ML090700411
| ML090700411 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/11/2009 |
| From: | Apger G NRC Region 4 |
| To: | Entergy Operations |
| References | |
| 50-416/09-301, 50-417/09-301, ES-401, ES-401-1 50-416/09-301, 50-417/09-301 | |
| Download: ML090700411 (28) | |
Text
E S-401 BWR Examination Outline Form ES-401-1 Facility: Grand Gulf Date of Exam: March 9, 2009 RO K/A Category Points SRO-Only Points Tier Group 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 3 3 3 4 3 4 20 3 4 7 2 1 1 1 1 1 2 1 7 2 1 3 1. Emergency &
Abnormal Plant Evolutions Tier Totals 4 4 4 4 N/A 5 5 N/A 5 27 5 5 10 1 3 2 2 3 2 3 2 2 2 2 3 26 2 3 5 2 1 1 1 2 1 1 1 1 1 1 1 12 2 1 3 2. Plant Systems Tier Totals 4 3 3 5 3 4 3 3 3 3 4 38 4 4 8 1 2 3 4 1 2 3 4 3. Generic Knowledge and Abilities Categories 3 3 2 2 10 3 2 1 1 7 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 ATier 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, 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. 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. 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.
E S-401 2 Form ES-401-1 ES-401 BWR Examination OutlineForm ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / 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
R S Ability to operate and/or monitor the Neutron monitoring system as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (CFR: 41.7 / 45.6) (AA1.06 - RO)
Ability to determine and/or interpret the jet pump operability as it applies to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (CFR: 41.10 / 43.5 / 45.13) (AA2.05 - SRO) 3.3 3.4 1R 1S 295003 Partial or Complete Loss of AC / 6
R
Knowledge of the operational implications of Load shedding as it applies to PARTIAL OR COMPLETE LOSS OF A.C. POWER (CFR: 41.8 to 41.10) (AK1.02) 3.1 2R 295004 Partial or Total Loss of DC Pwr / 6
R Ability to determine and/or interpret the extent of partial or complete loss of D.C. power as it applies to PARTIAL OR COMPLETE LOSS OF D.C. POWER (CFR: 41.10 / 43.5 / 45.13) (AA2.02) 3.5 3R 295005 Main Turbine Generator Trip / 3
R
Knowledge of the operational implications of Pressure effects on reactor level as it applies to MAIN TURBINE GENERATOR TRIP (CFR: 41.8 to 41.10) (AK1.03) 3.5 4R 295006 SCRAM / 1
RAbility to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 / 45.12 / 45.13)
(2.1.7) 4.4 5R 295016 Control Room Abandonment / 7
R SKnowledge of limiting conditions for operations and safety limits.
(CFR: 41.5 / 43.2 / 45.2) (2.2.22
- RO) Knowledge of abnormal condition procedures.
(CFR: 41.10 / 43.5 / 45.13) (2.4.11 - SRO) 4.0
4.2 6R
2S 295018 Partial or Total Loss of CCW / 8
R
Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and system loads (CFR: 41.7 / 45.8) (AK2.01) 3.3 7R 295019 Partial or Total Loss of Inst. Air / 8
R Ability to manage the control room crew during plant transients. (CFR: 41.10 / 43.5 / 45.12 / 45.13)
(2.1.6) 3.8 8R 295021 Loss of Shutdown Cooling / 4
R Ability to operate and/or monitor Alternate heat removal methods as they apply to LOSS OF SHUTDOWN COOLING (CFR: 41.7 / 45.6) (AA1.04) 3.7 9R 295023 Refueling Acc / 8
R Knowledge of the reasons for responses of interlocks associated with fuel handling equipment as they apply to REFUELING ACCIDENTS (CFR: 41.5 / 45.6) (AK3.02) (RO) 3.4 10R
295024 High Drywell Pressure / 5
R Ability to operate and/or monitor the emergency generators as they apply to HIGH DRYWELL PRESSURE (CFR: 41.7 / 45.6) (EA1.06) 3.7 11R 295025 High Reactor Pressure / 3
R
S Knowledge of the interrelations between HIGH REACTOR PRESSURE and the reactor/turbine pressure regulating system (Plant Specific) (CFR: 41.7 / 45.8) (EK2.08 - RO)
Ability to interpret and execute procedure steps.
(CFR: 41.10 / 43.5 / 45.12) (2.1.20 - SRO) 3.7 (R O) 4.6 (S R
O) 12R
3S 295026 Suppression Pool High Water Temp.
/ 5
S R Ability to determine and/or interpret reactor pressure as it applies to SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.10 / 43.5 / 45.13) (EA2.03 - SRO)
Knowledge of conservative decision making practices.
(CFR: 41.10 / 43.5 / 45.12) (2.1.39 -
RO) 4.
0 (S
R O)
3.6 (R O) 4S 13R 295027 High Containment Temperature / 5
R
Knowledge of the interrelations between HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) and the containment spray (plant-specific): (CFR: 41.7 / 45.8) (EK2.01) 3.2 14R 295028 High Drywell Temperature / 5
R SAbility to determine and/or interpret the Drywell pressure as it applies to HIGH DRYWELL TEMPERATURE : (CFR: 41.10 / 43.5 / 45.13) (EA2.04 - RO)
Knowledge of EOP mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) (2.4.6 - SRO) 4.1 (R O) 4.7 (S R O) 15R
5S 295030 Low Suppression Pool Wtr Lvl / 5
R Ability to determine and/or interpret the Suppression pool temperature as it applies to LOW SUPPRESSION POOL WATER LEVEL : (CFR: 41.10 / 43.5 / 45.13) (EA2.02) 3.9 16R 295031 Reactor Low Water Level / 2
R S Ability to operate and/or monitor low pressure core spray as it applies to REACTOR LOW WATER LEVEL : (CFR: 41.7 / 45.6) (EA1.03 -
RO) Ability to determine and/or interpret adequate core cooling as it applies to REACTOR LOW WATER LEVEL : (CFR: 41.10 / 43.5 / 45.13) (EA2.04 -
SRO) 4.4 4.
8 (S R O) 17R 6S 295037 SCRAM Condition Present and Power Above APRM Downscale R
Knowledge of the operational implications of the reactor pressure effects on reactor power as it
4.1 18R or Unknown / 1 applies to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: (CFR: 41.8 to 41.10) (EK1.01) 295038 High Off-site Release Rate / 9
R Knowledge of the reasons for emergency depressurization as it applies to HIGH OFF-SITE RELEASE RATE: (CFR: 41.5 / 45.6) (EK3.04) 3.6 19R 600000 Plant Fire On Site / 8
R S Knowledge of the reasons for actions contained in the abnormal procedure for plant fire on site as it applies to PLANT FIRE ON SITE: (AK3.04 - RO)
Ability to identify post-accident instrumentation. (CFR: 41.6 / 45.4) (2.4.3 - SRO) (REJECTED)
Knowledge of the emergency plan. (CFR: 43.5) (2.4.29 - SRO) 2.8 (R O) 4.4 (S R O) 20R
7S
K/A Category Totals:
3 3
3 4 3 R 3 S 4 R 4 S Group Point Total:
20/7 E S-401 3 Form ES-401-1 ES-401 BWR Examination OutlineForm ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / 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
R Ability to identify and interpret diverse indications to validate the response of another indication.
(CFR: 41.7 / 43.5 / 45.4) (2.1.45) 4.3 21R 295007 High Reactor Pressure / 3
295008 High Reactor Water Level / 2
295009 Low Reactor Water Level / 2
R Ability to determine and/or interpret Reactor water level as it applies to LOW REACTOR WATER LEVEL :(CFR: 41.10 / 43.5 / 45.13) (AA2.01) 4.2 22R 295010 High Drywell Pressure / 5
R
Knowledge of the operational implications of temperature increases as it applies to HIGH DRYWELL PRESSURE : (CFR: 41.8 to 41.10) (AK1.03) 3.2 23R 295011 High Containment Temp / 5
R Knowledge of the reasons for the increased containment cooling (Mark-III) response as it applies to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): (CFR: 41.5 /
45.6) (AK3.01) 3.6 24R 295012 High Drywell Temperature / 5
S Ability to determine and/or interpret the drywell temperature as it applies to HIGH DRYWELL TEMPERATURE : (CFR: 41.10 / 43.5 / 45.13) (AA2.01) 3.9 8S 295013 High Suppression Pool Temp. / 5
295014 Inadvertent Reactivity Addition / 1
295015 Incomplete SCRAM / 1
295017 High Off-site Release Rate / 9
R
Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the standby gas treatment/FRVS: (CFR: 41.7 / 45.8) (AK2.12) 3.4 25R 295020 Inadvertent Cont. Isolation / 5 & 7
295022 Loss of CRD Pumps / 1
R Knowledge of the operational implications of the Reactivity control concepts as they apply to LOSS OF CRD PUMPS: (CFR: 41.8 to 41.10) (AK1.02) 3.6 26R 295029 High Suppression Pool Wtr Lvl / 5
S Ability to determine and/or interpret reactor pressure as it applies to HIGH SUPPRESSION POOL WATER LEVEL: (CFR: 41.10 / 43.5 / 45.13) (EA2.02) 3.6 9S 295032 High Secondary Containment Area Temperature / 5
295033 High Secondary Containment Area Radiation Levels / 9
S Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12 / 43.4 / 45.9) (2.3.15)
3.1 10S 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
R Ability to determine and / or interpret the Hydrogen monitoring system availability as it applies to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: (CFR: 41.10 / 43.5 / 45.13) (EA2.01) 3.1 27R
K/A Category Point Totals:
1 1
1 1 2 R 2 S 1 R 1 S Group Point Total:
7/3 E S-401 4 Form ES-401-1 ES-401BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / 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
R Knowledge of how to conduct system lineups, such as valves , breakers, switches, etc. (CFR: 41.10 / 45.1 / 45.12) (2.1.29) 4.1 28R 205000 Shutdown Cooling
R
S Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on reactor water level (plant-specific): (CFR: 41.7 / 45.4) (K3.02 -
RO) Knowledge of procedures and limitations involved in core alterations.
(CFR: 41.10 / 43.6 / 45.7) (2.1.36 - SRO) 3.2(RO)
4.1(SR O) 29R
11S 206000 HPCI
207000 Isolation (Emergency)
Condenser
209001 LPCS
R Knowledge of the process for conducting special or infrequent tests.
(CFR: 41.10 / 43.3 / 45.13) (2.2.7) 2.9 30R 209002 HPCS
R
Knowledge of the effect that a loss or malfunction of the Suppression pool suction strainer (BWR-5,6) will have on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS): (CFR: 41.7 / 45.7) (K6.04) 2.5 31R 211000 SLC
R
Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on the core spray line break detection system (plant- specific): (CFR: 41.7 / 45.4) (K3.02) 3.0 32R 212000 RPS
R
Knowledge of electrical power supplies to the RPS motor-generator sets: (CFR: 41.7) (K2.01) 3.2 33R 215003 IRM
R
Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM design feature(s) and/or interlocks which provide for the rod withdrawal blocks: (CFR: 41.7) (K4.01) 3.7 34R 215004 Source Range Monitor
R
Knowledge of the effect that a loss or malfunction of the RPS will have on the SOURCE RANGE MONITOR (SRH) SYSTEM : (CFR: 41.7 / 45.7) (K6.01 - RO) 3.2(RO) 35R
SAbility to verify system alarm setpoints and operate controls identified in the alarm response manual.
(CFR: 41.10 / 43.5 / 45.3) (2.4.50 - SRO) This KA was rejected Ability to diagnose and recognize trends in a timely manner utilizing the appropriate control room reference material.
(CFR: 41.10 / 43.5 / 45.12). (G-2.4.47) 4.0 (SR O) 12S 215005 APRM / LPRM
R
Knowledge of the operational implications of Assignment of LPRM's to specific APRM channels as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM : (CFR: 41.5 / 45.3) (K5.06) 2.5 36R 217000 RCIC
R
R
Knowledge of electrical power supplies to the gland seal compressor (vacuum pump): (CFR: 41.7) (K2.04)
Knowledge of the effect that a loss or malfunction of the condensate storage and transfer system will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): (CFR: 41.7 / 45.7) (K6.04) 2.6 3.5 37R 38R 218000 ADS
R
R
Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the nuclear boiler instrument system:
(CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.03)
Ability to (a) predict the impacts of the Loss of A.C. or D.C. power to ADS valves on the AUTOMATIC DEPRESSURIZATION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) (A2.05) 3.7
3.4 39R
40R 223002 PCIS/Nuclear Steam Supply Shutoff
R
S Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including valve closures: (CFR: 41.5 / 45.5) (A1.02 - RO)
Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7 / 41.10 / 43.2 / 45.13) (2.2.39 - SRO) 3.7(RO)
4.5(SR O) 41R
13S 239002 SRVs
R
Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
ADS Actuation (CFR: 41.5 / 45.6) (A2.04) 4.1 42R 259002 Reactor Water Level Control
R Ability to monitor automatic operations of the REACTOR WATER LEVEL CONTROL SYSTEM including runout flow control (plant-specific): (CFR: 41.7 / 45.7) (A3.01) 3.0 43R 261000 SGTS
R S
Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including system flow: (CFR: 41.5 / 45.5) (A1.01 - RO)
Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High system pressure (plant-specific) (CFR: 41.5 / 45.6) (A2.14 - SRO) 2.9 (RO)
3.2(SR O) 44R
14S 262001 AC Electrical Distribution
R
R Knowledge of the operational implications of the following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION: principle involved with paralleling two A.C. sources (CFR: 41.5 / 45.3) (K5.01)
Ability to manually operate and/or monitor in the control room: voltage, current, power, and frequency on A.C. buses (CFR: 41.7 / 45.5 to 45.8) (A4.05) 3.1
3.3 45R
46R 262002 UPS (AC/DC)
R
R Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design feature(s) and/or interlocks which provide for the following: transfer from preferred power to alternate power supplies (CFR: 41.7) (K4.01)
Ability to manually operate and/or monitor in the control room: transfer from alternative source to preferred source (CFR: 41.7 / 45.5 to 45.8) (A4.01) 3.1
2.8 47R
48R 263000 DC Electrical Distribution R
S
Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUTION and Battery charger and battery: (CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.02 - RO)
Ability to (a) predict the impacts of Grounds on the D.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) (A2.01 - SRO) 3.2(RO)
3.2(
SR O) 49R
15S 264000 EDGs R Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for speed droop control: (CFR: 41.7) (K4.03) 2.5 50R 300000 Instrument Air
R
R Knowledge of the connections and / or cause- effect relationships between INSTRUMENT AIR SYSTEM and the cooling water to compressor: (CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.04 -
RO) Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including air temperature: (CFR: 41.7 / 45.7) (A3.02 -
RO) 2.8 2.9 51R
52R 400000 Component Cooling Water
R Knowledge of tagging and clearance procedures. (CFR: 41.10 / 45.13) (2.2.13) 4.1 53R
K/A Category Point Totals:
3 2
2 3
2 3
2 2 R 2 S 2
2 3 R 3 S Group Point Total:
26/5 E S-401 5 Form ES-401-1 ES-401 BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 2 (RO / 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
R Ability to manually operate and/or monitor the SDV isolation valve test switch in the control room: CFR: 41.7 / 45.5 to 45.8) (A4.06) 2.8 54R 201002 RMCS
201003 Control Rod and Drive Mechanism R
Knowledge of the physical connections and/or cause-effect relationships between CONTROL ROD AND DRIVE MECHANISM and the control rod drive hydraulic system: (CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.01) 3.2 55R 201004 RSCS
201005 RCIS
R 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.
(CFR: 41.5 / 43.5 / 45.12) (2.2.44) 4.2 56R 201006 RWM
202001 Recirculation
R
Knowledge of the effect that a loss or malfunction of the Control rod drive system (plant-specific) will have on the RECIRCULATION SYSTEM : (CFR: 41.7 / 45.7) (K6.05) 2.7 57R 202002 Recirculation Flow Control
S
Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation pump speed mismatch between loops. (CFR 41.5 / 45.6) (A2.04) 16S 204000 RWCU
214000 RPIS
215001 Traversing In-core Probe
S
215002 RBM
216000 Nuclear Boiler Inst.
R
Ability to predict and/or monitor changes in parameters associated with operating the NUCLEAR BOILER INSTRUMENTATION controls including recorders and meters: (CFR: 41.5 / 45.5) (A1.01) 3.4 58R 219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.
S
Ability to (a) predict the impacts of the Compressor trips (loss of air) (plant-specific) on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) (A2.08) 3.1 17S 226001 RHR/LPCI: CTMT Spray Mode
R
Knowledge of RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE design feature(s) and/or interlocks which provide for pump minimum flow protection: (CFR: 41.7) (K4.05) 2.5 59R 230000 RHR/LPCI: Torus/Pool Spray Mode
233000 Fuel Pool Cooling/Cleanup
S Knowledge of new and spent fuel movement procedures. (CFR: 41.10 / 43.7 / 45.13) (2.1.42) 3.4 18S 234000 Fuel Handling Equipment
239001 Main and Reheat Steam
239003 MSIV Leakage Control
241000 Reactor/Turbine Pressure Regulator
R
Knowledge of the operational Implications of turbine inlet pressure vs. reactor pressure as they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM: (CFR: 41.5 / 45.3) (K5.04) 3.3 60R 245000 Main Turbine Gen. / Aux.
R
Knowledge of the physical connections and/or cause-effect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the D. C . electrical distribution: (CFR: 41.2 to 41.9 / 45.7 to 45.8) (K1.09) 2.7 61R 256000 Reactor Condensate
R Ability to monitor automatic operations of the REACTOR CONDENSATE SYSTEM including pump starts: (CFR: 41.7 / 45.7) (A3.02) 3.0 62R 259001 Reactor Feedwater
R
Ability to (a) predict the impacts of following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of Extraction Steam (CFR: 41.5 / 45.6) (A2.04) 3.3 63R 268000 Radwaste
271000 Offgas
272000 Radiation Monitoring R Knowledge of RADIATION MONITORING System design feature(s) and/or interlocks which provide for redundancy: (CFR: 41.7) (K4.01) 2.7 64R 286000 Fire Protection
R
Knowledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on personnel protection: (CFR: 41.7 / 45.4) (K3.02) 3.2 65R 288000 Plant Ventilation
290001 Secondary CTMT
290003 Control Room HVAC
290002 Reactor Vessel Internals
K/A Category Point Totals:
1 1
1 2
1 1
1 1R 2 S 1
1 1 R 1 S Group Point Total:
12/3 E S-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Grand Gulf Date of Exam: 2009 RO SRO-Only Category K/A # Topic IR # IR # 2.1.13 Knowledge of facility requirements for controlling vital/controlled access. (CFR: 41.10 / 43.5 / 45.9 / 45.10) 2.5 66R
2.1.17 Ability to make accurate, clear, and concise verbal reports.
(CFR: 41.10 / 45.12 / 45.13)
3.9 67R
2.1.39 Knowledge of conservative decision making practices.
(CFR: 41.10 / 43.5 / 45.12)
3.6 68R
2.1.5 (S) Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
(CFR: 41.10 / 43.5 / 45.12)
3.9 19S 2.1.23 (S) Ability to perform specific system and integrated plant procedures during all modes of plant operation.
(CFR: 41.10 / 43.5 / 45.2 / 45.6)
4.4 20S 2.1.30 (S) Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7)
4.0 21S
- 1. Conduct of Operations Subtotal 3
3 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc. (CFR: 41.10 / 43.5 /
45.13) 2.6 69R
2.2.37 Ability to determine operability and/or availability of safety related equipment. (CFR: 41.7 / 43.5 / 45.12) 3.6 70R
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. (CFR: 41.5 / 43.5 / 45.12) 4.2 71R
2.2.25 (S) Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
(CFR: 41.5 / 41.7 / 43.2)
4.2 22S 2.2.42 (S) Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)
4.6 23S 2. Equipment Control Subtotal 3
2 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10) 3.2 72R
2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 / 43.4 / 45.10) 3.4 73R
2.3.11 (S) Ability to control radiation releases. (CFR: 41.11 / 43.4 /
45.10)
4.3 24S
- 3. Radiation Control Subtotal 2
1 2.4.13 Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10 / 45.12) 4.0 74R
2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. (CFR: 41.7 / 43.5 / 45.12) 4.0 75R
2.4.37 (S) Knowledge of the lines of authority during implementation of the emergency plan. (CFR: 41.10 / 45.13)
4.1 25S 4. Emergency Procedures /
Plan Subtotal 2
1 Tier 3 Point Total
10 7
E S-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection 2/1 206000 HPCI
This exam is being written for the BWR-6 design. This question is only applicable to the BWR-2, -3, and -4 designs.
2/1 207000 Isolation (Emergency)
Condenser This exam is being written for the BWR-6 design. This question is only applicable to the BWR-2 and -3 designs.
2/1 261000 SGTS
This exam is being written for a BWR-6 design, which includes Mark-III containment. The line item selected (A1.06) is specific for Mark-I containment.
1/1 295024 High Drywell Pressure The original random selection of EA1.16 involves containment/drywell vacuum breakers, and this plant does not include these. Drywell vacuum relief is provided for in the CGCS, but physical passive vacuum breakers are not
included.
1/1 295028 High Drywell Temperature This exam is being written for a BWR-6 design, which includes Mark-III containment. The line item selected (EA2.06) is specific for Mark-I containment.
2/2 230000 RHR/LPCI:
Torus/Pool Spray Mode This exam is being written for a BWR-6 design, which includes Mark-III containment. The system selected is specific for Mark-I containment.
2/1 263000 DC Electrical
Distribution For the selected item for an RO question (K1.03), it will be difficult to develop valid discriminatory answers.
3 G 2.1.30 A valid SRO question could not be developed for this KA. (Ability to locate and operate components, including local controls.) Another KA was randomly selected.
2/2 215001 A2.01
This KA was rejected due to it not being applicable to a Mark III containment. Another KA was randomly selected.
1/1 295028 G-2.4.18
This KA was rejected due to the fact that this was selected for a SRO question, and EOP bases knowledge is applicable to RO questions. Another generic Emergency Procedures/Plan KA was selected for the Safety Function.
1/1 295023 AA2.03
A valid SRO question could not be developed for this KA. Another safety function was selected, and a KA was randomly selected.
2/1 215004 G-2.4.50
This KA was rejected due to it being focused on actions found in the alarm cards making it an RO question. Another KA was randomly selected.
2/2 268000 A2.01
This KA was rejected due to not being able to write a valid RO question. Another KA was randomly selected.
1/1 600000 G2.4.3
This KA was rejected due to not being able to write a valid SRO question and another KA was selected.
E S-301 Administrative Topics Outline Form ES-301-1 Facility: _
Grand Gulf__________________ Date of Examination
_2009-03__ Administrative Topic (see Note)
Type Code* Describe activity to be performed Conduct of Operations
R, N Perform a Standby Liquid Control (SLC) storage tank operability surveillance.
Conduct of Operations
R, N Calculate time to boil following a loss of shutdown cooling.
Equipment Control R, N Prepare a tagout for the Division I EDG fuel oil transfer pump.
Radiation Control R, N Determine the Health Physics requirements associated with a given Radiological Work Permit (RWP).
Emergency Procedures/Plan
NA NA NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the adminis trative 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)
E S-301 Administrative Topics Outline Form ES-301-1 Facility: _
Grand Gulf__________________ Date of Examination:
_____________
Examination Level: RO SRO Operating Test Number:
_2009-03__ Administrative Topic (see Note)
Type Code* Describe activity to be performed Conduct of Operations D, N Review plant chemistry results versus the requirements in the Techni cal Specifications. (JPM
- 12) Conduct of Operations
R, N Review the results of a Jet Pump Surveillance.
Equipment Control
R, N Review a prepared tagout.
Radiation Control D, N Review a liquid radioactive waste release permit. (JPM 11) Emergency Procedures/Plan R, N Classify an event covered in an operating test scenario in accordance with the Emergency Operating Procedures (EOP). NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the adminis trative 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)
E S-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __
Grand Gulf
___________________ Date of Examination:
_____________
Exam Level: RO SRO-I SRO-U Operating Test No.: __
2009-03__ 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. Start RCIC in Pressure Control Mode (Suppression Pool to Suppression Pool)
S, C, N 3 b. Perform the full flow surveillance test on the High Pressure Core Spray (HPCS) system. (JPM 4)
S, C, A, EN, D 2 c. Place Division 1 Main Steam Leakage Control System (MSLCS) in service [perform in parallel with d. below].
S, C, L, EN, N, A 9 d. Start a Recirculation pump [perform in parallel with c.
above]. (JPM 13) S, C, L, D, A 4 e. Shift Residual Heat Removal (RHR) system from
Containment Spray to Suppr ession Pool Cooling mode.
S, C, L, N, EN, E 5 f. Restore offsite power to vital buses and remove Emergency Diesel Generator (EDG) from service.
S, C, EN, N 6 g. Bypass a Control Rod in Rod Panel Control (RPC).(JPM 15)
S, C, D 7 h. Shift Circulating Cooling Water (CCW) pump in service. (JPM 7)
S, C, D, A 8 In-Plant Systems
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Line up the Emergency Core Cooling System (ECCS)
to receive an alternate source of water. (JPM 8)
D, R 2
- j. Place an Uninterruptible Power Supply (UPS) inverter in service. (Used JPM 6, but modified to add alternate path) M, A 6 k. Perform a Standby Liquid Control (SLC) recirculation test (look at procedure for locations). (JPM 1)
D, R 1 @ 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 E S-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __
Grand Gulf
___________________ Date of Examination:
_____________
Exam Level: RO SRO-I SRO-U Operating Test No.: __
2009-03__ 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. Start RCIC in Pressure Control Mode (Suppression Pool to Suppression Pool).
S, C, N 3 b. Perform the full flow surveillance test on the High Pressure Core Spray (HPCS) system. (JPM 4)
S, C, A, EN, D 2 c. Place Division 1 Main Steam Leakage Control System (MSLCS) in service [perform in parallel with d. below].
S, C, L, EN, N, A 9 d. Start a Recirculation pump [perform in parallel with c.
above]. (JPM 13)
S, C, L, D, A 4 e. Shift Residual Heat Removal (RHR) system from Containment Spray to Suppre ssion Pool Cooling mode.
S, C, L, N, EN, E 5 f. Restore offsite power to vital buses and remove Emergency Diesel Generator (EDG) from service.
S, C, EN, N 6 g. Bypass a Control Rod in Rod Panel Control (RPC). (JPM 15) S, C, D 7 h. Shift Circulating Cooling Water (CCW) pump in service. (JPM 7)
S, C, D, A 8 In-Plant Systems
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Line up the Emergency Core Cooling System (ECCS)
to receive an alternate source of water. (JPM 8)
D, R 2 j. Place an Uninterruptible Power Supply (UPS) inverter in service. (Used JPM 6, with revision to add alternate path.)
M, A 6
- k. Perform a Standby Liquid Control (SLC) recirculation test (look at procedure for locations). (JPM 1)
D, R 1 @ 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 E S-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: __
Grand Gulf
___________________ Date of Examination:
_____________
Exam Level: RO SRO-I SRO-U Operating Test No.: __
2009-03__ 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. Perform the full flow surveillance test on the High Pressure Core Spray (HPCS) system. (JPM 4)
S, C, A, EN, D 2 b. Place Division 1 Main Steam Leakage Control System (MSLCS) in service. (manually place in service)
S, C, L, EN, N, A 9 Shift Residual Heat Removal (RHR) system from Containment Spray to Suppression Pool Cooling mode.
S, C, L, N, EN, E 5 In-Plant Systems
@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. Line up the Emergency Core Cooling System (ECCS) to receive an alternate source of water. (JPM 8)
D, R 2 j. Place an Uninterruptible Power Supply (UPS) inverter in service. (Used JPM 6, but revised to add alternate
path) M, A 6 k. Perform a Standby Liquid Control (SLC) recirculation test (look at procedure for locations). (JPM 1)
D, R 1 @ 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 ES-D-1 ES-D-2 ES-301-5
DUE TO EXAMINATION SCENARIO COMPROMISE DISCOVERED DURING ON-SITE VALIDATION, ALL OF THE DRAFT SCENARIOS WERE REMOVED FROM THE EXAMINATION.
TWO SCENARIOS WERE DEVELOPED ON-SITE DURING VALIDATION WEEK, AND THE FACILITY LICENSEE RETURNED THE FINAL EXAM INATION SCENARIO OUTLINES ALONG WITH THE SCENARIOS IN THEIR FINAL OPERATING EXAMINATION SUBMITTAL.
SEE THE FINAL OUTLINES FILE FOR THE ES-D-1 AND D-2 FORMS, AND THE ES-301-5 TRANSIENT AND EVENTS CHECKLIST.