Text

2013-11-Draft Outlines
	ML14017A033
Person / Time
Site:	Grand Gulf
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

ES-401 BWR Examination Outline - RO Form ES-401-1 Facility: Grand Gulf Date of Exam: November, 2013 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

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

Abnormal Plant 2 2 2 1 N/A 1 0 N/A 1 7 3 Evolutions Tier Totals 5 6 6 3 3 4 27 10 1 3 2 2 2 2 3 2 2 2 4 2 26 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 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 K K A A G K/A Topic(s) IR Q#

1 2 3 1 2 AK3.01 - Knowledge of the reasons for the 295001 Partial or Complete Loss of Forced X following responses as they apply to PARTIAL OR 1 Core Flow Circulation / 1 & 4 3.3 COMPLETE LOSS OF A.C. POWER.

2.1.7 Ability to evaluate plant performance and 295003 Partial or Complete Loss of AC / 6 X make operational judgments based on operating characteristics / reactor behavior / and instrument 3.7 2 interpretation.

AK2.02 -. Knowledge of the interrelations between 295004 Partial or Total Loss of DC Pwr / 6 X PARTIAL OR COMPLETE LOSS OF D.C. POWER 3.0 3 and the following: Batteries AA1.04 - Ability to operate and/or monitor the 295005 Main Turbine Generator Trip / 3 X following as they apply to MAIN TURBINE 2.7 4 GENERATOR TRIP : Main generator controls AK1.02 - Knowledge of the operational implications 295006 SCRAM / 1 X of the following concepts as they apply to SCRAM : 3.4 5 Shutdown margin AA2.05 - Ability to determine and/or interpret the 295016 Control Room Abandonment / 7 X following as they apply to CONTROL ROOM 3.8 6 ABANDONMENT : Drywell pressure AA2.02 - Ability to determine and/or interpret the 295018 Partial or Total Loss of CCW / 8 X following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING 3.1 7 WATER : Cooling water temperature AK2.16 - Knowledge of the interrelations between 295019 Partial or Total Loss of Inst. Air / 8 X PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: Reactor core 2.8 8 isolation cooling AK3.01 - Knowledge of the reasons for the 295021 Loss of Shutdown Cooling / 4 X following responses as they apply to LOSS OF SHUTDOWN COOLING : Raising reactor water 3.3 9 level AA1.04 - Ability to operate and/or monitor the 295023 Refueling Acc / 8 X following as they apply to REFUELING 3.4 10 ACCIDENTS : Radiation monitoring equipment EK1.02 - Knowledge of the operational implications 295024 High Drywell Pressure / 5 X of the following concepts as they apply to HIGH DRYWELL PRESSURE : Containment building 3.9 11 integrity: Mark-III 2.4.50 - Ability to verify system alarm setpoints and 295025 High Reactor Pressure / 3 X operate controls identified in the alarm response 4.2 12 manual.

EK3.05 - Knowledge of the reasons for the 295026 Suppression Pool High Water X following responses as they apply to Temp. / 5 SUPPRESSION POOL HIGH WATER 3.9 13 TEMPERATURE: Reactor SCRAM EK1.03 - Knowledge of the operational implications 295027 High Containment Temperature / 5 X of the following concepts as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III 3.8 14 CONTAINMENT ONLY) : Containment integrity:

Mark-III.

EK2.02 - Knowledge of the interrelations between 295028 High Drywell Temperature / 5 X HIGH DRYWELL TEMPERATURE and the following: Components 3.2 15 internal to the drywell EA2.03 - Ability to determine and/or interpret the 295030 Low Suppression Pool Wtr Lvl / 5 X following as they apply to LOW SUPPRESSION 3.7 16 POOL WATER LEVEL : Reactor pressure 2.1.31 Ability to locate control room switches /

295031 Reactor Low Water Level / 2 X controls and indications and to determine that they 4.2 17 are correctly reflecting the desired plant lineup.

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 EK3.02 - Knowledge of the reasons for the 295038 High Off-site Release Rate / 9 X following responses as they apply to HIGH OFF- 3.9 18 SITE RELEASE RATE: System isolations AK3.04 - Knowledge of the reasons for the 600000 Plant Fire On Site / 8 X following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal 2.8 19 procedure for plant fire on site AK2.03 - Knowledge of the interrelations between 700000 Generator Voltage and Electric Grid X GENERATOR VOLTAGE AND lELECTRIC GRID Disturbances / 6 DISTURBANCES and the following: Sensors, 3.0 20 detectors, indicators 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 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 AK1..05 - Knowledge of the operational implications of 295009 Low Reactor Water Level / 2 X the following concepts as they apply to LOW 3.3 21 REACTOR WATER LEVEL : Natural circulation 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 2.2.44 - Ability to interpret control room indications to 295012 High Drywell Temperature / 5 X verify the status and operation of a system, and understand how operator actions and directives affect 4.2 22 plant and system conditions.

AA1.02 - Ability to operate and/or monitor the following 295013 High Suppression Pool Temp. / 5 X as they apply to HIGH SUPPRESSION POOL TEMPERATURE : Systems that add heat to the 3.9 23 suppression pool 295014 Inadvertent Reactivity Addition / 1 AK2. Knowledge of the interrelations between 295015 Incomplete SCRAM / 1 X INCOMPLETE SCRAM and the following: Rod control 3.2 24 and information system: Plant-Specific 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 EK3.02 - Knowledge of the reasons for the following 295032 High Secondary Containment X responses as they apply to HIGH SECONDARY Area Temperature / 5 CONTAINMENT AREA TEMPERATURE : Reactor 3.6 25 SCRAM 295033 High Secondary Containment Area Radiation Levels / 9 EK2.02 - Knowledge of the interrelations between 295034 Secondary Containment X SECONDARY CONTAINMENT VENTILATION HIGH Ventilation High Radiation / 9 RADIATION and the following: Area radiation 3.8 26 monitoring system 295035 Secondary Containment High Differential Pressure / 5 EK1.01 - Knowledge of the operational implications of 295036 Secondary Containment High X the following concepts as they apply to SECONDARY Sump/Area Water Level / 5 CONTAINMENT HIGH SUMP/AREA WATER LEVEL : 2.9 27 Radiation releases 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 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 K6.10 - Knowledge of the effect that a loss or 203000 RHR/LPCI: Injection X malfunction of the following will have on the Mode RHR/LPCI: INJECTION MODE (PLANT 3.0 28 SPECIFIC) : Component cooling water systems A2. Ability to (a) predict the impacts of the 205000 Shutdown Cooling X following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate 2.6 29 the consequences of those abnormal conditions or operations: Low shutdown cooling suction pressure: Plant-Specific K2.01 - Knowledge of electrical power X supplies to the following: Pump motors 3.1 30 206000 HPCI NA GGNS 207000 Isolation (Emergency) NA GGNS Condenser K3.03 - Knowledge of the effect that a loss or 209001 LPCS X malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following: 2.9 31 Emergency generators A4.08 - Ability to manually operate and/or X monitor in the control room: Reactor water 3.9 32 level 2.4.18 - Knowledge of the specific bases for 209002 HPCS X EOPs. 3.3 33 K4.09 - Knowledge of STANDBY LIQUID 211000 SLC X CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

Dampening of positive displacement pump 2.5 34 discharge oscillations (accumulators): Plant-Specific K1. Knowledge of the physical connections 212000 RPS X and/or cause-effect relationships between REACTOR PROTECTION SYSTEM and the 3.4 35 following: A.C. electrical distribution K1.05 - Knowledge of the physical 215003 IRM X connections and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR 3.3 36 (IRM) SYSTEM and the following: Display control system: Plant-Specific K6.02 - Knowledge of the effect that a loss or X malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) 3.6 37 SYSTEM : 24/48 volt D.C. power: Plant-Specific A1.05 - Ability to predict and/or monitor 215004 Source Range Monitor X changes in parameters associated with operating the SOURCE RANGE MONITOR 3.6 38 (SRM) SYSTEM controls including: SCRAM, rod block, and period alarm trip setpoints A3.04 - Ability to monitor automatic 215005 APRM / LPRM X operations of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE 3.2 39 MONITOR SYSTEM including: Annunciator and alarm signals

A2.15 - Ability to (a) predict the impacts of the 217000 RCIC X following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ;

and (b) based on those predictions, use 3.8 40 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Steam line break K5.01 - Knowledge of the operational 218000 ADS X implications of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION 3.8 41 SYSTEM : ADS logic operation A4.03 - Ability to manually operate and/or 223002 PCIS/Nuclear Steam X monitor in the control room: Reset system Supply Shutoff 3.6 42 isolations K2.01 - Knowledge of electrical power 239002 SRVs X supplies to the following: SRV solenoids 2.8 43 A3.01 - Ability to monitor automatic 259002 Reactor Water Level X operations of the REACTOR WATER LEVEL Control CONTROL SYSTEM including: Runout flow 3.0 44 control: Plant-Specific K1.08 - Knowledge of the physical 261000 SGTS X connections and/or cause-effect relationships between STANDBY GAS TREATMENT 2.8 45 SYSTEM and the following: Process radiation monitoring system K4.04 - Knowledge of A.C. ELECTRICAL 262001 AC Electrical X DISTRIBUTION design feature(s) and/or Distribution interlocks which provide for the following: 2.8 46 Protective relaying A4.04 Ability to manually operate and/or X monitor in the control room: Synchronizing 3.6 47 and paralleling of different A.C. supplies A1.02 - Ability to predict and/or monitor 262002 UPS (AC/DC) X changes in parameters associated with operating the UNINTERRUPTABLE POWER 2.5 48 SUPPLY (A.C./D.C.) controls including: Motor generator outputs 2.4.6 - Knowledge of EOP mitigation 263000 DC Electrical X strategies. 3.7 49 Distribution K3.02 - Knowledge of the effect that a loss or X malfunction of the D.C. ELECTRICAL DISTRIBUTION will have on the following: 3.5 50 Components using D.C. control power (i.e.

breakers)

K5.06 - Knowledge of the operational 264000 EDGs X implications of the following concepts as they apply to EMERGENCY GENERATORS 3.4 51 (DIESEL/JET) : Load sequencing K6.03 - Knowledge of the effect that a loss or 300000 Instrument Air X malfunction of the following will have on the INSTRUMENT 2.7 52 AIR SYSTEM: Temperature indicators A4.01 - Ability to manually operate and / or 400000 Component Cooling X monitor in the control room: CCW indications Water 3.1 53 and control 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 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 201002 RMCS K1.03 - Knowledge of the physical 201003 Control Rod and Drive X connections and/or cause-effect Mechanism relationships between CONTROL ROD 3.1 54 AND DRIVE MECHANISM and the following: RPIS 201004 RSCS 201005 RCIS 201006 RWM 2.4.9 - Knowledge of low 202001 Recirculation X power/shutdown implications in accident (e.g., loss of coolant accident or loss of 3.8 55 residual heat removal) mitigation strategies.

202002 Recirculation Flow Control K4.08 - Knowledge of REACTOR 204000 RWCU X WATER CLEANUP SYSTEM design feature(s) and/or interlocks which provide for the following: Reducing 3.3 56 reactor pressure upstream of low pressure piping: LP-RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM K5.13 - Knowledge of the operational 216000 Nuclear Boiler Inst. X implications of the following concepts as they apply to NUCLEAR BOILER 3.5 57 INSTRUMENTATION : Reference leg flashing: Design-Specific 219000 RHR/LPCI: Torus/Pool Cooling Mode K4.06 - Knowledge of PRIMARY 223001 Primary CTMT and Aux. X CONTAINMENT SYSTEM AND AUXILIARIES design feature(s) and/or interlocks which provide for the following: 3.1 58 Maintains proper containment/secondary containment to drywell differential pressure 226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode A2.19 - Ability to (a) predict the impacts 233000 Fuel Pool Cooling/Cleanup X of the following on the FUEL POOL COOLING AND CLEAN-UP ; and (b) based on those predictions, use procedures to correct, control, or 2.5 59 mitigate the consequences of those abnormal conditions or operations:

Inadequate system/pool chemistry 234000 Fuel Handling Equipment

K6.08 - Knowledge of the effect that a 239001 Main and Reheat Steam X loss or malfunction of the following will have on the MAIN AND REHEAT 3.3 60 STEAM SYSTEM: Main condenser vacuum 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator K3.08 - Knowledge of the effect that a 245000 Main Turbine Gen. / Aux. X loss or malfunction of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS will have on 3.7 61 following: Reactor/turbine pressure control system: Plant-Specific 256000 Reactor Condensate K5.03 - Knowledge of the operational 259001 Reactor Feedwater X implications of the following concepts as they apply to REACTOR FEEDWATER 2.8 62 SYSTEM : Turbine operation: TDRFP's-Only 268000 Radwaste A4.01 - Ability to manually operate 271000 Offgas X and/or monitor in the control room: Reset 2.8 63 system isolations 272000 Radiation Monitoring A3.06 - Ability to monitor automatic 286000 Fire Protection X operations of the FIRE PROTECTION 3.0 64 SYSTEM including: Fire dampers 288000 Plant Ventilation 290001 Secondary CTMT K4.01 - Knowledge of CONTROL ROOM 290003 Control Room HVAC X HVAC design feature(s) and/or interlocks which provide for the following: System 3.1 65 initiations/reconfiguration: Plant-Specific 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 #

2.1.21 Ability to verify the controlled procedure copy. 3.5 66 1.

Conduct 2.1.27 Knowledge of system purpose and/or function. 3.9 67 of Operations Ability to locate and operate components, including local 2.1.30 4.4 68 controls.

2.1.40 Knowledge of refueling administrative requirements. 2.8 69 Ability to obtain and interpret station electrical and mechanical

2. 2.2.41 drawings. 3.5 70 Equipment Knowledge of the process used to track inoperable alarms.

Control 2.2.43 3.0 71 Knowledge of radiation exposure limits under normal or

3. 2.3.4 emergency conditions. 3.2 72 Radiation Control Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor 2.3.13 alarms, containment entry requirements, fuel handling 3.4 73 responsibilities, access to locked high-radiation areas, aligning filters, etc.

Ability to prioritize and interpret the significance of each

4. 2.4.45 annunciator or alarm. 4.1 74 Emergency Ability to diagnose and recognize trends in an accurate and Procedures / Plan 2.4.47 timely manner utilizing the appropriate control room reference 4.2 75 material.

Tier 3 Point Total 10

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 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 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 20 4 3 7 Emergency &

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

Plant 2 12 2 1 3 Systems 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).