGTS TREATMENT SYSTEM and the following: Process radiation monitoring system 2.4.21 Knowledge of the parameters and logic used to 4.0 47 assess the status of safety functions, such as reactivity 262001 AC Electrical Distribution control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

K6.03 Knowledge of the effect that a loss or 2.7 48 262002 UPS (AC/DC) malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) :

Static inverter K2.01 Knowledge of electrical power supplies to the 3.1 49 263000 DC Electrical Distribution following: Major D.C. loads A2.01 Ability to (a) predict the impacts of the following 3.5 50 on the EMERGENCY GENERATORS (DIESEL/JET) ;

and (b) based on those predictions, use procedures to 264000 EDGs correct, control, or mitigate the consequences of those abnormal conditions or operations: Parallel operation of emergency generator Rev 1

ES-401 7 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 A4.01 Ability to manually operate and / or monitor in 2.6 51 300000 Instrument Air the control room: Pressure Gauges A3.01 Ability to monitor automatic operations of the 3.0 52 CCWS including: Setpoints on instrument signal levels 400000 Component Cooling Water for normal operations, warnings, and trips that are applicable to the CCWS 510000 (SF4 SWS*) Service Water (Normal and Emergency)

K/A Category Point Totals: 3 3 2 2 2 2 2 2 2 3 3 Group Point Total: 26 Rev 1

ES-401 8 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

System # / Name K K K K K K A A A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic K4.08 Knowledge of CONTROL ROD DRIVE 3.1 54 HYDRAULIC SYSTEM design feature(s) and/or interlocks which provide for the following: Controlling control rod drive header pressure 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS K3.01 Knowledge of the effect that a loss or 3.3 57 malfunction of the ROD CONTROL AND INFORMATION SYSTEM (RCIS) will have on following: Control rod drive system: BWR-6 201006 RWM 202001 Recirculation K1.15 Knowledge of the physical connections 3.2 55 and/or cause effect relationships between RECIRCULATION SYSTEM and the following:

Nuclear boiler instrumentation (reactor water level/pressure) 202002 Recirculation Flow Control K6.06 Knowledge of the effect that a loss or 3.1 56 malfunction of the following will have on the RECIRCULATION FLOW CONTROL SYSTEM :

Reactor water level 204000 RWCU 214000 RPIS 215001 Traversing In-Core Probe 215002 RBM 216000 Nuclear Boiler Inst. A1.02 Ability to predict and/or monitor changes in 2.9 58 parameters associated with operating the NUCLEAR BOILER INSTRUMENTATION controls including: Removing or returning a sensor (transmitter) to service 219000 RHR/LPCI: Torus/Pool Cooling 2.4.49 Ability to perform without reference to 4.6 65 Mode procedures those actions that require immediate operation of system components and controls.

223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode K2.02 Knowledge of electrical power supplies to 2.9 59 the following: Pumps 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator Rev 1

ES-401 9 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

System # / Name K K K K K K A A A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 245000 Main Turbine Gen. / Aux. A4.01 Ability to manually operate and/or monitor 2.7 60 in the control room: Turbine Lube Oil Pumps 256000 Reactor Condensate K4.08 Knowledge of REACTOR CONDENSATE 3.6 61 SYSTEM design feature(s) and/or interlocks which provide for the following: Dedicated ECCS water supply 259001 Reactor Feedwater K5.03 Knowledge of the operational implications 2.8 62 of the following concepts as they apply to REACTOR FEEDWATER SYSTEM : Turbine operation: TDRFP's-Only 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring A3.06 Ability to monitor automatic operations of 3.4 63 the RADIATION MONITORING SYSTEM including: Ventilation system isolation indications 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals A2.03 Ability to (a) predict the impacts of the 3.6 64 following on the REACTOR VESSEL INTERNALS

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations
Control rod drop accident 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 1 1 2 1 1 1 1 1 1 1 Group Point Total: 12 Rev 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3 - RO) Form ES-401-3 Facility: Grand Gulf Nuclear Station Date of Exam: February 2020 Category K/A # Topic RO SRO-Only IR # IR #

2.1.8 Ability to coordinate personnel activities outside the control room. 3.4 66 2.1.19 Ability to use plant computers to evaluate system or component status. 3.9 67 1.

Conduct of Operations Subtotal 2 2.2.40 Ability to apply Technical Specifications for a system. 3.4 68 2.2.43 Knowledge of the process used to track inoperable alarms. 3.0 69

2. 2.2.44 Ability to interpret control room indications to verify the status and 4.2 70 Equipment operation of a system, and understand how operator actions and Control directives affect plant and system conditions.

Subtotal 3 2.3.11 Ability to control radiation releases. 3.8 71 2.3.14 Knowledge of radiation or contamination hazards that may arise during 3.4 72 normal, abnormal, or emergency conditions or activities.

3.

Radiation Control Subtotal 2 2.4.2 Knowledge of system set points, interlocks and automatic actions 4.5 73 associated with EOP entry conditions.

2.4.29 Knowledge of the emergency plan. 3.1 74 4.

Emergency Procedures / 2.4.45 Ability to prioritize and interpret the significance of each annunciator or 4.1 75 Plan alarm.

Subtotal 3 Tier 3 Point Total 10 Rev 1

ES-401 BWR Examination Outline Form ES-401-1 Facility: Grand Gulf Nuclear Station Date of Exam: February 2020 Tier Group RO K/A Category Points SRO-Only Points 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 4 3 7 Emergency &

2 1 2 3 Abnormal Plant Evolutions Tier Totals 5 5 10 1 3 2 5 2.

Plant 2 2 1 3 Systems Tier Totals 5 3 8

3. Generic Knowledge and Abilities Categories 1 2 3 4 1 2 3 4 7 2 1 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. 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 K/A 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 K/As having an importance rating (IR) of 2.5 or higher. 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 K/A categories.
7. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A 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 K/As.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics 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 a category 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

  • These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

Rev 1

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 (SRO)

K/A Topic(s)

E/APE # / Name / Safety Function K K K A A G* IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 AA2.02 Ability to determine and/or interpret the 4.3 76 295003 Partial or Complete Loss of AC / 6 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER : Reactor power / pressure /

and level 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip / 3 AA2.03 Ability to determine and/or interpret the following as they apply to SCRAM : Reactor Water 4.2 77 295006 SCRAM / 1 Level 295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW / 8 295019 Partial or Total Loss of Inst. Air / 8 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure / 3 EA2.02 Ability to determine and/or interpret the 4.2 78 following as they apply to HIGH REACTOR PRESSURE: Reactor Power 295026 Suppression Pool High Water Temp. / 5 2.2.25 Knowledge of the bases in Technical 4.2 79 295027 High Containment Temperature / 5 Specifications for limiting conditions for operations and safety limits.

295028 High Drywell Temperature / 5 295030 Low Suppression Pool Wtr Lvl / 5 295031 Reactor Low Water Level / 2 EA2.03 Ability to determine and/or interpret the 4.2 80 following as they apply to REACTOR LOW WATER LEVEL : Reactor Pressure 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 2.4.4 Ability to recognize abnormal indications for 4.7 81 system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the 4.1 82 600000 Plant Fire On Site / 8 resultant operational effects.

700000 Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals: 0 0 0 0 4 3 Group Point Total: 7 Rev 1

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 (SRO)

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

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 AA2.01 Ability to determine and/or interpret the 4.3 83 295015 Incomplete SCRAM / 1 following as they apply to INCOMPLETE SCRAM:

Reactor power 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area 2.2.12 Knowledge of surveillance procedures. 4.1 84 Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 2.1.25 Ability to interpret reference materials, such 4.2 85 500000 High CTMT Hydrogen Conc. / 5 as graphs, curves, tables, etc.

K/A Category Point Totals: 0 0 0 0 1 2 Group Point Total: 3 Rev 1

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

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 203000 RHR/LPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI 20700 Isol Condenser 209001 LPCS 209002 HPCS A2.03 Ability to (a) predict the impacts of 3.4 86 the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on those predictions, use procedures to 211000 SLC correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. power failures 212000 RPS 215003 IRM 215004 Source Range Monitor 215005 APRM / LPRM A2.01 Ability to (a) predict the impacts of 3.7 87 the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC);

and (b) based on those predictions, use 217000 RCIC procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System Initiation Signal 218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff A2.03 Ability to (a) predict the impacts of 4.2 88 the following on the RELIEF/SAFETY VALVES; and (b) based on those 239002 SRVs predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Stuck open SRV.

2.4.50 Ability to verify system alarm 4.0 89 259002 Reactor Water Level setpoints and operate controls identified in Control l the alarm response manual.

261000 SGTS 2.4.41 Knowledge of the emergency action 4.6 90 262001 AC Electrical Distribution level thresholds and classifications.

262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water Rev 1

ES-401 5 Form ES-401-1 510000 (SF4 SWS*) Service Water K/A Category Point Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 Rev 1

ES-401 6 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)

System # / Name K K K K K K A A2 A A G* K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 201001 CRD Hydraulic A2.08 Ability to (a) predict the impacts of 2.8 91 the following on the CONTROL ROD DRIVE HYDRAULIC SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Inadequate system flow 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-Core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux. 2.4.35 Knowledge of local auxiliary 4.0 92 operator tasks during an emergency and the resultant operational effects.

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate A2.03 Ability to (a) predict the impacts of 259001 Reactor Feedwater the following on the REACTOR 3.6 93 FEEDWATER SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals 204000 RWCU K/A Category Point Totals: 0 0 0 1 0 0 0 2 0 0 1 Group Point Total: 3 Rev 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3-SRO) Form ES-401-3 Facility: Grand Gulf Nuclear Station Date of Exam: February 2020 Category K/A # Topic RO SRO-Only IR # IR #

2.1.2 Knowledge of operator responsibilities during all modes 4.4 94 of plant operation.

2.1.37 Knowledge of procedures, guidelines, or limitations 4.6 95

1. associated with reactivity management.

Conduct of Operations Subtotal 2 2.2.7 Knowledge of the process for conducting special or 3.6 96 infrequent tests.

2.2.21 Knowledge of pre- and post-maintenance operability 4.1 97

2. requirements.

Equipment Control Subtotal 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.7 98 emergency conditions.

3.

Radiation Control Subtotal 1 2.4.29 Knowledge of the emergency plan. 4.4 99 2.4.42 Knowledge of emergency response facilities. 3.8 100 4.

Emergency Procedures / Plan Subtotal 2 Tier 3 Point Total 7 Rev 1

ES-401 Record of Rejected K/As Form ES-401-4 Randomly Tier/Group Selected K/A Reason for Rejection (Original)

(New)

RO T1 - G1 Original KA: AK3.04 Knowledge of the reasons for the following 295003 295003 responses as they apply to PARTIAL OR COMPLETE LOSS OF AK3.04 AK3.07 A.C. POWER : Ground isolation Q# 2 At GGNS, if a ground occurred on an A.C. Powered bus the electrical department would perform the check and isolation of the ground. Operations does not perform a ground isolation.

Randomly selected New K/A: AK3.05, Reactor SCRAM Page 1 point totals not affected by this change.

RO T1 - G1 Original KA: AK3.04 Knowledge of the reasons for the following 295021 295021 responses as they apply to LOSS OF SHUTDOWN COOLING :

AK3.04 AK3.01 Increasing drywell cooling Q# 9 At GGNS, there is no procedural requirement to increase drywell cooling on a loss of Shutdown Cooling. The Off Normal Event Procedure for Inadequate Decay Heat Removal does not mention increasing drywell cooling to mitigate this loss.

Randomly selected New K/A: AK3.01, AK3.01 Raising reactor water level Page 1 point totals not affected by this change.

RO T1 - G1 This KA was placed in error and replaced, NO swap required, 295037 A2 listed but K2 revised ES-401-1, K/A Topic for 295037 to include the following:

EA2.03 words are used.

Ability to determine and/or interpret the following as they apply to Q# 18 SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : EA2.03 SBLC tank level Page 1 point totals not affected by this change.

RO T1 - G1 700000 Original KA: AK1.02 Knowledge of the operational implications of 700000 AK1.01 the following concepts as they apply to GENERATOR VOLTAGE AK1.02 AND ELECTRIC GRID DISTURBANCES: Over-excitation Q# 20 Even though the ONEP states a band to maintain MVARS during an Over-excited state, procedures conflict with the limits. To prevent and confusion request change of KA.

Randomly selected AK1.01, Definition of terms: volts, watts, amps, VARs, power factor

ES-401 Record of Rejected K/As Form ES-401-4 RO T2 - G1 This KA was placed in error from a different K/A system and 261000 261000 replaced.

K1.11 K1.08 Randomly selected New K/A: K1.08. Knowledge of the physical Q# 46 connections and/or cause effect relationships between STANDBY GAS TREATMENT SYSTEM and the following: Process radiation monitoring system.

Page 1 point totals not affected by this change.

RO T2 - G1 This KA was placed in error from Rev. 3 NUREG 1123 and 510000 209002 replaced.

K1.02 K1.02 Randomly Selected new K/A 209002: K1.02 Knowledge of the Q# 53 physical connections and/or cause effect relationships between HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) and the following: Suppression Pool: BWR-5,6 Page 1 point totals not affected by this change.

RO T2 - G2 Original KA: K1.14 Knowledge of the physical connections and/or 202001 202001 cause effect relationships between RECIRCULATION SYSTEM and K1.14 K1.15 the following: Rod block monitor Q# 55 At GGNS a Rod Block Monitor system is not used. The RC&IS system provides the Control Rod Block feature.

Randomly selected New K/A: K1.15 Raising reactor water level Page 1 point totals not affected by this change.

RO T2 - G2 Original KA: K6.06 Knowledge of the effect that a loss or 202002 202002 malfunction of the following will have on the RECIRCULATION K6.06 K6.05 FLOW CONTROL SYSTEM : Reactor/turbine pressure regulating system Q# 56 At GGNS, the Reactor/turbine pressure regulating system no longer provides any input into the Recirculation Flow Control system anymore. GGNS controls the flow control system in MANUAL valve control, NO auto feedback from the Reactor/turbine pressure regulating system.

Randomly selected New K/A: K6.05, Reactor water level Page 1 point totals not affected by this change.

ES-401 Record of Rejected K/As Form ES-401-4 RO T2 - G2 Original KA: 214000, K3.03 Knowledge of the effect that a loss or 214000 201005 malfunction of the ROD POSITION INFORMATION SYSTEM will K3.03 K3.01 have on following: RMCS: Plant-Specific Q# 57 At GGNS, Rod position and information is a part of the RCIS system (K/A 201005). RPIS is not a stand alone system.

Randomly selected New K/A: 201005 RCIS K3.01, Knowledge of the effect that a loss or malfunction of the ROD CONTROL AND INFORMATION SYSTEM (RCIS) will have on following: Control rod drive system: BWR-6 Page 1 point totals not affected by this change.

RO T2 G2 Original KA: 245000, A4.05 Ability to manually operate and/or 245000 245000 monitor in the control room. Generator megawatt output.

A4.05 A4.01 Due to the limited response of the megawatt output does not lend a Q# 60 question with plausible distractors.

Randomly selected New K/A: A4.01, Turbine Lube Oil pumps.

Page 1 point totals not affected by this change.

RO T2 - G2 Original KA: 259001, K5.02 Knowledge of the operational 259001 259001 implications of the following concepts as they apply to REACTOR K5.02 K5.03 FEEDWATER SYSTEM : Water hammer Q# 62 At GGNS, Water hammer is a generic concern and not a specific one in the feedwater procedures.

Randomly selected New K/A: K5.03, Turbine operation: TDRFP's-Only Page 1 point totals not affected by this change.

RO T2 - G2 Original KA: 272000 Radiation Monitoring, A3.05 Ability to monitor 272000 272000 automatic operations of the RADIATION MONITORING SYSTEM A3.05 A3.06 including: Refuel floor overhead crane operation interrupt Q# 63 At GGNS, there is NO refuel floor overhead crane operation interrupt action with the Radiation Monitoring system.

Randomly selected New K/A: A3.06, Ventilation system isolation indications Page 1 point totals not affected by this change.

ES-401 Record of Rejected K/As Form ES-401-4 RO T2 - G2 This KA was placed in error from Rev. 3 NUREG 1123 and 51001 219000 replaced.

2.4.49 2.4.49 Randomly Selected new K/A 219000 Q# 65 K/A Topic, 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls, remains the same.

Page 1 point totals not affected by this change.

RO T3 Original KA: Ability to manage the control room crew during plant 2.1.6 2.1.8 transients.

Q# 66 The ability to manage is inherent a SRO / Supervisor task.

Randomly Selected new K/A 2.1.36 K/A Topic, 2.1.36 Knowledge of procedures and limitations involved in core alterations.

Page 1 point totals not affected by this change.

RO T3 Original KA: Knowledge of the parameters and logic used to 2.4.21 2.4.29 assess the status of safety functions, such as reactivity control, core Q# 74 cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Assessing status is inherently an SRO function.

Randomly selected new K/A 2.4.29 Knowledge of the emergency plan.

Page 1 point totals not affected by this change.

ES-401 Record of Rejected K/As Form ES-401-4 SRO T1-G1 Original KA: 2.2.39 Knowledge of less than or equal to one hour 295027 295027 Technical Specification action statements for systems.

2.2.39 2.2.25 This K/A does not meet the knowledge requirements for a SRO, <1 Q# 79 hour Tech Specs action statements are RO knowledge level.

Randomly selected New K/A: 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Page 1 point totals not affected by this change.

SRO T1-G1 This KA was placed in error from Rev. 3 NUREG 1123 and 510000 262001 replaced.

2.4.41 2.4.41 Randomly Selected new K/A 262001.

Q# 90 2.4.41 Knowledge of the emergency action level thresholds and classifications, remained the same.

Page 1 point totals not affected by this change.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 2/3/2020 Examination Level: RO SRO Operating Test Number: GGNS 2/2020 Administrative Topic (see Note) Type Describe activity to be performed Code*

Determine Core Flow, given plant parameters, system status or events determine actual Reactor Core Flow.

Conduct of Operations R, N GJPM-OPS-2/2020-AR1 2.1.7 (4.4)

Reactor Water Level Determination, The operator will evaluate plant conditions at the Remote Shutdown Panel to determine Narrow Conduct of Operations R, D Range reactor water level and the status of injection sources.

GJPM-OPS-2/2020-AR2 2.1.25 (3.9)

Emergency Exposure Limits, The operator will evaluate a condition involving abnormally high radiological conditions and determine Radiation Control R, D actions required to administratively control the dose received by determining who authorizes dose extensions in various situations.

GJPM-OPS-2/2020-AR3 2.3.4 (3.2)

Loss of Shutdown Cooling, Time to 200°F, given plant status and parameters determine the time to 200 on a loss of Shutdown Cooling.

Emergency Plan R, N GJPM-OPS-2/2020-AR4 2.4.11 (3.4/3.6)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes) (2)

(N)ew or (M)odified from bank ( 1) (2)

(P)revious 2 exams ( 1, randomly selected) (0)

Rev 0 8/6/2019

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 2/3/2020 Examination Level: RO SRO Operating Test Number: GGNS 2/2020 Administrative Topic (see Note) Type Describe activity to be performed Code*

Determine Reportability, This task is to use corporate procedures and given plant conditions to determine the reportability and Conduct of Operations R, D complete applicable notification form GJPM-OPS-2/2020-AS1 2.1.20 (4.6)

Determine Penetration Isolation Requirements, given failure of penetration isolation valve failure, determine Tech Spec Conduct of Operations R, D action and requirements for isolating.

GJPM-OPS-2/2020-AS2 2.1.7 (4.7)

Tagout Removal Approval, given a protective tagging removal, verify restored positions and information.

Equipment Control R, D GJPM-OPS-2/2020-AS3 2.2.15 (4.3) - 2.2.15 (4.3) - 2.2.41 (3.9)

Authorize Emergency Exposure, given plant status and events in progress, determine appropriate radiation exposure limits.

Radiation Control R, N GJPM-OPS-2/2020-AS4 2.3.4 (3.7)

PAR Determination, given plant status and events in progress, determine correct PAR recommendations.

Emergency Plan R, N GJPM-OPS-2/2020-AS5 2.4.44 (4.4)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

(N)ew or (M)odified from bank ( 1) (2)

(P)revious 2 exams ( 1, randomly selected) (0)

Rev 2 1/15/2019

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination: 2/03/2020 Exam Level: RO SRO-I SRO-U Operating Test No.: GGNS 2-2020 Control Room Systems* (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function S1 - Transfer Recirculation Pumps to Slow Speed A-D-S 1 (GJPM-OPS-2-2020S1) 202001 A2.04 & A4.01 (3.7)

S2 - Retest MSIV Slow Closure A-D-P-S 3 (GJPM-OPS-2-2020S2) 239001 A2.11 (4.1)

S3 - Performing HPCS Quarterly Functional Test A-D-S-EN 4 (GJPM-OPS-2-2020S3) 209002: A1.01 (3.6); A4.01 (3.7)

S4 - Secure Containment Spray and Align for RPV Injection (GJPM-OPS-2-2020S4) 226001 A2.20 (3.7) & A4.07 (3.5) L-M-S-EN 5 S5 - Rotate CCW Pumps (GJPM-OPS-2-2020S5) 400000 A2.01 (3.3) & A4.01 (3.1) A-D-S 8 S6 - Place Standby Gas Treatment System in STANDBY Mode (GJPM-OPS-2-2020S6) 261000 A2.13 (3.4) & A4.03 (3.0) L-N-S-EN 9 C1 - Defeat Feed Pump Level 9 Trips (GJPM-OPS-2-2020CR1) 259001 A3.10 (3.4) D-C-L 2 S7 - Transfer RPS B to Normal Power Source and RPS A to Alternate Power Source (RO ONLY) D-S 7 (GJPM-OPS-2-2020S7) 212000 A2.19 (3.8) & A4.14 (3.8)

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

P1 - RPS Motor Generator Startup D 7 (GJPM-OPS-2-2020P1) 212000 A2.01 (3.7) & A1.01 (2.8)

P2 - Align Fire Water to RHR C per EP Attachment 26 D-E-L-R 8 (GJPM-OPS-2-2020P2) 286000 A1.05 (3.2)

P3 - HPCS Diesel Generator Emergency Shutdown A-E-N 6 (GJPM-OPS-2-2020P3) 264000 A4.04 (3.7)

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO / SRO-I / SRO-U A 4-6 / 4-6 / 2-3 (5)

(A)lternate path (C)ontrol room C ----- (1)

(D)irect from bank D <9 / <8 / <4 (8)

(E)mergency or abnormal in-plant E >1 / >1 / >1 (2)

(EN)gineered safety feature EN >1 / >1 / > 1 (control room sys) (3)

(L)ow-Power / Shutdown L >1 / >1 / >1 (3)

(N)ew or (M)odified from bank including 1(A) N-M >2 / >2 / >1 (3)

(P)revious 2 exams P <3 / <3 / < 2 (randomly selected) (1)

(R)CA (S)imulator R >1 / >1 / >1 (1)

S (7)

Rev 0 08/30/2019

JPM

Description:

S1 - Transfer Recirculation Pumps to Slow Speed (GJPM-OPS-2-2020S1) 202001 A2.04 & A4.01 (3.7)

  • This task is to transfer Reactor Recirculation Pumps to slow speed per IOI - 2, 03-1 2, Power Operations Attachment IV section 8.8.6 and 8.8.7. Upon transfer to slow speed and reopening of both Recirculation Flow Control Valves to 50%, both Reactor Recirculation Pumps will trip to OFF. With the Reactor Mode Switch in RUN at power and no Reactor Recirculation Pumps operating, entry into the Reduction in Recirculation Flow ONEP 05-1-02-III-3, Immediate Operator Actions step 2.1.2 will be required to insert a Manual Reactor Scram.

S2 - Retest MSIV Slow Closure (GJPM-OPS-2-2020S2) 239001 A2.11 (4.1)

  • This task is to perform a slow closure on MSIV B21-F028A.
  • Following the closure of the MSIV, recognize High - High temperature in Main Steam Tunnel without Group 1 MSIV isolation. Applicant should manually close all remaining MSIVs (7) using handswitches on P601 panel to isolate the steam leak.
  • At initial power level Main Steam Line Drains should be closed with the exception of B21-F019, INBD MSL DR OTBD DR VLV which has another valve in the line already closed B21-F016, INBD MSL DR INBD DR VLV.

S3 - Performing HPCS Quarterly Functional Test (GJPM-OPS-2-2020S3) 209002: A1.01 (3.6); A4.01 (3.7)

  • This task requires the ability to manually start the only ECCS-qualified high pressure injection system.
  • This task demonstrates the ability to operate HPCS in the "test return" mode, which puts HPCS flow in a loop from and to the Suppression Pool, one of its two suction sources.

HPCS is operated in this mode for surveillance and post-maintenance testing.

  • As HPCS is placed in the test return mode the system will experience a failure to initiate and a failure to inject once manually initiated. This will require to arm and depress the initiation pushbutton and then manually open the E22-F004.

Rev 0 08/30/2019

S4 - Secure Containment Spray and Align for RPV Injection (GJPM-OPS-2-2020S4) 226001 A2.20 (3.7) & A4.07 (3.5)

  • This task is to secure RHR systems from Containment Spray and align them for injection into the RPV during a LOCA. During the performance one RHR system will not provide sufficient flow to raise RPV water level and the second RHR system will have a failure of E12-F042 LPCI injection valve to open requiring the use of an alternate injection path through E12-F053. Realignment of RHR from Containment Spray to LPCI mode is directed from the Emergency Procedures when there is not Adequate Core Cooling.

Use of Shutdown Cooling lines for injection to the RPV from RHR is allowed per the Emergency Procedures and attachments are provided to facilitate this evolution.

S5 - Rotate CCW Pumps (GJPM-OPS-2-2020S5) 400000 A2.01 (3.3) & A4.01 (3.1)

  • This task is to rotate CCW Pumps per SOI. During the evolution, a trip will occur on one of the operating CCW pumps requiring the restart of the non-operating CCW pump per the Loss of CCW ONEP.

S6 - Place Standby Gas Treatment System in STANDBY Mode (GJPM-OPS-2-2020S6) 261000 A2.13 (3.4) & A4.03 (3.0)

  • This task is to place one Standby Gas Treatment System in STANDBY Mode after an automatic initiation signal on Radiation that is still present.

C1 - Defeat Feed Pump Level 9 Trips (GJPM-OPS-2-2020CR1) 259001 A3.10 3.4/3.4

  • This task defeats the High Reactor Water Level trip of the Reactor Feed Pumps, which under certain conditions is directed by the EOPs to maintain adequate core cooling.

S7 - Transfer RPS B to Normal Power Source and RPS A to Alternate Power Source (RO ONLY)

(GJPM-OPS-2-2020S7) 212000 A2.19 (3.8) & A4.14 (3.8)

  • This task is to align RPS B power to be supplied from its Normal source, the Motor Generator Set, and to align RPS A power to be supplied from its Alternate source, 480V ESF breaker 52-154204.

P1 - RPS Motor Generator Startup (GJPM-OPS-2-2020P1) 212000 A2.01 (3.7) & A1.01 (2.8)

  • This task is to perform a startup of the RPS Motor Generator and align the RPS Bus to the Normal Supply per the SOI.

Rev 0 08/30/2019

P2 - Align Fire Water to RHR C per EP Attachment 26 (GJPM-OPS-2-2020P2) 286000 A1.05 (3.2)

  • This task simulates routing and connecting fire hoses from hose stations to test connections on ECCS injection piping in the Auxiliary Building.

P3 - HPCS Diesel Generator Emergency Shutdown (GJPM-OPS-2-2020P3) 264000 A4.04 (3.7)

  • This task simulates an auto start of HPCS Diesel Generator with a subsequent oil system failure requiring the operator to EMERGENCY STOP (trip) the HPCS D/G. The Control Room switch and local Emergency Stop switch will not work, the operator must use other means to stop the EDG. Per P81 SOI the lay shaft handle on each diesel engine must be manipulated to stop the EDG.

Rev 0 08/30/2019

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Grand Gulf Nuclear Station Date of Examination: 2/03/2020 Exam Level: RO SRO-I SRO-U Operating Test No.: GGNS 2-2020 Control Room Systems* (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function S1 - Transfer Recirculation Pumps to Slow Speed A-D-S 1 (GJPM-OPS-2-2020S1) 202001 A2.04 & A4.01 (3.7)

S2 - Retest MSIV Slow Closure A-D-P-S 3 (GJPM-OPS-2-2020S2) 239001 A2.11 (4.1)

S3 - Performing HPCS Quarterly Functional Test A-D-S-EN 4 (GJPM-OPS-2-2020S3) 209002: A1.01 (3.6); A4.01 (3.7)

S4 - Secure Containment Spray and Align for RPV Injection (GJPM-OPS-2-2019S4) 226001 A2.20 (3.7) & A4.07 (3.5) L-M-S-EN 5 S5 - Rotate CCW Pumps (GJPM-OPS-2-2020S5) 400000 A2.01 (3.3) & A4.01 (3.1) A-D-S 8 S6 - Place Standby Gas Treatment System in STANDBY Mode (GJPM-OPS-2-2020S6) 261000 A2.13 (3.4) & A4.03 (3.0) L-N-S-EN 9 C1 - Defeat Feed Pump Level 9 Trips (GJPM-OPS-2-2020CR1) 259001 A3.10 (3.4) D-C-L 2 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 - RPS Motor Generator Startup D 7 (GJPM-OPS-2-2020P1) 212000 A2.01 (3.7) & A1.01 (2.8)

P2 - Align Fire Water to RHR C per EP Attachment 26 (GJPM-OPS-2-2020P2) 286000 A1.05 (3.2) D-E-L-R 8 P3 - HPCS Diesel Generator Emergency Shutdown (GJPM-OPS-2-2020P3) 264000 A4.04 (3.7) A-E-N 6

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO / SRO-I / SRO-U A 4-6 / 4-6 / 2-3 (5)

(A)lternate path (C)ontrol room C ----- (1)

(D)irect from bank D <9 / <8 / <4 (7)

(E)mergency or abnormal in-plant E >1 / >1 / >1 (2)

(EN)gineered safety feature EN >1 / >1 / > 1 (control room sys) (3)

(L)ow-Power / Shutdown L >1 / >1 / >1 (3)

(N)ew or (M)odified from bank including 1(A) N-M >2 / >2 / >1 (3)

(P)revious 2 exams P <3 / <3 / < 2 (randomly selected) (1)

(R)CA (S)imulator R >1 / >1 / >1 (1)

S (6)

Rev 0 08/30/2019

JPM

Description:

S1 - Transfer Recirculation Pumps to Slow Speed (GJPM-OPS-2-2020S1) 202001 A2.04 & A4.01 (3.7)

  • This task is to transfer Reactor Recirculation Pumps to slow speed per IOI - 2, 03-1 2, Power Operations Attachment IV section 8.8.6 and 8.8.7. Upon transfer to slow speed and reopening of both Recirculation Flow Control Valves to 50%, both Reactor Recirculation Pumps will trip to OFF. With the Reactor Mode Switch in RUN at power and no Reactor Recirculation Pumps operating, entry into the Reduction in Recirculation Flow ONEP 05-1-02-III-3, Immediate Operator Actions step 2.1.2 will be required to insert a Manual Reactor Scram.

S2 - Retest MSIV Slow Closure (GJPM-OPS-2-2020S2) 239001 A2.11 (4.1)

  • This task is to perform a slow closure on MSIV B21-F028A.
  • Following the closure of the MSIV, recognize High - High temperature in Main Steam Tunnel without Group 1 MSIV isolation. Applicant should manually close all remaining MSIVs (7) using handswitches on P601 panel to isolate the steam leak.
  • At initial power level Main Steam Line Drains should be closed with the exception of B21-F019, INBD MSL DR OTBD DR VLV which has another valve in the line already closed B21-F016, INBD MSL DR INBD DR VLV.

S3 - Performing HPCS Quarterly Functional Test (GJPM-OPS-2-2020S3) 209002: A1.01 (3.6); A4.01 (3.7)

  • This task requires the ability to manually start the only ECCS-qualified high pressure injection system.
  • This task demonstrates the ability to operate HPCS in the "test return" mode, which puts HPCS flow in a loop from and to the Suppression Pool, one of its two suction sources.

HPCS is operated in this mode for surveillance and post-maintenance testing.

  • As HPCS is placed in the test return mode the system will experience a failure to initiate and a failure to inject once manually initiated. This will require to arm and depress the initiation pushbutton and then manually open the E22-F004.

Rev 0 08/30/2019

S4 - Secure Containment Spray and Align for RPV Injection (GJPM-OPS-2-2020S4) 226001 A2.20 (3.7) & A4.07 (3.5)

  • This task is to secure RHR systems from Containment Spray and align them for injection into the RPV during a LOCA. During the performance one RHR system will not provide sufficient flow to raise RPV water level and the second RHR system will have a failure of E12-F042 LPCI injection valve to open requiring the use of an alternate injection path through E12-F053. Realignment of RHR from Containment Spray to LPCI mode is directed from the Emergency Procedures when there is not Adequate Core Cooling.

Use of Shutdown Cooling lines for injection to the RPV from RHR is allowed per the Emergency Procedures and attachments are provided to facilitate this evolution.

S5 - Rotate CCW Pumps (GJPM-OPS-2-2020S5) 400000 A2.01 (3.3) & A4.01 (3.1)

  • This task is to rotate CCW Pumps per SOI. During the evolution, a trip will occur on one of the operating CCW pumps requiring the restart of the non-operating CCW pump per the Loss of CCW ONEP.

S6 - Place Standby Gas Treatment System in STANDBY Mode (GJPM-OPS-2-2020S6) 261000 A2.13 (3.4) & A4.03 (3.0)

  • This task is to place one Standby Gas Treatment System in STANDBY Mode after an automatic initiation signal on Radiation that is still present.

C1 - Defeat Feed Pump Level 9 Trips (GJPM-OPS-2-2020CR1) 259001 A3.10 3.4/3.4

  • This task defeats the High Reactor Water Level trip of the Reactor Feed Pumps, which under certain conditions is directed by the EOPs to maintain adequate core cooling.

P1 - RPS Motor Generator Startup (GJPM-OPS-2-2020P1) 212000 A2.01 (3.7) & A1.01 (2.8)

  • This task is to perform a startup of the RPS Motor Generator and align the RPS Bus to the Normal Supply per the SOI.

Rev 0 08/30/2019

P2 - Align Fire Water to RHR C per EP Attachment 26 (GJPM-OPS-2-2020P2) 286000 A1.05 (3.2)

  • This task simulates routing and connecting fire hoses from hose stations to test connections on ECCS injection piping in the Auxiliary Building.

P3 - HPCS Diesel Generator Emergency Shutdown (GJPM-OPS-2-2020P3) 264000 A4.04 (3.7)

  • This task simulates an auto start of HPCS Diesel Generator with a subsequent oil system failure requiring the operator to EMERGENCY STOP (trip) the HPCS D/G. The Control Room switch and local Emergency Stop switch will not work, the operator must use other means to stop the EDG. Per P81 SOI the lay shaft handle on each diesel engine must be manipulated to stop the EDG.

Rev 0 08/30/2019

SCENARIOS 1 & 3 OMITTED AS THEY WERE UNUSED SPARE SCENARIOS AND WERE PLACED IN THE LICENSEES EXAM BANK

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