Text

12 Final Outlines
	ML13099A291
Person / Time
Site:	Grand Gulf
Issue date:	12/10/2012
From:	Chris Steely; Operations Branch IV
To:	; Entergy Operations
	laura hurley
References
	ES-401, ES-401-1
	Download: ML13099A291 (36)
	v • d • e

ES-401 BWR Examination Outline - RO Form ES-401-1 Facility: Grand Gulf Nuclear Station Date of Exam: October 19,2012 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 3 3 4 3 4 20 7 Emergency &

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

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 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 - RO 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 #

1 2 3 1 2 295001 Partial or Complete Loss of Forced X Ability to operate and/or monitor the following as 3.5 15 Core Flow Circulation / 1 & 4 they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: AA1.01 Recirculation System, 55.41(b)(7) & (10)

Ability to determine and/or interpret the following as 295003 Partial or Complete Loss of AC / 6 X they apply to PARTIAL OR COMPLETE LOSS OF 3.5 14 A.C. POWER : AA2.04 System lineups 55.41(b)(10)

G2.1.7 Ability to evaluate plant performance and 295004 Partial or Total Loss of DC Pwr / 6 X make operational judgments based on operating 4.4 61 characteristics, reactor behavior, and instrument interpretation. 55.41(b)(10)

Knowledge of the reasons for the following 295005 Main Turbine Generator Trip / 3 X responses as they apply to MAIN TURBINE 3.8 5 GENERATOR TRIP: AK3.07 Bypass valve operation 55.41(b)(5)

Knowledge of the operational implications of the 295006 SCRAM / 1 X following concepts as they apply to SCRAM : 3.7 16 AK1.01 Decay heat generation and removal 55.41(b)(8) & (10)

Ability to determine and/or interpret the following as 295016 Control Room Abandonment / 7 X they apply to CONTROL ROOM ABANDONMENT: 4.2 17 AA2.02 Reactor water level 55.41(b)(10)

Knowledge of the reasons for the following 295018 Partial or Total Loss of CCW / 8 X responses as they apply to PARTIAL OR 2.9 46 COMPLETE LOSS OF COMPONENT COOLING WATER : AK3.01 Isolation of non-essential heat loads 55.41(b)(10)

Knowledge of the interrelations between PARTIAL 295019 Partial or Total Loss of Inst. Air / 8 X OR COMPLETE LOSS OF INSTRUMENT AIR and 3.8 48 the following: AK2.01 CRD hydraulics 55.41(b)(7) &

(10)

Ability to operate and/or monitor the following as 295021 Loss of Shutdown Cooling / 4 X they apply to LOSS OF SHUTDOWN COOLING: 3.0 49 AA1.05 Reactor recirculation 55.41(b)(10) 295023 Refueling Acc / 8 X G2.1.27 Knowledge of system purpose and/or 3.9 6 function. 55.41(b)(7)

Knowledge of the operational implications of the 295024 High Drywell Pressure / 5 X following concepts as they apply to HIGH 4.1 18 DRYWELL PRESSURE: EK1.01 Drywell integrity 55.41(b)(8) & (9)

Knowledge of the operational implications of the 295025 High Reactor Pressure / 3 X following concepts as they apply to HIGH 3.5 47 REACTOR PRESSURE: EK1.06 Pressure effects on reactor water level 55.41(b)(5)

Knowledge of the reasons for the following 295026 Suppression Pool High Water X responses as they apply to SUPPRESSION POOL 3.9 50 Temp. / 5 HIGH WATER TEMPERATURE: EK3.05 Reactor SCRAM 55.41(b)(10) 295027 High Containment Temperature / 5 X G2.2.38 Knowledge of conditions and limitations in 3.6 7 the facility license. 55.41(b)(10)

Knowledge of the interrelations between HIGH 295028 High Drywell Temperature / 5 X DRYWELL TEMPERATURE and the following: 3.2 8 EK2.02 Components internal to the drywell 55.41(b)(7)

Ability to determine and/or interpret the following as 295030 Low Suppression Pool Wtr Lvl / 5 X they apply to LOW SUPPRESSION POOL WATER 3.7 60 LEVEL: EA2.03 Reactor pressure 55.41(b)(10)

Ability to operate and/or monitor the following as 295031 Reactor Low Water Level / 2 X they apply to REACTOR LOW WATER LEVEL: 3.7 52 EA1.07 Safety/relief valves 55.41(b)(7)

Knowledge of the interrelations between SCRAM 295037 SCRAM Condition Present X CONDITION PRESENT AND REACTOR POWER 4.0 54 and Reactor Power Above APRM ABOVE APRM DOWNSCALE OR UNKNOWN and Downscale or Unknown / 1 the following: EK2.07 Neutron monitoring system 55.41(b)(10) 295038 High Off-site Release Rate / 9 G2.4.49 Ability to perform without reference to 600000 Plant Fire On Site / 8 X procedures those actions that require immediate 4.6 53 operation of system components and controls.

55.41(b)(10)

Ability to operate and/or monitor the following as l 700000 Generator Voltage and Electric Grid X they apply to GENERATOR VOLTAGE AND 3.6 19 Disturbances / 6 ELECTRIC GRID DISTURBANCES: AA1.01 Grid frequency and voltage 55.41(b)(5) & (10)

K/A Category Totals: 3 3 3 4 3 4 Group Point Total: 20

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline - RO 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 Knowledge of the interrelations between HIGH 295008 High Reactor Water Level / 2 X REACTOR WATER LEVEL and the following: AK2.06 3.4 11 RCIC 55.41(b)(7) 295009 Low Reactor Water Level / 2 Knowledge of the operational implications of the 295010 High Drywell Pressure / 5 X following concepts as they apply to HIGH DRYELL 3.2 12 PRESSURE: AK1.03 Temperature increases 55.41(b)(10) 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 G2.4.4 Ability to recognize abnormal indications for 295013 High Suppression Pool Temp. / 5 X system operating parameters that are entry-level 4.5 20 conditions for emergency and abnormal operating procedures. 55.41(b)(10) 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 Ability to operate and/or monitor the following as they 295022 Loss of CRD Pumps / 1 X apply to LOSS OF CRD PUMPS: AA1.02 RPS 3.6 21 55.41(b)(10) 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 Ability to determine and/or interpret the following as 295034 Secondary Containment X they apply to SECONDARY CONTAINMENT 3.8 13 Ventilation High Radiation / 9 VENTILATION HIGH RADIATION: EA2.01 Ventilation radiation levels 55.41(b)(10)

Knowledge of the reasons for the following responses 295035 Secondary Containment High X as they apply to SECONDARY CONTAINMENT HIGH 3.3 22 Differential Pressure / 5 DIFFERENTIAL PRESSURE: EK3.02 Secondary containment ventilation response 55.41(b)(4) & (5)

Ability to operate and/or monitor the following as 295036 Secondary Containment High X they apply to SECONDARY CONTAINMENT HIGH 3.5 71 Sump/Area Water Level / 5 SUMP/AREA WATER LEVEL: EA1.02 Affected systems so as to isolate damaged portions 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 1 1 1 2 1 1 Group Point Total: 7

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline - RO 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 Knowledge of the effect that a loss or 203000 RHR/LPCI: Injection X malfunction of the following will have on the 3.0 23 Mode RHR/LPCI: INJECTION MODE: K6.10 Component cooling water systems 55.41(b)(7) 205000 Shutdown Cooling X G2.2.12 Knowledge of surveillance 3.7 24 procedures. 55.41(b)(10) 206000 HPCI 207000 Isolation (Emergency)

Condenser Knowledge of LOW PRESSURE CORE 209001 LPCS X SPRAY SYSTEM design feature(s) and/or 3.0 9 interlocks which provide for the following:

K4.02 Prevents water hammer 55.41(b)(7)

Knowledge of the effect that a loss or X malfunction of the following will have on the 2.8 25 LOW PRESSURE CORE SPRAY SYSTEM:

K6.05 ECCS room cooler(s) 55.41(b)(7) &

(10)

Knowledge of the effect that a loss or 209002 HPCS X malfunction of the HIGH PRESSURE CORE 3.9 26 SPRAY SYSTEM (HPCS) will have on following: K3.03 Adequate core cooling 55.41(b)(7) & (10)

Knowledge of the physical connections and/or 211000 SLC X cause-effect relationships between STANDBY 3.4 10 LIQUID CONTROL SYSTEM and the following: K1.05 RWCU 55.41(b)(7)

Knowledge of the operational implications of 212000 RPS X the following concepts as they apply to 3.3 27 REACTOR PROTECTION SYSTEM: K5.02 Specific logic arrangements 55.41(b)(5) 215003 IRM Ability to (a) predict the impacts of the 215004 Source Range Monitor X following on the SOURCE RANGE MONITOR 3.0 28 (SRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.03 Stuck detector 55.41(b)(5) & (10)

Knowledge of the physical connections and/or 215005 APRM / LPRM X cause-effect relationships between 3.6 55 AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following: K1.09 Reactor recirculation system 55.41(b)(7)

Ability to monitor automatic operations of the 217000 RCIC X REACTOR CORE ISOLATION COOLING 3.6 56 SYSTEM (RCIC) including: A3.02 Turbine startup 55.41(b)(7)

Ability to manually operate and/or monitor in X the control room: A4.06 Suppression pool 3.6 29 level 55.41(b)(7) & (10)

Knowledge of electrical power supplies to the 218000 ADS X following: K2.01 ADS logic . 55.41(b)(8) 3.1 1 G2.1.28 Knowledge of the purpose and 223002 PCIS/Nuclear Steam X function of major system components and 4.1 2 Supply Shutoff controls. 55.41(b)(7)

Knowledge of the physical connections and/or 239002 SRVs X cause-effect relationships between 3.6 4 RELIEF/SAFETY VALVES and the following:

K1.04 Main steam 55.41(b)(8)

Knowledge of RELIEF/SAFETY VALVES X design feature(s) and/or interlocks which 3.4 62 provide for the following: K4.04 Ensures even distribution of heat load to suppression pool, and adequate steam condensing 55.41(b)(7)

Ability to predict and/or monitor changes in 259002 Reactor Water Level X parameters associated with operating the 3.8 33 Control REACTOR WATER LEVEL CONTROL SYSTEM controls including: A1.03 Reactor power 55.41(b)(5) & (10)

Ability to predict and/or monitor changes in 261000 SGTS X parameters associated with operating the 2.9 63 STANDBY GAS TREATMENT SYSTEM controls including: A1.01 System flow 55.41(b)(7)

Ability to (a) predict the impacts of the 262001 AC Electrical X following on the A.C. ELECTRICAL 3.8 69 Distribution DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.04 Types of loads that, if deenergized, would degrade or hinder plant operation 55.41(b)(5) & (10)

Knowledge of the effect that a loss or 262002 UPS (AC/DC) X malfunction of the UNINTERRUPTABLE 2.9 38 POWER SUPPLY (A.C./D.C.) will have on following: K3.02 Recirculation pump speed 55.41(b)(7)

Knowledge of electrical power supplies to the 263000 DC Electrical X following: K2.01 Major D.C. loads 55.41(b)(7) 3.1 30 Distribution X G2.2.22 Knowledge of limiting conditions for 4.0 34 operations and safety limits. 55.41(b)(8) &

(10)

Ability to (a) predict the impacts of the 264000 EDGs X following on the EMERGENCY 2.9 57 GENERATORS (DIESEL/JET) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.04 Consequences of operating under/over excited 55.41(b)(5) &

(10)

Knowledge of the effect that a loss or X malfunction of the EMERGENCY 4.1 51 GENERATORS (DIESEL/JET) will have on following: K3.03 Major loads powered from electrical buses fed by the emergency generator(s) 55.41(b)(7)

Knowledge of the operational implications of 300000 Instrument Air X the following concepts as they apply to the 2.5 35 INSTRUMENT AIR SYSTEM: K5.01 Air compressors 55.41(b)(4) & (5) & (7)

Ability to manually operate and / or monitor in X the control room: A4.01 Pressure gauges 2.6 3 55.41(b)(4)

Ability to predict and / or monitor changes in 400000 Component Cooling X parameters associated with operating the 2.7 58 Water CCWS controls including: A1.03 CCW Pressure 55.41(b)(5) & (10)

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

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline - RO 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 Knowledge of the physical connections 201001 CRD Hydraulic X and/or cause-effect relationships 3.1 31 between CONTROL ROD DRIVE HYDRAULIC SYSTEM and the following: K1.09 Plant air systems 55.41(b)(6) 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS Knowledge of ROD CONTROL AND 201005 RCIS X INFORMATION SYSTEM (RCIS) 3.5 32 design feature(s) and/or interlocks which provide for the following: K4.06 Rod pattern controller rod blocks 55.41(b)(7) 201006 RWM Ability to (a) predict the impacts of the 202001 Recirculation X following on the RECIRCULATION 3.1 36 SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.08 Recirculation flow mismatch 55.41(b)(5) & (10) 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode Ability to (a) predict the impacts of the 233000 Fuel Pool Cooling/Cleanup X following on the FUEL POOL COOLING 2.5 64 AND CLEAN-UP ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.16 Loss of coolant accident signal 55.41(b)(5) &

(10) 234000 Fuel Handling Equipment

Knowledge of electrical power supplies 239001 Main and Reheat Steam X to the following: K2.01 Main steam 3.2 37 isolation valve solenoids 55.41(b)(7)

Ability to manually operate and/or 239003 MSIV Leakage Control X monitor in the control room: A4.03 Main 3.3 39 steamline pressures 55.41(b)(7)

Knowledge of the operational 241000 Reactor/Turbine Pressure X Implications of the following concepts as 2.8 65 Regulator they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM:

K5.05 Turbine inlet pressure vs. turbine load 55.41(b)(5) 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater X G2.1.30 Ability to locate and operate 4.4 66 components, including local controls.

55.41(b)(7) & (10)

Knowledge of the effect that a loss or 268000 Radwaste X malfunction of the RADWASTE will have 2.7 70 on following: K3.04 Drain sumps 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation Ability to monitor automatic operations of 290001 Secondary CTMT X the SECONDARY CONTAINMENT 3.9 59 including: A3.01 Secondary containment isolation 55.41(b)(7)

Knowledge of the effect that a loss or 290003 Control Room HVAC X malfunction of the following will have on 2.6 68 the CONTROL ROOM HVAC: K6.04 Fire protection 55.41(b)(7)

Knowledge of the effect that a loss or 290002 Reactor Vessel Internals X malfunction of the REACTOR VESSEL 3.1 67 INTERNALS will have on following:

K3.07 Nuclear boiler instrumentation 55.41(b)(7)

K/A Category Point Totals: 1 1 2 1 1 1 0 2 1 1 1 Group Point Total: 12

ES-401 Generic Knowledge and Abilities Outline (Tier 3) - RO Form ES-401-3 Facility: Grand Gulf Nuclear Station Date of Exam: October 19, 2012 Category K/A # Topic RO SRO-Only IR # IR #

2.1.2 Knowledge of operator responsibilities during all modes of plant 4.1 40 operation. 55.41(b)(10) 1.

Conduct 2.1.36 Knowledge of procedures and limitations involved in core 3.0 72 of Operations alterations. 55.41(b)(10) 2.1.37 Knowledge of procedures, guidelines, or limitations associated 4.3 41 with reactivity management. 55.41(b)(1)

Subtotal 3 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.0 42 55.41(b)(5)

2. 2.2.39 Knowledge of less than or equal to one hour Technical 3.9 73 Equipment Specification action statements for systems. 55.41(b)(10)

Control 2.2.41 Ability to obtain and interpret station electrical and mechanical 3.5 43 drawings. 55.41(b)(10)

Subtotal 3 2.3.7 Ability to comply with radiation work permit requirements during 3.5 44 normal or abnormal conditions. 55.41(b)(12)

3. 2.3.14 Knowledge of radiation or contamination hazards that may arise 3.4 45 Radiation Control during normal, abnormal, or emergency conditions or activities.

55.41(b)(12)

Subtotal 2 2.4.4 Ability to recognize abnormal indications for system operating 4.5 74 parameters that are entry level conditions for emergency and

4. abnormal operating procedures. 55.41(b)(10)

Emergency Procedures / Plan 2.4.25 Knowledge of fire protection procedures. 55.41(b)(10) 3.3 75 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 1/1 295016 AA2.05 Cannot create an operationally valid question to associate Control Room Abandonment with the concept of determining or interpreting drywell pressure, for two reasons: 1) neither the Remote Shutdown Panels, nor the Alternate Shutdown Panels have drywell pressure indication; and 2) although drywell pressure indication would still be available via SPDS in the TSC and EOF, once EP-3 (Containment Control) has been entered, there is no operational interest in knowing drywell pressure (i.e., EP-3 has no Drywell Pressure mitigation leg, nor is there any EP Figure (in EP-1) that uses drywell pressure as a parameter for making any EP related mitigation decisions). Remained within the AA2 subset of 295016 and randomly selected AA2.02 Reactor water level.

2/1 209001 K6.11 Cannot create a question that has even slightest discriminatory validity for K6.11 ADS. Once in the EPs (EP-2, or EP-2A),

operators manually inhibit ADS auto-initiation, never use Manual ADS initiation, and are permitted to intentionally Emergency Depressurize using at least 7 SRVs (whether they be ADS Valves, or any others among the 20 total SRVs). Remained within the K6 subset of 209001 and randomly selected K6.05 ECCS room cooler(s).

2/2 201002 K1.01 The RMCS System (201002) is not applicable for GGNS (BWR-6);

see the Systems Deleted section below. Randomly re-selected among Tier 2 / Group 2. The CRD Hydraulic System (201001) is the substitute system. Remained within the K1 subset (as was originally selected for RMCS) and randomly selected K1.09.

2/1 300000 K5.13 Cannot create a question that has even minimal discriminatory validity, nor one that is operationally valid, for K13 Filters. GGNS has only branch filters in each of the major air headers and these filters provide a singular function of keeping corrosion products and dirt within the header piping from reaching safety-related equipment. Procedurally, the Loss of Instrument Air ONEP does not even address these filters. Their only mention is to be found in the Instrument Air System SOI; that being a small section that instructs field operators on how to rotate them when needed.

Remained within the K5 subset of 300000 and selected the only other K5 statement with an Importance Rating of at least 2.5that statement is K5.01 Air compressors.

1/1 295018 AK3.06 Cannot create a question that has even minimal discriminatory validity, nor one that is operationally valid, for AK3.06 Increasing cooling water flow to heat exchangers. Not operationally valid because the Loss of CCW ONEP (abnormal) does not even address the potential for having to increase HX cooling water flow. Not discriminatory valid because no reasonably plausible distracters can be included in the answer choices. Remained within the AK3 subset of 295018 and randomly selected AK3.01 Isolation of non-essential heat loads.

2/1 217000 A3.05 Cannot create an operationally valid question for A3.05; operators simply ensure RCIC initiates (automatically or manually) and that once it has level can be restored and maintained in a prescribed bandnothing more to say. Remained within the A3 subset of 217000 and randomly selected A3.02 Turbine startup.

2/1 400000 A1.04 Cannot create an operationally valid question for A1.04 for two reasons: 1) at GGNS the only CCW related indication is for CCW Pumps Discharge Pressure, and 2) regarding Surge Tank Levelany question would be developed at the non-licensed operator level, rather than for the RO. Remained within the A1 subset of 400000 and randomly selected A1.03 CCW Pressure.

2/1 261000 A1.04 Cannot create a question without unacceptable overlap with the already written Question #6. Remained within the A1 subset of 261000 and randomly selected A1.01 System flow.

2/2 233000 A1.03 Cannot create a question that has even minimal discriminatory validity for this KA, for at least two reasons: 1) FPCCU has only three controls (Pump, F/D Bypass Valve, F/D Inlet Valve) and three indicators (Pool Temperature, Cask Pool Temperature, Drain Tank Level) in the control rooma question that asks how pool temperature would respond to stopping one (or both) of the two running FPCCU Pumps lacks any discrimination; a question that asks how pool temperature would respond to closing one (or both) of the F/D Inlet Valves (reducing system flow) lacks any discrimination; 2) manually opening one (or both) of the F/D Bypass Valves has no effect on system flow to the pool (i.e., pool temperature does not change). Similarly, neither Surge Tank Level (A1.01), nor Pool Level (A1.02) are affected by operating any of the three controls. A1.04 and A1.05 have Importance Ratings of 2.4. As such, this Exam Author randomly selected both a new KA Statement, and a specific KA within that subset. The substitute KA is A2.16 Loss of coolant accident signal.

3 2.1.32 Could not write a purely Tier 3 (i.e., non-system specific) question for the originally selected KA. Randomly selected 2.1.36, Knowledge of procedures and limitations involved in core alterations, as its substitute.

SYSTEMS DELETED 201002 Reactor Manual Control System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

201004 Rod Sequence Control System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

201006 Rod Worth Minimizer System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

214000 Rod Position Information System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

215002 Rod Block Monitor System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

206000 High Pressure Coolant Injection (HPCI) - System is not part of BWR-6 design.

207000 Isolation (Emergency) Condenser - System is not part of BWR-6 design.

230000 RHR/LPCI: Torus/Pool Spray Mode - System is not part of the BWR-6 Mark III Containment design.

ES-401 BWR Examination Outline - SRO Form ES-401-1 Facility: Grand Gulf Nuclear Station Date of Exam: December 7, 2012 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 3 4 7 Emergency &

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

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

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