Text

2014-10 - Final Outlines as Givens
	ML14310A423
Person / Time
Site:	Grand Gulf
Issue date:	10/24/2014
From:	Vincent Gaddy; Operations Branch IV
To:	; Entergy Operations
	laura hurley
References
	Download: ML14310A423 (29)
	v • d • e

ES-401 BWR Examination Outline - RO Form ES-401-1 Facility: Grand Gulf Date of Exam: October 17, 2014 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 2 1 5 3 3 6 20 7 Emergency &

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

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 4 3 3 3 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 / SRO)

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

1 2 3 1 2 AK1.04 Knowledge of the operational implications 295001 Partial or Complete Loss of Forced X of the following concepts as they apply to PARTIAL 2.5 Core Flow Circulation / 1 & 4 OR COMPLETE LOSS OF FORCED CORE FLOW 1 CIRCULATION : Limiting cycle oscillation: Plant Specific 2.1.31 Ability to locate control room switches, 295003 Partial or Complete Loss of AC / 6 X controls, and indications, and to determine that they 4.6 2 correctly reflect the desired plant lineup.

2.4.4 Ability to recognize abnormal indications for 295004 Partial or Total Loss of DC Pwr / 6 X system operating parameters that are entry-level 4.5 3

conditions for emergency and abnormal operating procedures.

AK2.02 Knowledge of the interrelations between 295005 Main Turbine Generator Trip / 3 X MAIN TURBINE GENERATOR TRIP and the 2.9 4 following: Feedwater Temperature 295006 SCRAM / 1 295016 Control Room Abandonment / 7 X 2.2.12 Knowledge of surveillance procedures. 3.7 5 AK3.07 Knowledge of the reasons for the following 295018 Partial or Total Loss of CCW / 8 X responses as they apply to PARTIAL OR 3.1 6

COMPLETE LOSS OF COMPONENT COOLING WATER : Cross-connecting with backup systems.

295019 Partial or Total Loss of Inst. Air / 8 X 2.2.41 Ability to obtain and interpret station electrical 3.5 7 and mechanical drawings.

AA2.01 Ability to determine and/or interpret the 295021 Loss of Shutdown Cooling / 4 X following as they apply to LOSS OF SHUTDOWN 3.5 8 COOLING : Reactor water heatup/cooldown rate.

AA2.01 Ability to determine and/or interpret the 295023 Refueling Acc / 8 X following as they apply to REFUELING ACCIDENTS 3.6 9

Area radiation levels EA1.04 Ability to operate and/or monitor the 295024 High Drywell Pressure / 5 X following as they apply to HIGH DRYWELL 4.1 10 PRESSURE: RHR/LPCI EA2.01 Ability to determine and/or interpret the 295025 High Reactor Pressure / 3 X following as they apply to HIGH REACTOR 4.3 11 PRESSURE: Reactor pressure EK3.05 Knowledge of the reasons for the following 295026 Suppression Pool High Water X responses as they apply to SUPPRESSION POOL 3.9 12 Temp. / 5 HIGH WATER TEMPERATURE: Reactor SCRAM EK3.02 Knowledge of the reasons for the following 295027 High Containment Temperature / 5 X responses as they apply to HIGH CONTAINMENT 3.2 13 TEMPERATURE MARK III CONTAINMENT ONLY)

Containment spray: Plant specific 2.1.28 Knowledge of the purpose and function of 295028 High Drywell Temperature / 5 X 4.1 14 major system components and controls.

EK3.06 Knowledge of the reasons for the following 295030 Low Suppression Pool Wtr Lvl / 5 X responses as they apply to LOW SUPPRESSION 3.6 15 POOL WATER LEVEL: Reactor SCRAM EK3.01 Knowledge of the reasons for the following 295031 Reactor Low Water Level / 2 X responses as they apply to REACTOR LOW 3.9 16 WATER LEVEL : Automatic depressurization system actuation 295037 SCRAM Condition Present X 2.4.6 Knowledge of EOP mitigation strategies. 3.7 and Reactor Power Above APRM 17 Downscale or Unknown / 1 EK2..02 Knowledge of the interrelations between 295038 High Off-site Release Rate / 9 X HIGH OFF-SITE RELEASE RATE and the following: 3.6 18 Offgas System

AA1.06 Ability to operate and / or monitor the 600000 Plant Fire On Site / 8 X following as they apply to PLANT FIRE ON SITE: 3.0 19 Fire Alarm AA1.03 Ability to operate and/or monitor the 700000 Generator Voltage and Electric Grid X following as they apply to GENERATOR VOLTAGE 3.8 Disturbances / 6 20 AND ELECTRIC GRID DISTURBANCES: Voltage regulator controls K/A Category Totals: 2 1 5 3 3 6 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 / SRO)

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

1 2 3 1 2 AK2.07 Knowledge of the interrelations between LOSS 295002 Loss of Main Condenser Vac / 3 X OF MAIN CONDENSER VACUUM and the following: 3.1 21 Offgas system 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 AK2.04 Knowledge of the interrelations between LOW 295009 Low Reactor Water Level / 2 X REACTOR WATER LEVEL and the following: Reactor 2.6 22 water cleanup AA1.01 Ability to operate and/or monitor the following 295010 High Drywell Pressure / 5 X as they apply to HIGH DRYWELL PRESSURE : 3.4 23 Drywell ventilation/cooling AK2.01 Knowledge of the interrelations between HIGH 295011 High Containment Temp / 5 X CONTAINMENT TEMPERATURE (MARK III 3.7 24 CONTAINMENT ONLY) and the following:

Containment ventilation/cooling: Mark-III.

AK1.01Knowledge of the operational implications of 295012 High Drywell Temperature / 5 X the following concepts as they apply to HIGH 3.3 25 DRYWELL TEMPERATURE : Pressure/temperature relationship AA1.01 Ability to operate and/or monitor the following 295013 High Suppression Pool Temp. / 5 X as they apply to HIGH SUPPRESSION POOL 3.9 26 TEMPERATURE : Suppression pool cooling 295014 Inadvertent Reactivity Addition / 1 AK1.01 Knowledge of the operational implications of 295015 Incomplete SCRAM / 1 X the following concepts as they apply to INCOMPLETE 3.6 27 SCRAM : Shutdown margin 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 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 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 2 3 2 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 / SRO)

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 K4.14 Knowledge of RHR/LPCI: INJECTION 203000 RHR/LPCI: Injection X MODE (PLANT SPECIFIC) design feature(s) 3.6 28 Mode and/or interlocks which provide for the following: Operation from remote shutdown panel K5.02 Knowledge of the operational 205000 Shutdown Cooling X implications of the following concepts as they 2.8 29 apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) :Valve operation K4.04 Knowledge of SHUTDOWN COOLING X SYSTEM (RHR SHUTDOWN COOLING 2.6 30 MODE) design feature(s) and/or interlocks which provide for the following: Adequate pump NPSH 206000 HPCI NA GGNS 207000 Isolation (Emergency) NA GGNS Condenser K6.01 Knowledge of the effect that a loss or 209001 LPCS X malfunction of the following will have on the 3.4 31 LOW PRESSURE CORE SPRAY SYSTEM : A.C. power 2.1.19 Ability to use plant computers to X evaluate system or component status. 3.9 32 A1.09 Ability to predict and/or monitor 209002 HPCS X changes in parameters associated with 2.6 33 operating the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) controls including:

Condensate storage tank level: BWR-5,6 K5.05 Knowledge of the operational 211000 SLC X implications of the following concepts as they 2.5 34 apply to STANDBY LIQUID CONTROL SYSTEM : Accumulator operation: Plant-Specific K3.01 Knowledge of the effect that a loss or 212000 RPS X malfunction of the REACTOR PROTECTION 3.0 35 SYSTEM will have on following: Process radiation monitoring K6.04 Knowledge of the effect that a loss or 215003 IRM X malfunction of the following will have on the 3.0 36 INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM : Detectors A3.01 Ability to monitor automatic operations of X the INTERMEDIATE RANGE MONITOR (IRM) 3.3 37 SYSTEM including: Meters and recorders Ability to (a) predict the impacts of the 215004 Source Range Monitor X following on the SOURCE RANGE MONITOR 2.7 38 (SRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.01 Power supply degraded

K1.13 Knowledge of the physical connections 215005 APRM / LPRM X and/or causeeffect 2.6 39 relationships between AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following:

Traversing incore probe system 2.1.7 Ability to evaluate plant performance 217000 RCIC X and make operational judgments based on 4.4 40 operating characteristics, reactor behavior, and instrument interpretation.

K5.01 Knowledge of the operational 218000 ADS X implications of the following concepts as they 3.8 41 apply to AUTOMATIC DEPRESSURIZATION SYSTEM :ADS logic operation Ability to manually operate and/or 223002 PCIS/Nuclear Steam X 3.6 42 Supply Shutoff monitor in the control room:A4.01 Valve closures K4.01 Knowledge of RELIEF/SAFETY 239002 SRVs X VALVES design feature(s) and/or interlocks 3.9 43 which provide for the following: Insures that only one or two safety/relief valves reopen following the initial portion of a reactor isolation event (LLS logic): Plant-Specific K6.08 Knowledge of the effect that a loss or 259002 Reactor Water Level X malfunction of the following will have on the 2.7 44 Control REACTOR WATER LEVEL CONTROL SYSTEM :Loss of dP across startup level control bypass valve: Plant-Specific K3.02 Knowledge of the effect that a loss or 261000 SGTS X malfunction of the STANDBY GAS 3.6 45 TREATMENT SYSTEM will have on following: Off-site release rate A1.03 Ability to predict and/or monitor 262001 AC Electrical X changes in parameters associated with 2.9 46 Distribution operating the A.C. ELECTRICAL DISTRIBUTION controls including: Bus voltage K3.02 Knowledge of the effect that a loss or X malfunction of the A.C. ELECTRICAL 3.8 47 DISTRIBUTION will have on following:

Emergency generators A1.02 A1. Ability to predict and/or monitor 262002 UPS (AC/DC) X changes in parameters associated with 2.5 48 operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs A2.02 Ability to (a) predict the impacts of the 263000 DC Electrical X following on the D.C. ELECTRICAL 2.6 49 Distribution DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Loss of ventilation during charging K2.01 Knowledge of electrical power supplies X to the following: Major D.C. loads 3.1 50 K3.02 Knowledge of the effect that a loss or 264000 EDGs X malfunction of the EMERGENCY 3.9 51 GENERATORS (DIESEL/JET) will have on following: A.C. electrical distribution K1.04 Knowledge of the connections and / or 300000 Instrument Air X cause effect relationships between 2.8 52 INSTRUMENT AIR SYSTEM and the following: Cooling water to compressor K2.02 Knowledge of electrical power supplies 400000 Component Cooling X to the following: CCW valve 2.9 53 Water K/A Category Point Totals: 2 2 4 3 3 3 3 2 1 1 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 / SRO)

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 K1.05 Knowledge of the physical 201001 CRD Hydraulic X connections and/or cause-effect 2.7 54 relationships between CONTROL ROD DRIVE HYDRAULIC SYSTEM and the following: Feedwater (or reactor water cleanup)-CRD return to vessel: Plant-Specific 201002 RMCS K5.01 Knowledge of the operational 201003 Control Rod and Drive X 2.6 55 Mechanism implications of the following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM :Hydraulics 201004 RSCS 201005 RCIS X A1.01 First stage shell pressure/turbine 3.2 56 load: BWR-6 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control A4.02 Ability to manually operate and/or 204000 RWCU X 2.9 57 monitor in the control room: Valve controllers 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

2.1.28 Knowledge of the purpose and 219000 RHR/LPCI: Torus/Pool Cooling X 4.1 58 Mode function of major system components and lcontrols.

223001 Primary CTMT and Aux.

K5.06 Knowledge of the operational 226001 RHR/LPCI: CTMT Spray Mode X implications of the following concepts as 2.6 59 they apply to RHR/LPCI:

cONTAINMENT SPRAY SYSTEM MODE :Vacuum breaker operation 230000 RHR/LPCI: Torus/Pool Spray Mode K4.08 Knowledge of FUEL POOL 233000 Fuel Pool Cooling/Cleanup X 2.6 60 COOLING AND CLEAN-UP design feature(s) and/or interlocks which provide for the following: Pool cooling during loss of coolant accident: BWR-6 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator

K6.08 Knowledge of the effect that a loss 245000 Main Turbine Gen. / Aux. X 3.0 61 or malfunction of the following will have on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS : Main steam 256000 Reactor Condensate K6.07 Knowledge of the effect that a loss 259001 Reactor Feedwater X 3.8 62 or malfunction of the following will have on the REACTOR FEEDWATER SYSTEM : Reactor water level control system K3.04 Knowledge of the effect that a loss 268000 Radwaste X or malfunction of the RADWASTE will 2.7 63 have on following: Drain sumps K1.07 Knowledge of the physical 271000 Offgas X connections and/or cause-effect 2.7 64 relationships between OFFGAS SYSTEM and the following: Plant air systems 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT A3.02 Ability to monitor automatic 290003 Control Room HVAC X 3.0 65 operations of the CONTROL ROOM HVAC including: Initiation/failure of fire protection system 290002 Reactor Vessel Internals K/A Category Point Totals: 2 0 1 1 2 2 1 0 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: October 17, 2014 Category K/A # Topic RO SRO-Only IR # IR #

Ability to locate control room switches, controls, and indications, 2.1.31 and to determine that they correctly reflect the desired plant 4.6 66 lineup.

1.

Conduct 2.1.41 Knowledge of the refueling process. 2.8 67 of Operations 2.1.1 Knowledge of conduct of operations requirements. 3.8 68 2.1.43 Knowledge of the process used to track inoperable alarms. 3.0 69 Subtotal 4 Ability to determine operability and/or availability of safety related 2.2.37 equipment. 3.6 70 2.2.23 Ability to track Technical Specification limiting conditions for 3.1 71

2. operations.

Equipment Subtotal 2 Control Ability to use radiation monitoring systems, such as fixed 2.3.5 radiation monitors and alarms, portable survey instruments, 2.9 72 personnel monitoring equipment, etc.

Knowledge of radiation monitoring systems, such as fixed

3. 2.3.15 radiation monitors and alarms, portable survey instruments, 2.9 73 Radiation personnel monitoring equipment, etc.

Control Subtotal 2 2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.6 74 Knowledge of EOP implementation hierarchy and coordination 2.4.16 with other support procedures or guidelines such as, operating 3.5 75 4.

Emergency procedures, abnormal operating procedures, and severe Procedures / accident management guidelines.

Plan Subtotal 2 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 2/1 215004 K6.06 Importance rating < 2.5 (2.2) 2/2 245000 K6.07 Importance rating < 2.5 (2.4) 2/2 259001 K6.08 Importance rating < 2.5 (2.1) 2/1 263000 K1.03 De-selected for exam balance. K1 was oversampled.

2/1 400000 K1.04 De-selected for exam balance. K1 was oversampled.

2/1 215005 K6.05 De-selected for exam balance. K6 was oversampled.

2/1 211000 K5.05 De-selected, N/A for GGNS 2/1 205000 K4.04 De-selected due to lack of training material 2/2 201001 K1.05 De-selected, N/A for GGNS 1/1 295018 AK3.07 De-selected due to a lack of adequate distractors 3 2.1.31 De-selected due to difficulty in writing generic question 2/1 259002 K6.08 De-selected, N/A for GGNS 1/1 295003 2.1.31 De-selected due to difficulty in writing generic question 1/1 295028 2.1.28 De-selected due to difficulty in writing generic question 2/1 209001 2.1.19 De-selected due to lack of familiarity 2/1 262002 A1.02 De-selected due to lack of training material (Changed to Knowledge) 1/1 295016 2.2.12 De-selected due to a lack of adequate distracters 2/2 201005 A1.01 De-selected No longer used at GGNS Ref, EC-49891, 49880 2/2 226001 K5.06 De-selected N/A for GGNS 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: October 17, 2014 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 6 1 7 Emergency &

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

Plant 2 12 2 1 3 Systems Tier Totals 38 6 2 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).