ML14017A033

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2013-11-Draft Outlines
ML14017A033
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 11/15/2013
From: Garchow S
Operations Branch IV
To:
Entergy Operations
laura hurley
References
ES-401, ES-401-1
Download: ML14017A033 (30)
v • d • e


Text

ES-401 BWR Examination Outline - RO Form ES-401-1 Facility: Grand Gulf Date of Exam: November, 2013 Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total

1.

Emergency &

Abnormal Plant Evolutions 1

3 4

5 N/A 2

3 N/A 3

20 7

2 2

2 1

1 0

1 7

3 Tier Totals 5

6 6

3 3

4 27 10

2.

Plant Systems 1

3 2

2 2

2 3

2 2

2 4

2 26 5

2 2

0 1

2 2

1 0

1 1

1 1

12 3

Tier Totals 5

2 3

4 4

4 2

3 3

5 3

38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

4 2

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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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 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 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 importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the 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.

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 K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR Q#

295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 X

AK3.01 - Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER.

3.3 1

295003 Partial or Complete Loss of AC / 6 X

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

3.7 2

295004 Partial or Total Loss of DC Pwr / 6 X

AK2.02 -. Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following: Batteries 3.0 3

295005 Main Turbine Generator Trip / 3 X

AA1.04 - Ability to operate and/or monitor the following as they apply to MAIN TURBINE GENERATOR TRIP : Main generator controls 2.7 4

295006 SCRAM / 1 X

AK1.02 - Knowledge of the operational implications of the following concepts as they apply to SCRAM :

Shutdown margin 3.4 5

295016 Control Room Abandonment / 7 X

AA2.05 - Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT : Drywell pressure 3.8 6

295018 Partial or Total Loss of CCW / 8 X

AA2.02 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Cooling water temperature 3.1 7

295019 Partial or Total Loss of Inst. Air / 8 X

AK2.16 - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: Reactor core isolation cooling 2.8 8

295021 Loss of Shutdown Cooling / 4 X

AK3.01 - Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING : Raising reactor water level 3.3 9

295023 Refueling Acc / 8 X

AA1.04 - Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS : Radiation monitoring equipment 3.4 10 295024 High Drywell Pressure / 5 X

EK1.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE : Containment building integrity: Mark-III 3.9 11 295025 High Reactor Pressure / 3 X

2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

4.2 12 295026 Suppression Pool High Water Temp. / 5 X

EK3.05 - Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor SCRAM 3.9 13 295027 High Containment Temperature / 5 X

EK1.03 - Knowledge of the operational implications of the following concepts as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) : Containment integrity:

Mark-III.

3.8 14 295028 High Drywell Temperature / 5 X

EK2.02 - Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following: Components internal to the drywell 3.2 15 295030 Low Suppression Pool Wtr Lvl / 5 X

EA2.03 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL : Reactor pressure 3.7 16 295031 Reactor Low Water Level / 2 X

2.1.31 Ability to locate control room switches /

controls and indications and to determine that they are correctly reflecting the desired plant lineup.

4.2 17

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 X

EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: System isolations 3.9 18 600000 Plant Fire On Site / 8 X

AK3.04 - Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site 2.8 19 700000 Generator Voltage and Electric Grid Disturbances / 6 X

AK2.03 - Knowledge of the interrelations between GENERATOR VOLTAGE AND lELECTRIC GRID DISTURBANCES and the following: Sensors, detectors, indicators 3.0 20 K/A Category Totals:

3 4

5 2

3 3

Group Point Total:

20

ES-401 3

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

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 X

AK1..05 - Knowledge of the operational implications of the following concepts as they apply to LOW REACTOR WATER LEVEL : Natural circulation 3.3 21 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 X

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

4.2 22 295013 High Suppression Pool Temp. / 5 X

AA1.02 - Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE : Systems that add heat to the suppression pool 3.9 23 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 X

AK2. Knowledge of the interrelations between INCOMPLETE SCRAM and the following: Rod control and information system: Plant-Specific 3.2 24 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 X

EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE : Reactor SCRAM 3.6 25 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 X

EK2.02 - Knowledge of the interrelations between SECONDARY CONTAINMENT VENTILATION HIGH RADIATION and the following: Area radiation monitoring system 3.8 26 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 X

EK1.01 - Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL :

Radiation releases 2.9 27 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals:

2 2

1 1

0 1

Group Point Total:

7

ES-401 4

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 203000 RHR/LPCI: Injection Mode X

K6.10 - Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) : Component cooling water systems 3.0 28 205000 Shutdown Cooling X

A2. Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low shutdown cooling suction pressure: Plant-Specific 2.6 29 X

K2.01 - Knowledge of electrical power supplies to the following: Pump motors 3.1 30 206000 HPCI NA GGNS 207000 Isolation (Emergency)

Condenser NA GGNS 209001 LPCS X

K3.03 - Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:

Emergency generators 2.9 31 X

A4.08 - Ability to manually operate and/or monitor in the control room: Reactor water level 3.9 32 209002 HPCS X

2.4.18 - Knowledge of the specific bases for EOPs.

3.3 33 211000 SLC X

K4.09 - Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

Dampening of positive displacement pump discharge oscillations (accumulators): Plant-Specific 2.5 34 212000 RPS X

K1. Knowledge of the physical connections and/or cause-effect relationships between REACTOR PROTECTION SYSTEM and the following: A.C. electrical distribution 3.4 35 215003 IRM X

K1.05 - Knowledge of the physical connections and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following: Display control system: Plant-Specific 3.3 36 X

K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM : 24/48 volt D.C. power: Plant-Specific 3.6 37 215004 Source Range Monitor X

A1.05 - Ability to predict and/or monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including: SCRAM, rod block, and period alarm trip setpoints 3.6 38 215005 APRM / LPRM X

A3.04 - Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including: Annunciator and alarm signals 3.2 39

217000 RCIC X

A2.15 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Steam line break 3.8 40 218000 ADS X

K5.01 - Knowledge of the operational implications of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM : ADS logic operation 3.8 41 223002 PCIS/Nuclear Steam Supply Shutoff X

A4.03 - Ability to manually operate and/or monitor in the control room: Reset system isolations 3.6 42 239002 SRVs X

K2.01 - Knowledge of electrical power supplies to the following: SRV solenoids 2.8 43 259002 Reactor Water Level Control X

A3.01 - Ability to monitor automatic operations of the REACTOR WATER LEVEL CONTROL SYSTEM including: Runout flow control: Plant-Specific 3.0 44 261000 SGTS X

K1.08 - Knowledge of the physical connections and/or cause-effect relationships between STANDBY GAS TREATMENT SYSTEM and the following: Process radiation monitoring system 2.8 45 262001 AC Electrical Distribution X

K4.04 - Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the following:

Protective relaying 2.8 46 X

A4.04 Ability to manually operate and/or monitor in the control room: Synchronizing and paralleling of different A.C. supplies 3.6 47 262002 UPS (AC/DC)

X A1.02 - Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs 2.5 48 263000 DC Electrical Distribution X

2.4.6 - Knowledge of EOP mitigation strategies.

3.7 49 X

K3.02 - Knowledge of the effect that a loss or malfunction of the D.C. ELECTRICAL DISTRIBUTION will have on the following:

Components using D.C. control power (i.e.

breakers) 3.5 50 264000 EDGs X

K5.06 - Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET) : Load sequencing 3.4 51 300000 Instrument Air X

K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the INSTRUMENT AIR SYSTEM: Temperature indicators 2.7 52 400000 Component Cooling Water X

A4.01 - Ability to manually operate and / or monitor in the control room: CCW indications and control 3.1 53 K/A Category Point Totals:

3 2

2 2

2 3

2 2

2 4

2 Group Point Total:

26

ES-401 5

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism X

K1.03 - Knowledge of the physical connections and/or cause-effect relationships between CONTROL ROD AND DRIVE MECHANISM and the following: RPIS 3.1 54 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation X 2.4.9 - Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

3.8 55 202002 Recirculation Flow Control 204000 RWCU X

K4.08 - Knowledge of REACTOR WATER CLEANUP SYSTEM design feature(s) and/or interlocks which provide for the following: Reducing reactor pressure upstream of low pressure piping: LP-RWCU 3.3 56 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

X K5.13 - Knowledge of the operational implications of the following concepts as they apply to NUCLEAR BOILER INSTRUMENTATION : Reference leg flashing: Design-Specific 3.5 57 219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

X K4.06 - Knowledge of PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES design feature(s) and/or interlocks which provide for the following:

Maintains proper containment/secondary containment to drywell differential pressure 3.1 58 226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup X

A2.19 - Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Inadequate system/pool chemistry 2.5 59 234000 Fuel Handling Equipment

239001 Main and Reheat Steam X

K6.08 - Knowledge of the effect that a loss or malfunction of the following will have on the MAIN AND REHEAT STEAM SYSTEM: Main condenser vacuum 3.3 60 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

X K3.08 - Knowledge of the effect that a loss or malfunction of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS will have on following: Reactor/turbine pressure control system: Plant-Specific 3.7 61 256000 Reactor Condensate 259001 Reactor Feedwater X

K5.03 - Knowledge of the operational implications of the following concepts as they apply to REACTOR FEEDWATER SYSTEM : Turbine operation: TDRFP's-Only 2.8 62 268000 Radwaste 271000 Offgas X

A4.01 - Ability to manually operate and/or monitor in the control room: Reset system isolations 2.8 63 272000 Radiation Monitoring 286000 Fire Protection X

A3.06 - Ability to monitor automatic operations of the FIRE PROTECTION SYSTEM including: Fire dampers 3.0 64 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC X

K4.01 - Knowledge of CONTROL ROOM HVAC design feature(s) and/or interlocks which provide for the following: System initiations/reconfiguration: Plant-Specific 3.1 65 290002 Reactor Vessel Internals K/A Category Point Totals:

2 0

1 2

2 1

0 1

1 1

1 Group Point Total:

12

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Grand Gulf Date of Exam: November, 2013 Category K/A #

Topic RO SRO-Only IR Q#

IR

1.

Conduct of Operations 2.1.21 Ability to verify the controlled procedure copy.

3.5 66 2.1.27 Knowledge of system purpose and/or function.

3.9 67 2.1.30 Ability to locate and operate components, including local controls.

4.4 68 2.1.40 Knowledge of refueling administrative requirements.

2.8 69

2.

Equipment Control 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

3.5 70 2.2.43 Knowledge of the process used to track inoperable alarms.

3.0 71

3.

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

3.2 72 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.4 73

4.

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

4.1 74 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

4.2 75 Tier 3 Point Total 10

ES-401 Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection SYSTEMS DELETED 201002 Reactor Manual Control System - This system is not incorporated into the BWR-6 design. The functions of this system are incorporated into the Rod Control and Information System.

201004 Rod Sequence Control System - This system is not incorporated into the BWR-6 design. The functions of this system are incorporated into the Rod Control and Information System.

201006 Rod Worth Minimizer System - This system is not incorporated into the BWR-6 design. The functions of this system are incorporated into the Rod Control and Information System.

214000 Rod Position Information System - This system is not incorporated into the BWR-6 design. The functions of this system are incorporated into the Rod Control and Information System.

215002 Rod Block Monitor System - This system is not incorporated into the BWR-6 design.

The functions of this system are incorporated into the Rod Control and Information System.

206000 High Pressure Core Injection (HPCI) - This system is not incorporated into the BWR 6 design.

207000 Isolation (Emergency) Condenser - This system is not incorporated into the BWR 6 design. This was replaced by the Mark III Containment Suppression Pool.

230000 RHR/LPCI: Torus/Pool Spray Mode - This system is not incorporated into the BWR 6 Mark III Containment design.

Written Exam Sample Plan: This sampling plan was developed using the manual sampling method described in ES401,Attachment 1 of NUREG1021, Revision 9, Supplement 1. It applies this same manual method throughout the sampling process, including the sampling of the Generic KAs listed on page 4 of ES401, section D.1.b, as well as any resampling that is required for rejected KAs (i.e., KA swaps).

Instead of tokens, the plan was developed using the web site random.org to generate the random number associated with each decision. Instead of bounding the possible selections by the number of tokens, the web site allows the user to specify the range of possible numbers for each choice.

ES-401 BWR Examination Outline - SRO Form ES-401-1 Facility: Grand Gulf Date of Exam:

November, 2013 Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total

1.

Emergency &

Abnormal Plant Evolutions 1

N/A N/A 20 4

3 7

2 7

2 1

3 Tier Totals 27 6

4 10

2.

Plant Systems 1

26 2

3 5

2 12 2

1 3

Tier Totals 38 4

4 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

2 2

1 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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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 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 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 importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the 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.

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)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC / 6 X

AA2.03 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER : Battery status: Plant-Specific 3.5 76 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 X

2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

4.5 77 295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW / 8 X

AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Component temperatures 3.4 78 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 295026 Suppression Pool High Water Temp. / 5 X

2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

4.3 79 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 X

EA2.03 - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE : Reactor water level 3.9 80 295030 Low Suppression Pool Wtr Lvl / 5 295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X

EA2.04 - Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Suppression pool temperature 4.1 81 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / 8 700000 Generator Voltage and Electric Grid Disturbances / 6 X

2.1.20 Ability to interpret and execute procedure steps.

4.6 82 K/A Category Totals:

4 3

Group Point Total:

7

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

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 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 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 X

AA2.04 - Ability to determine and/or interpret the following as they apply to INADVERTENT CONTAINMENT ISOLATION :Drywell/containment temperature 3.4 83 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 Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 X

EA2.01-Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:

3.9 84 295036 Secondary Containment High Sump/Area Water Level / 5 X

2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

4.6 85 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals:

2 1

Group Point Total:

3

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

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 203000 RHR/LPCI: Injection Mode X

2.1.19 - Ability to use plant computers to evaluate system or component status.

3.8 86 205000 Shutdown Cooling 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS 209002 HPCS 211000 SLC X

A2.07 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Valve closures 3.2 87 212000 RPS 215003 IRM 215004 Source Range Monitor 215005 APRM / LPRM X

A2.02 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Upscale or downscale trips 3.7 88 217000 RCIC 218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control X

2.4.34 - Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects.

4.1 89 261000 SGTS 262001 AC Electrical Distribution 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air

400000 Component Cooling Water X

2.4.2 - Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

4.6 90 K/A Category Point Totals:

2 3

Group Point Total:

5

ES-401 5

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism X

A2.06 - Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of CRD cooling water flow 3.1 91 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 X

A2.03 - Ability to (a) predict the impacts of the following on the RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve closures 3.2 92 223001 Primary CTMT and Aux.

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 X 2.4.1 Knowledge of EOP entry conditions and immediate action steps.

4.8 93 259001 Reactor Feedwater 268000 Radwaste

271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals:

2 1

Group Point Total:

3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Grand Gulf Date of Exam: November, 2013 Category K/A #

Topic RO SRO-Only IR IR

1.

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

4.4 94 2.1.38 Knowledge of the station's requirements for verbal communications when implementing procedures.

3.8 95 Subtotal 2

2.

Equipment Control 2.2.35 Ability to determine Technical Specification Mode of Operation.

4.5 96 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

4.2 97 Subtotal 2

3.

Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.8 98 Subtotal 1

4.

Emergency Procedures / Plan 2.4.11 Knowledge of abnormal condition procedures.

4.2 99 2.4.25 Knowledge of fire protection procedures.

3.7 100 Subtotal 2

Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection Written Exam Sample Plan: This sampling plan was developed using the manual sampling method described in ES401,Attachment 1 of NUREG1021, Revision 9, Supplement

1. It applies this same manual method throughout the sampling process, including the sampling of the Generic KAs listed on page 4 of ES401, section D.1.b, as well as any resampling that is required for rejected KAs (i.e., KA swaps). Instead of tokens, the plan was developed using the web site random.org to generate the random number associated with each decision. Instead of bounding the possible selections by the number of tokens, the web site allows the user to specify the range of possible numbers for each choice.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Grand Gulf Nuclear Station Date of Examination: 11/11/2013 Examination Level: RO SRO Operating Test Number: LOT 2013 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations R-N Determine Surveillance Requirements for OPDRV GJPM-OPS-2013-AS1 2.1.23 (4.3/4.4), 2.1.25 (3.9/4.2), 2.1.40 (2.8/3.9)

Conduct of Operations R-N Manual On-Line Risk Assessment GJPM-OPS-2013-AS2 2.1.20 (4.6/4.6), 2.1.25 (3.9/4.2), 2.2.17 (2.6/3.8)

Equipment Control R-N Determine Penetration Isolation Requirements GJPM-OPS-2013-AS3 2.2.15 (3.9/4.3), 2.2.40 (3.4/4.7), 2.2.41 (3.5/3.9)

Radiation Control R-N Authorize Emergency Exposure GJPM-OPS-2013-AS4 2.3.4 (3.2/3.7)1 Emergency Procedures/Plan S/R-B Emergency Event Classification GJPM-OPS-2013-AS5 2.4.41 (2.9/4.6)

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

  • Type Codes & Criteria:

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

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: GRAND GULF NUCLEAR STATION Date of Examination: 11/8/2013 Exam Level: RO SRO-I SRO-U Operating Test No.:

LOT-2013 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

a. 202001 A2.04 (3.7/3.8), A2.26 (2.9/3.1), A3.07 (3.3/3.3) /

Returning a Recirculation Loop to Service at Power, GJPM-OPS-2013CR1 A-N-S 1

b. 217000 A4.04 (3.6/3.6) / RCIC Manual Startup, GJPM-OPS-2013CR2 A-M-S 2
c. 241000 A2.06 (3.1/3.2) / Open Main Steam Isolation Valves, GJPM-OPS-2013CR3 M-L-S 3
d. 205000 A4.03 (3.6/3.5) / Defeat SDC Injection Valve Isolation Interlocks, GJPM-OPS-2013CR4 C-D-E-L-EN 4
e. 219000 A4.01 (3.8/3.7), A4.02 (3.7/3.5), A4.05 (3.4/3.4 /

Startup Suppression Pool Cooling B GJPM-OPS-2013CR5 A-M-S 5

f.

264000 A4.04 (3.7/3.7), / Start,Parallel and Load Div 1 D/G GJPM-OPS-2013CR6 A-D-S 6

g. 201005 A2.03 (3.2/3.2), A2.04 (3.2/3.2), A2.06 (3.2/3.2), A2.07 3.2/3.2, / Bypass a Control Rod in RACS, GJPM-OPS-2013CR7 C-D-L 7

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

h. 212000 A2.01, (3.7/3.9), / RPS Motor Generator Startup GJPM-OPS-2013PS1 D

7

i.

286000 A1.05 (3.2/3.2), / Align Fire Water to RHR C per EP 6, GJPM-OPS-2013PS2 D-E-L-R 8

j.

262001 2.1.30 (4.4/4.0), 2.1.20 (4.6/4.6), / Placing LSS in Standby, GJPM-OPS-2013PS3 D

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)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

Rev 0 (2/28/12)

Page 1 of 2 ES-301 Transient and Event Checklist Form ES-301-5 Facility: GGNS Date of Exam: 11/11-15/2013 Operating Test No.: LOT-2013 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

2 3

T O

T A

L M

I N

I M

U M(*)

CREW POSITION CREW POSITION CREW POSITION CREW POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

I4 I7 RX 0

0 0

0 1

NOR 0

1 1

2 1

I/C 5

3 2

10 4

MAJ 1

1 1

3 2

TS 2

2 2

I2 I3 RX 0

0 0

1 NOR 1

0 1

1 I/C 2

5 7

4 MAJ 1

1 2

2 TS 2

2 2

I5 I8 RX 0

0 0

0 1

NOR 1

0 0

1 1

I/C 2

3 4

9 4

MAJ 1

1 1

3 2

TS 2

2 2

I6 I9 RX 0

0 0

0 1

NOR 0

0 0

0 1

I/C 3

5 2

10 4

MAJ 1

1 1

3 2

TS 2

2 2

Instructions:

1.

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; ()Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

Rev 0 (2/28/12)

Page 2 of 2 ES-301 Transient and Event Checklist Form ES-301-5 Facility: GGNS Date of Exam: 11/11-15/2013 Operating Test No.: LOT-2013 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

2 3

T O

T A

L M

I N

I M

U M(*)

CREW POSITION CREW POSITION CREW POSITION CREW POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

I1 I10 RX 0

0 0

1 NOR 0

1 1

1 I/C 5

3 8

4 MAJ 1

1 2

2 TS 2

2 2

RX NOR I/C MAJ TS RX NOR I/C MAJ TS RX NOR I/C MAJ TS Instructions:

3.

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; ()Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

4.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

Appendix D Required Operator Actions Form ES-D-1 Scenario 3 Page 1 of 2 Facility: Grand Gulf Nuclear Station Scenario No.: 3 Op-Test No.: LOT-2013 Examiners: ____________________________ Operators:

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

Withdraw control rods per the start up control rod movement sequence.

Control rod data fault requiring entry of substitute position Control rod drift out.

Failure of ESF Transformer 11.

Main Steam Line leak outside containment with inability to isolate.

Scram Air Header failure to vent - ATWS below 5% power.

Standby Liquid Control System piping failure.

Initial Conditions: Plant is operating at 4.5% power during start up. Reactor pressure is 400 psig.

Inoperable Equipment: none Turnover:

Plant is operating at 4.5% power during start up.

Reactor pressure is 400 psig.

Step 143 of the start up control rod movement sequence has been completed.

Condensate Pumps A and C are in service.

Condensate Booster Pump A is in service.

Continue start up by performing steps 144 through 146 of the start up control rod movement sequence. Then, place Reactor Feed Pump A in service per IOI-1, step 6.2.13d.

Reactor Feed Pump minimum flow controllers on 1H22-P171 have been verified to be in AUTO per IOI-1 step 6.2.13d.

The walkdown of Reactor Feed Pumps per IOI-1 step 6.2.13d(1) has been completed satisfactorily.

This is a Division 1 work day.

Scenario Notes:

This is a new scenario.

Validation Time (60-90 min): XX min

Appendix D Required Operator Actions Form ES-D-1 Scenario 3 Page 2 of 2 Event No.

Malf. No.

Event Type Event Description 1

N (ATC)

Withdraw control rods per the start up control rod movement sequence. (03-1-01-1, Cold Shutdown to Generator Carrying Minimum Load; 04-1-01-C11-2, Rod Control and Information System; Control Rod Movement Sequence).

2 rci036 C (ATC)

Control Rod 60-21 data fault resulting in a control rod withdrawal block (ARI 04-1-02-1H13-P680-4A-C5; 04-1-01-C11-2, Rod Control and Information System, section 4.11).

3 z161161_04

-45 C (ATC)

A (CREW)

TS (CRS)

Control Rod 04-45 drift out (05-1-02-IV-1, Control Rod/Drive Malfunctions; ARI 04-1-02-1H13-P680-4A2-E4).

4 r21134g n41141a C (BOP)

A (CREW)

TS (CRS)

ESF Transformer 11 trip followed by trip of Division 1 Diesel Generator (05-1-02-I-4, Loss of AC Power; 05-1-02-III-5, Automatic Isolations, 02-S-01-27, Operations Philosophy).

5 ms066b ms183b ms184b c11167 M(CREW)

Main Steam Line B leak in Auxiliary Building Steam Tunnel with failure/inability to isolate, ATWS - failure of scram air header to vent, power below 5%(EP-4, Auxiliary Building Control; EP-2A, ATWS RPV Control; 05-1-02-III-5, Automatic Isolations; 05 02-I-1, Reactor Scram; 02-S-01-27 Operations Philosophy).

When the second area reaches its maximum safe temperature, the crew performs Emergency Depressurization by opening 8 ADS/SRVs Before Emergency Depressurization, the crew terminates and prevents all injection except boron, CRD, and RCIC per EP-2A.

Following the ATWS, crew directs installation of EP Attachments 18, 19, and 20 and inserts control rods by manual scram and/or normal rod insertion per EP-2A step Q-

1.

6 c41263 C (BOP)

Standby Liquid Control System piping failure (SOI 04-1-01-C41-1, Standby Liquid Control System, Attachment VI; EP-2, ATWS RPV Control, Attachment 28).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Critical Task (As defined in NUREG 1021 Appendix D)

Quantitative Attributes Table Normal Events 1

Abnormal Events 2

Reactivity Manipulations 0

Total Malfunctions 8

Instrument/Component Failures 4

EP Entries (Requiring substantive action) 2 Major Transients 1

EP Contingencies 1

Tech Spec Calls 2

Critical Tasks 3

Appendix D Required Operator Actions Form ES-D-1 Scenario 4 Page 1 of 2 Facility: Grand Gulf Nuclear Station Scenario No.: 4 Op-Test No.: LOT-2013 Examiners: ____________________________ Operators:

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

Return Condensate Pump B and Condensate Booster Pump B to service.

Control Rod Drive Pump A trip resulting in CRD HCU pressure fault.

Standby Service Water A Cooling Tower Fan B trip.

Feedwater Master Level Controller output failure high.

Feedwater Line B rupture in Turbine Building.

ATWS - hydraulic block power above 5%.

Standby Liquid Control System squib valves fail to immediately actuate (actuate after a delay, when Emergency Depressurization is commenced).

Initial Conditions: Plant is operating at 75% power. Condensate Pump B and Condensate Booster Pump B are in standby following maintenance on Condensate Pump B. Standby Service Water A is in operation for weekly chemical addition.

Inoperable Equipment: none Turnover:

Plant is operating at 75% power.

Condensate Pump B and Condensate Booster Pump B are in standby following maintenance on Condensate Pump B.

This is a Division 1 work day.

Immediately following the brief The ATC will return Condensate Pump B and Condensate Booster Pump B to service in accordance with 04-1-01-N19-1 section 4.3 and 03-1-01-2 step 6.6.

  • All prerequisites of step 4.3.1 have been completed.
  • Steps 4.3.2a(1), (2), and (3) have been completed.

Scenario Notes:

This is a new scenario.

Validation Time (60-90 min): XX min

Appendix D Required Operator Actions Form ES-D-1 Scenario 4 Page 2 of 2 Event No.

Malf. No.

Event Type Event Description 1

N (ATC)

Return Condensate Pump B and Condensate Booster Pump B to service. (03-1-01-2, Power Operations, step 6.6; 04-1 N19-1, Condensate System, section 4.3.2).

2 c11028a z024_024_32_17 C (BOP)

A (CREW)

TS (CRS)

Control Rod Drive Pump A trip resulting in CRD HCU 32-17 low pressure fault that will not clear (05-1-02-IV-7, Control Rod/Drive Malfunctions; ARI 04-1-02-1H13-P680-4A2-D4; TS 3.1.5, TR 3.1.5) 3 p41148d C (BOP)

TS (CRS)

Standby Service Water A Cooling Tower Fan B trip. (ARI 04 02-1H13-P870-1A-B2; SOI 04-1-01-P41-1, Standby Service Water System; 02-S-01-27, Operations Philosophy; TS 3.7.1).

4 r21134g n41141a C (BOP)

A (CREW)

TS (CRS)

Feedwater Master Level Controller output failure high (05-1 V-7, Feedwater System Malfunctions).

5 fw070b c11164 M(CREW)

Feedwater Line B rupture in Turbine Building, ATWS - hydraulic block power above 5%(EP-2A, ATWS RPV Control; 05-1-02-I-1, Reactor Scram; 05-1-02-I-2, Turbine Generator Trips; 02-S 27, Operations Philosophy).

When reactor water level cannot be restored and maintained above -191 cfz using Table 1 systems, the crew performs Emergency Depressurization by opening 8 ADS/SRVs.

Before Emergency Depressurization, the crew terminates and prevents all injection except boron, CRD, and RCIC per EP-2A.

When reactor pressure decreases to MSCP, 219 psig, the crew commences and slowly raises injection using RHR A and/or RHR B via E12F053A/B, SDC Return to Feedwater, to restore and maintain RPV level to greater than -191".

Criterion is to give the highest priority to restore RPV level greater than -191".

6 c41263 C (BOP)

Standby Liquid Control System squib valves fail to immediately actuate (actuate after a delay, when Emergency Depressurization is commenced) (SOI 04-1-01-C41-1, Standby Liquid Control System, Attachment VI; EP-2, ATWS RPV Control, Attachment 28).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Critical Task (As defined in NUREG 1021 Appendix D)

Quantitative Attributes Table Normal Events 1

Abnormal Events 2

Reactivity Manipulations 0

Total Malfunctions 8

Instrument/Component Failures 4

EP Entries (Requiring substantive action) 2 Major Transients 1

EP Contingencies 1

Tech Spec Calls 2

Critical Tasks 3

Appendix D Required Operator Actions Form ES-D-1 Scenario 5 Page 1 of 2 Facility: Grand Gulf Nuclear Station Scenario No.: 5 Op-Test No.: LOT-2013 Examiners: ____________________________ Operators:

Objectives: To evaluate the candidates ability to operate the facility in response to the following evolutions:

Place Reactor Water Clean-Up filters in HOLD and secure RWCU pump A.

RWCU Heat Exchanger leak inside Containment with failure of Division 1 RWCU valves to automatically isolate.

Jet Pumps 11/12 failure.

Service Transformers 11 and 21 lockout.

Reactor Recirc piping rupture.

Failure of HPCS injection valve.

RHR B/C logic power failure.

Initial Conditions: Plant is operating at 100% power.

Inoperable Equipment: Division 1 Diesel Generator is tagged out of service.

Turnover:

Plant is operating at 100% power.

Division 1 Diesel Generator is tagged out of service to replace an optical isolator in 1H22-P400.

  • The plant is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> into 14 day LCO 3.8.1b.
  • The next AC/DC lineup is due in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
  • Maintenance on DG11 should be complete within the next hour.

Immediately following turnover:

  • Place RWCU filters in hold per 04-1-01-G33-1 section 4.6.
  • Then, secure RWCU pump A per 04-1-01-G33-1 section 5.9 for planned maintenance on its discharge check valve, 1G33F012A.

This is a Division 1 work week.

Scenario Notes:

This is a new scenario.

Validation Time (60-90 min): XX min

Appendix D Required Operator Actions Form ES-D-1 Scenario 5 Page 2 of 2 Event No.

Malf. No.

Event Type Event Description 1

N (BOP)

Place Reactor Water Clean-Up filters in HOLD and secure RWCU pump A. (04-1-01-G33-1, Reactor Water Clean-Up System, sections 4.6 and 5.9).

2 g33033 (rf) e31210 C (ATC)

A (CREW)

TS (CRS)

RWCU Heat Exchanger leak inside Containment with failure of Division 1 RWCU valves to automatically isolate (05-1-02-III-5, Automatic Isolations; ARI 04-1-02-1H13-P680-11A-A3, A4,E3; TS 3.3.6.1) 3 rr011f C (ATC)

A (CREW)

TS (CRS)

Failure of Jet Pumps 11/12 rams head. (05-1-02-III-6, Jet Pump Anomalies; 05-1-02-III-3, Reduction in Recirculation System Flow Rate; TS 3.4.3).

4 r21133a r21133b rr063b M (CREW)

Service Transformers 11 and 21 lockout / Recirc loop B rupture (EP-2, RPV Control; EP-3, Containment Control; 05-1-02-I-1, Reactor Scram; 05-1-02-I-2, Turbine Generator Trips; 05-1-02-I-4, Loss of AC Power).

When reactor water level decreases to -160 (TAF), the crew opens 8 SRVs per EP-2 step ED-4. (At least seven SRVs must be open before RPV level drops to -217.)

The crew manually restores power to Division 1 ECCS bus 15AA, AND/OR manually opens HPCS injection valve 1E22F004, AND/OR manually starts and injects with RHR B or C and restores reactor water level to above -160 following emergency depressurization per EP-2 step L-14. (At least one ECCS must be aligned for injection prior to reactor pressure decreasing below 125 psig during Emergency Depressurization.)

5 (rf) r21221 C

(BOP/ATC)

RHR B/C logic power failure (ARI 04-1-02-1H13-P601-H2).

6 e22159a C (BOP)

Failure of HPCS Reactor Level 8 relay E22A-K13, resulting in closure of injection valve 1E22F004 (ARI 04-1-02-1H13-P601-16A-A3)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal (TS) Tech Spec Critical Task (As defined in NUREG 1021 Appendix D)

Quantitative Attributes Table Normal Events 1

Abnormal Events 2

Reactivity Manipulations 0

Total Malfunctions 8

Instrument/Component Failures 4

EP Entries (Requiring substantive action) 1 Major Transients 1

EP Contingencies 1

Tech Spec Calls 2

Critical Tasks 2

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