ML22195A276
| ML22195A276 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/23/2021 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | |
| Baker R | |
| Shared Package | |
| ML21055A860 | List: |
| References | |
| Download: ML22195A276 (17) | |
Text
1 Facility:
Dresden Nuclear Power Station, Units 2 & 3 K/A Catalog Rev. 2 Rev.
1 Date of Exam:
11/01/2021 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
Total A2 G*
Total
- 1.
Emergency and Abnormal Plant Evolutions 1
2 3
4 4
3 4
20 3
4 7
2 2
1 1
1 1
1 7
2 1
3 Tier Totals 4
4 5
5 4
5 27 5
5 10
- 2.
Plant Systems 1
3 3
3 2
2 2
3 2
2 2
2 26 2
3 5
2 1
0 1
1 1
1 1
1 2
2 1
12 0
2 1
3 Tier Totals 4
3 4
3 3
3 4
3 4
4 3
38 4
4 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 2
2 3
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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. 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 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 a category 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.
G* Generic K/As These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
2 ES-401 BWR Examination Outline (Dresden)
Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
Item #
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
1 (295001) (APE 1)
PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION / 1 & 4 X
(295001AK3.05) Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (CFR: 41.5 / 45.6): Reduced loop operating requirements: Plant-Specific 3.2 1
(55) 2 (295003) (APE 3)
PARTIAL OR COMPLETE LOSS OF AC POWER / 6 X
(295003AA1.01) Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER (CFR: 41.7 / 45.6): A.C.
electrical distribution system 3.7 2
(13) 3 (295004) (APE 4)
PARTIAL OR COMPLETE LOSS OF DC POWER / 6 X
(295004AK2.03) Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following (CFR: 41.7 / 45.8): D.C. bus loads 3.3 3
(10) 4 (295005) (APE 5) MAIN TURBINE GENERATOR TRIP / 3 X
(295005AK2.07) Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following (CFR: 41.7 / 45.8): Reactor pressure control:
3.6 4
(42) 5 (295006) (APE 6)
SCRAM / 1 X
(295006AA2.04) Ability to determine and/or interpret the following as they apply to SCRAM (CFR: 41.10 / 43.5 /
45.13): Reactor pressure 4.1 5
(65) 6 (295016) (APE 16)
CONTROL ROOM ABANDONMENT / 7 X
(295016AA1.09) Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT (CFR: 41.7 / 45.6):
Isolation/emergency condenser(s): Plant-Specific 4.0 6
(3) 7 (295018) (APE 18)
PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW) / 8 X
(295018AA2.04) Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CFR:
41.10 / 43.5 / 45.13): System flow 2.9 7
(4) 8 (295019) (APE 19)
PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR / 8 X
(295019AA1.01) Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR (CFR: 41.7 / 45.6): Backup air supply 3.5 8
(14) 9 (295021) (APE 21)
LOSS OF SHUTDOWN COOLING / 4 X
(295021) (APE 21) LOSS OF SHUTDOWN COOLING /
4 (G2.4.31) EMERGENCY PROCEDURES / PLAN:
Knowledge of annunciator alarms, indications, or response procedures (CFR: 41.10 / 45.3).
4.2 9
(68) 10 (295023) (APE 23)
REFUELING ACCIDENTS / 8 X
(295023) (APE 23) REFUELING ACCIDENTS / 8 (G2.1.28) CONDUCT OF OPERATIONS: Knowledge of the purpose and function of major system components and controls (CFR: 41.7).
4.1 10 (39) 11 (295024) (EPE 1) HIGH DRYWELL PRESSURE
/ 5 X
(295024EK1.01) Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE: Drywell Integrity: Plant specific (CFR: 41.8 to 41.10) 4.1 11 (30) 12 (295025) (EPE 2) HIGH REACTOR PRESSURE
/ 3 X
(295025) (EPE 2) HIGH REACTOR PRESSURE / 3 (G2.2.42) EQUIPMENT CONTROL: Ability to recognize system parameters that are entry-level conditions for Technical Specifications (CFR: 41.7 / 41.10 / 43.2 / 43.3 /
45.3).
3.9 12 (16) 13 (295026) (EPE 3)
SUPPRESSION POOL HIGH WATER TEMPERATURE / 5 X
(295026EK3.02) Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE (CFR: 41.5 /
45.6): Suppression pool cooling 3.9 13 (62)
3 Item #
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
14 (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY) / 5 X
(295028EA1.01) Ability to operate and/or monitor the following as they apply to HIGH DRYWELL TEMPERATURE (CFR: 41.7 / 45.6): Drywell spray:
Mark-I&II 3.8 14 (46) 15 (295030) (EPE 7) LOW SUPPRESSION POOL WATER LEVEL / 5 X
(295030EK1.02) Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL (CFR: 41.8 to 41.10): Pump NPSH 3.5 15 (31) 16 (295031) (EPE 8)
REACTOR LOW WATER LEVEL / 2 X
(295031EA2.03) Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL (CFR: 41.10 / 43.5 / 45.13): Reactor pressure 4.2 16 (32) 17 (295037) (EPE 14)
SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN / 1 X
(295037EK3.05) Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN (CFR:
41.5 / 45.6): Cold shutdown boron weight: Plant-Specific 3.2 17 (33) 18 (295038) (EPE 15)
HIGH OFFSITE RADIOACTIVITY RELEASE RATE / 9 X
(295038EK2.05) Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following (CFR: 41.7 / 45.8): Site emergency plan 3.7 18 (34) 19 (600000) (APE 24)
PLANT FIRE ON SITE /
8 X
(600000) (APE 24) PLANT FIRE ON SITE / 8 (G2.2.39)
EQUIPMENT CONTROL: Knowledge of less than or equal to one hour Technical Specification action statements for systems (CFR: 41.7 / 41.10 / 43.2 /
45.13).
3.9 19 (64) 20 (700000) (APE 25)
GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES / 6 X
(700000AK3.01) Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES (CFR: 41.5 / 45.6): Reactor and turbine trip criteria 3.9 20 (74) 21 (295001) (APE 1)
PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION / 1 & 4 X
(295001) (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION / 1 & 4 (G2.4.6)
EMERGENCY PROCEDURES / PLAN: Knowledge of EOP mitigation strategies (CFR: 41.10 / 43.5 / 45.13).
4.7 76
(??)
22 (295004) (APE 4)
PARTIAL OR COMPLETE LOSS OF DC POWER / 6 X
(295004AA2.02) Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER (CFR: 41.10 / 43.5
/ 45.13): Extent of partial or complete loss of D.C.
power 3.9 77 (87) 23 (295019) (APE 19)
PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR / 8 X
(295019AA2.01) Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR (CFR: 41.10
/ 43.5 / 45.13): Instrument air system pressure 3.6 78 (84) 24 (295023) (APE 23)
REFUELING ACCIDENTS / 8 X
(295023) (APE 23) REFUELING ACCIDENTS / 8 (G2.4.41) EMERGENCY PROCEDURES / PLAN:
Knowledge of the emergency action level thresholds and classifications (CFR: 41.10 / 43.5 / 45.11).
4.6 79 (80) 25 (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY) / 5 X
(295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY) / 5 (G2.4.47)
EMERGENCY PROCEDURES / PLAN: Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material (CFR: 41.10 / 43.5 / 45.12).
4.2 80 (83) 26 (295031) (EPE 8)
REACTOR LOW WATER LEVEL / 2 X
(295031EA2.01) Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL (CFR: 41.10 / 43.5 / 45.13): Reactor water level 4.6 81 (85)
4 Item #
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
27 (295038) (EPE 15)
HIGH OFFSITE RADIOACTIVITY RELEASE RATE / 9 X
(295038) HIGH OFFSITE RADIOACTIVITY RELEASE RATE / 9 (G2.4.30) EMERGENCY PROCEDURES:
Knowledge of events related to system operation/
status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator (CFR 41.10 / 43.5 / 45.11).
4.1 82 (98)
(295027) (EPE 4) HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)
/ 5 K/A Category Totals:
2 3
4 4
3(3) 4(4)
Group Point Total:
27
5 ES-401 BWR Examination Outline (Dresden)
Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
28 (295002) (APE 2) LOSS OF MAIN CONDENSER VACUUM / 3 X
(295002AK1.03) Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAIN CONDENSER VACUUM (CFR: 41.8 to 41.10): Loss of heat sink 3.6 21 (38) 29 (295007) (APE 7) HIGH REACTOR PRESSURE
/ 3 X
(295007AK1.03) Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE (CFR: 41.8 to 41.10):
Pressure effects on reactor power 3.8 22 (75) 30 (295010) (APE 10)
HIGH DRYWELL PRESSURE / 5 X
(295010AA1.01) Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE (CFR: 41.7 / 45.6): Drywell ventilation/cooling 3.4 23 (17) 31 (295013) (APE 13)
HIGH SUPPRESSION POOL TEMPERATURE.
/ 5 X
(295013AK3.02) Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL TEMPERATURE (CFR: 41.5 /
45.6): Limiting heat additions 3.6 24 (69) 32 (295014) (APE 14)
INADVERTENT REACTIVITY ADDITION / 1 X
(295014AA2.05) Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION (CFR: 41.10 / 43.5 / 45.13): Violation of safety limits 4.2 25 (43) 33 (295032) (EPE 9) HIGH SECONDARY CONTAINMENT AREA TEMPERATURE / 5 X
(295032EK2.05) Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA TEMPERATURE and the following (CFR: 41.7 / 45.8):
Temperature sensitive instrumentation 3.2 26 (70) 34 (500000) (EPE 16)
HIGH CONTAINMENT HYDROGEN CONCENTRATION / 5 X
(500000) (EPE 16) HIGH CONTAINMENT HYDROGEN CONCENTRATION / 5 (G2.1.32) CONDUCT OF OPERATIONS: Ability to explain and apply system limits and precautions (CFR: 41.10 / 43.2 / 45.12).
3.8 27 (72) 35 (295009) (APE 9) LOW REACTOR WATER LEVEL / 2 X
(295009) (APE 9) LOW REACTOR WATER LEVEL / 2 (G2.4.21) EMERGENCY PROCEDURES / PLAN:
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).
4.6 83 (90) 36 (295029) (EPE 6) HIGH SUPPRESSION POOL WATER LEVEL / 5 X
(295029EA2.03) Ability to determine and/or interpret the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL (CFR: 41.10 / 43.5 / 45.13):
Drywell/containment water level 3.5 84 (88) 37 (295036) (EPE 13)
SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL / 5 X
(295036EA2.03) Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL (CFR: 41.10 / 43.5 / 45.13): Cause of the high water level 3.8 85 (81)
(295008) (APE 8) HIGH REACTOR WATER LEVEL / 2 (295011) (APE 11)
HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY)
/ 5 (295012) (APE 12)
HIGH DRYWELL TEMPERATURE / 5
6 Item #
E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
(295015) (APE 15)
INCOMPLETE SCRAM
/ 1 -- DELETED (295017) (APE 17)
ABNORMAL OFFSITE RELEASE RATE / 9 (295020) (APE 20)
INADVERTENT CONTAINMENT ISOLATION / 5 & 7 (295022) (APE 22)
LOSS OF CONTROL ROD DRIVE PUMPS / 1 (295033) (EPE 10)
HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS / 9 (295034) (EPE 11)
SECONDARY CONTAINMENT VENTILATION HIGH RADIATION / 9 (295035) (EPE 12)
SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE / 5 K/A Category Totals:
2 1
1 1
1(2) 1(1)
Group Point Total:
10
7 ES-401 BWR Examination Outline (Dresden)
Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 2/Group 1 (RO/SRO)
Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
38 (203000) (SF2, SF4 RHR/LPCI) RHR/LPCI:
INJECTION MODE X
(203000A1.01) Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI:INJECTION MODE (PLANT SPECIFIC) controls including (CFR: 41.5
/ 45.5): Reactor water level 4.2 28 (22) 39 (205000) (SF4 SCS)
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)
X (205000K4.03) Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlocks which provide for the following (CFR: 41.7): Low reactor water level: Plant-Specific 3.8 29 (21) 40 (206000) (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM X
(206000K2.03) HIGH PRESSURE COOLANT INJECTION SYSTEM:
Knowledge of electrical power supplies to the following (CFR: 41.7):
Initiation logic:BWR-2,3,4 2.8 30 (66) 41 (207000) (SF4 IC)
ISOLATION (EMERGENCY)
CONDENSER X
(217000K5.07) Knowledge of the operational implications of the following concepts as they apply to ISOLATION (EMERGENCY)
CONDENSER: (CFR: 41.5 /
45.3): Temperature sensing 2.7 31 (45) 42 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X
(209001K3.01) Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following (CFR: 41.7 / 45.4):
Reactor water level 3.8 32 (37) 43 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X
(209001K5.05) Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM (CFR:
41.5 / 45.3): System venting 2.5 33 (54) 44 (211000) (SF1 SLCS)
STANDBY LIQUID CONTROL SYSTEM X
(211000K3.01) Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following (CFR:
41.7 / 45.4): Ability to shutdown the reactor in certain conditions 4.3 34 (28) 45 (212000) (SF7 RPS)
(212000A1.06) Ability to predict and/or monitor changes in parameters associated with operating the REACTOR PROTECTION SYSTEM controls including (CFR:
41.5 / 45.5): Reactor power 4.2 35 (53)
8 Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
46 (212000) (SF7 RPS)
(212000K1.13) Knowledge of the physical connections and/or cause-effect relationships between REACTOR PROTECTION SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): Containment pressure 3.5 36 (51) 47 (215003) (SF7 IRM)
INTERMEDIATE RANGE MONITOR SYSTEM X
(215003A2.01) Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) 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):
Power supply degraded 2.8 37 (73) 48 (215004) (SF7 SRMS)
SOURCE RANGE MONITOR SYSTEM X
(215004A4.01) SOURCE RANGE MONITOR (SRM)
SYSTEM: Ability to manually operate and/or monitor in the control room (CFR: 41.7 /
45.5 to 45.8): SRM count rate and period 3.9 38 (29) 49 (215005) (SF7 PRMS)
AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X
(215005K4.08) Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following (CFR: 41.7):
Sampling of overall core power in each APRM (accomplished through LPRM assignments and symmetrical rod patterns) 2.7 39 (52) 50 (218000) (SF3 ADS)
AUTOMATIC DEPRESSURIZATION SYSTEM X
(218000A1.03) Ability to predict and/or monitor changes in parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including (CFR: 41.5 / 45.5): ADS valve air supply pressure:
Plant-Specific 3.2 40 (44) 51 (223002) (SF5 PCIS)
PRIMARY CONTAINMENT ISOLATION SYSTEM /
NUCLEAR STEAM SUPPLY SHUTOFF X
(223002K1.20) Knowledge of the physical connections and/or cause-effect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the following (CFR: 41.2 to 41.9 /
45.7 to 45.8): A.C.
distribution: Plant-Specific 2.8 41 (71) 52 (239002) (SF3 SRV)
(239002A3.03) Ability to monitor automatic operations of the RELIEF/SAFETY VALVES including (CFR:
41.7 / 45.7): Tail pipe temperatures 3.6 42 (59)
9 Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
53 (259002) (SF2 RWLCS)
REACTOR WATER LEVEL CONTROL SYSTEM X
(259002A4.03) REACTOR WATER LEVEL CONTROL SYSTEM: Ability to manually operate and/or monitor in the control room (CFR: 41.7 /
45.5 to 45.8): All individual component controllers when transferring from manual to automatic modes 3.8 43 (23) 54 (259002) (SF2 RWLCS)
REACTOR WATER LEVEL CONTROL SYSTEM X
(259002) (SF2 RWLCS)
REACTOR WATER LEVEL CONTROL SYSTEM (G2.4.35) EMERGENCY PROCEDURES / PLAN:
Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects (CFR:
41.10 / 43.5 / 45.13).
3.8 44 (47) 55 (261000) (SF9 SGTS)
STANDBY GAS TREATMENT SYSTEM X
(261000K1.08) Knowledge of the physical connections and/or cause-effect relationships between STANDBY GAS TREATMENT SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): Process radiation monitoring system 2.8 45 (24) 56 (262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION X
(262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION (G2.2.37)
EQUIPMENT CONTROL:
Ability to determine operability and/or availability of safety related equipment (CFR: 41.7 / 43.5 / 45.12).
3.6 46 (25) 57 (262002) (SF6 UPS)
UNINTERRUPTABLE POWER SUPPLY (AC/DC)
X (262002K6.02) Knowledge of the effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) (CFR: 41.7 /
45.7): D.C. electrical power 2.8 47 (48) 58 (263000) (SF6 DC) DC ELECTRICAL DISTRIBUTION X
(263000A3.01) Ability to monitor automatic operations of the D.C. ELECTRICAL DISTRIBUTION including (CFR: 41.7 / 45.7): Meters, dials, recorders, alarms, and indicating lights 3.2 48 (27) 59 (264000) (SF6 EGE)
EMERGENCY GENERATORS (DIESEL/JET)
X (264000K3.03) Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on following (CFR: 41.7 / 45.4):
Major loads powered from electrical buses fed by the emergency generator(s) 4.1 49 (49) 60 (264000) (SF6 EGE)
EMERGENCY GENERATORS (DIESEL/JET)
X (264000K6.02) Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET) (CFR: 41.7 /
45.7): Fuel oil pumps 3.6 50 (36)
10 Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
61 (300000) (SF8 IA)
INSTRUMENT AIR SYSTEM X
(300000A2.01) Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:
41.5 / 45.6): Air dryer and filter malfunctions 2.9 51 (5) 62 (300000) (SF8 IA)
INSTRUMENT AIR SYSTEM X
(300000K2.01)
INSTRUMENT AIR SYSTEM: Knowledge of electrical power supplies to the following (CFR: 41.7):
Instrument air compressor 2.8 52 (19) 63 (400000) (SF8 CCS)
COMPONENT COOLING WATER SYSTEM X
(400000K2.01) CCWS:
Knowledge of electrical power supplies to the following (CFR: 41.7): CCW pumps 2.9 53 (50) 64 (203000) (SF2, SF4 RHR/LPCI) RHR/LPCI:
INJECTION MODE X
(203000) (SF2, SF4 RHR/LPCI) RHR/LPCI:
INJECTION MODE (G2.2.36) EMERGENCY PROCEDURES / PLAN:
Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations (CFR: 41.10 /
43.2 / 45.13).
4.2 86 (95) 65 (205000) (SF4 SCS)
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)
X (205000) (SF4 SCS)
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) (G2.1.23)
CONDUCT OF OPERATIONS: 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 87 (91) 66 (207000) (SF4 IC)
ISOLATION (EMERGENCY)
CONDENSER X
(207000) (SF4 IC) Isolation Condenser (G2.4.8)
Emergency Procedures /
Plan: Knowledge of how abnormal operating procedures are used in conjunction with EOPs (CFR: 41.10 / 43.5 / 45.13).
4.5 88 (86) 67 (239002) (SF3 SRV)
(239002A2.06) 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 (CFR: 41.5 /
45.6): Reactor high pressure 4.3 89 (99)
11 Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
68 (400000) (SF8 CCS)
COMPONENT COOLING WATER SYSTEM X
(400000A2.03) Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR:
41.5 / 45.6): High/low CCW temperature 3
90 (96)
(209002) (SF2, SF4 HPCS) HIGH PRESSURE CORE SPRAY SYSTEM (217000) (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM (510000) (SF4 SWS)
SERVICE WATER SYSTEM K/A Category Totals:
3 3
3 2
2 2
3 2(2) 2 2
2(3)
Group Point Total:
31
12 ES-401 BWR Examination Outline (Dresden)
Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 2/Group 2 (RO/SRO)
Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
69 (201002) (SF1 RMCS)
REACTOR MANUAL CONTROL SYSTEM X
(201002A3.04) Ability to monitor automatic operations of the REACTOR MANUAL CONTROL SYSTEM including (CFR:
41.7 / 45.7):Rod movement sequence timer malfunction alarm: Plant-Specific 2.8 54 (58) 70 (201003) (SF1 CRDM)
CONTROL ROD AND DRIVE MECHANISM X
(201003A4.02) CONTROL ROD AND DRIVE MECHANISM: Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8):
CRD mechanism position:
Plant-Specific 3.5 55 (8) 71 (204000) (SF2 RWCU)
REACTOR WATER CLEANUP SYSTEM X
(204000K3.02) Knowledge of the effect that a loss or malfunction of the REACTOR WATER CLEANUP SYSTEM will have on following (CFR:
41.7 / 45.4): Reactor water level 3.1 56 (56) 72 (215001) (SF7 TIP)
TRAVERSING IN CORE PROBE X
(215001A4.03)
TRAVERSING IN-CORE PROBE: Ability to manually operate and/or monitor in the control room (CFR: 41.7
/ 45.5 to 45.8): Isolation valves: Mark-I&II 3.0 57 (41) 73 (215002) (SF7 RBMS)
ROD BLOCK MONITOR SYSTEM X
(215002A1.01) Ability to predict and/or monitor changes in parameters associated with operating the ROD BLOCK MONITOR SYSTEM controls including (CFR: 41.5 / 45.5): Trip reference:BWR-3,4,5 2.7 58 (67) 74 (216000) (SF7 NBI)
NUCLEAR BOILER INSTRUMENTATION X
(216000K4.01) Knowledge of NUCLEAR BOILER INSTRUMENTATION design feature(s) and/or interlocks which provide for the following (CFR: 41.7):
Reading of nuclear boiler parameters outside the control room 3.6 59 (40) 75 (219000) (SF5 RHR SPC) RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE X
RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE (G2.1.20) CONDUCT OF OPERATIONS: Ability to interpret and execute procedure steps (CFR:
41.10 / 43.5 / 45.12).
4.6 60 (18)
13 Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
76 (234000) (SF8 FH)
FUEL HANDLING X
(234000A2.01) Ability to (a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT; 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): Interlock failure 3.3 61 (57) 77 (271000) (SF9 OG)
OFFGAS SYSTEM X
(271000K6.10) Knowledge of the effect that a loss or malfunction of the following will have on the OFFGAS SYSTEM (CFR: 41.7 / 45.7):
Condensate system flow 2.7 62 (60) 78 (286000) (SF8 FPS)
FIRE PROTECTION SYSTEM X
(286000A3.04) Ability to monitor automatic operations of the FIRE PROTECTION SYSTEM including (CFR: 41.7 / 45.7):
System initiation 3.2 63 (9) 79 (288000) (SF9 PVS)
PLANT VENTILATION SYSTEMS X
(288000K1.01) Knowledge of the physical connections and/or cause-effect relationships between PLANT VENTILATION SYSTEMS and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): A.C. electrical 2.6 64 (63) 80 (290003) (SF9 CRV)
CONTROL ROOM VENTILATION X
(290003K5.01) Knowledge of the operational implications of the following concepts as they apply to CONTROL ROOM HVAC (CFR: 41.5 / 45.3): Airborne contamination (e.g.,
radiological, toxic gas, smoke) control 3.2 65 (7) 81 (201006) (SF7 RWMS)
ROD WORTH MINIMIZER SYSTEM X
(201006A2.05) Ability to (a) predict the impacts of the following on the ROD WORTH MINIMIZER SYSTEM (RWH) (PLANT SPECIFIC); 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): Out of sequence rod movement; Plant-Spec(Not-BWR6) 3.5 91 (100)
14 Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
82 (214000) (SF7 RPIS)
ROD POSITION INFORMATION SYSTEM X
(214000A2.03) Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION 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): Overtravel/in-out 3.9 92 (92) 83 (230000) (SF5 RHR SPS) RHR/LPCI:
TORUS/SUPPRESSIO N POOL SPRAY MODE X
RHR/LPCI:
TORUS/SUPPRESSION POOL SPRAY MODE (G2.2.44) EQUIPMENT CONTROL: (multi-unit license) 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 / 45.1).
4.4 93 (94)
(201001) (SF1 CRDH)
CRD HYDRAULIC SYSTEM (201002) (SF1 RMCS)
REACTOR MANUAL CONTROL SYSTEM (202001) (SF1, SF4 RS) RECIRCULATION SYSTEM (202002) (SF1 RSCTL)
RECIRCULATION FLOW CONTROL SYSTEM (204000) (SF2 RWCU)
REACTOR WATER CLEANUP SYSTEM (223001) (SF5 PCS)
PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES (226001) (SF5 RHR CSS) RHR/LPCI:
CONTAINMENT SPRAY MODE SYSTEM MODE (233000) (SF9 FPCCU)
FUEL POOL COOLING/CLEANUP (239001) (SF3, SF4 MRSS) MAIN AND REHEAT STEAM SYSTEM
15 Item #
System / Safety Function / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
(239003) (SF9 MSVLCS) MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (241000) (SF3 RTPRS)
REACTOR/TURBINE PRESSURE REGULATING SYSTEM (245000) (SF4 MTGEN)
MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS (256000) (SF2 CDS)
CONDENSATE SYSTEM (259001) (SF2 FWS)
FEEDWATER SYSTEM (268000) (SF9 RW)
RADWASTE SYSTEM (272000) (SF7, SF9 RMS) RADIATION MONITORING SYSTEM (290001) (SF5 SC)
SECONDARY CONTAINMENT (290002) (SF4 RVI)
REACTOR VESSEL INTERNALS K/A Category Totals:
1 0
1 1
1 1
1 1(2) 2 2
1(1)
Group Point Total:
15
16 ES-401 BWR Examination Outline (Dresden)
Form ES-401-3 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)
Facility:
Dresden Date of Exam:
11/01/2021 Category K/A #
Topic RO SRO-Only Item #
IR Q#
IR Q#
- 1. Conduct of Operations G2.1.3 (G2.1.3) CONDUCT OF OPERATIONS: Knowledge of shift or short-term relief turnover practices (CFR: 41.10 / 45.13).
84 3.7 66 (12)
G2.1.19 (G2.1.19) CONDUCT OF OPERATIONS: Ability to use plant computers to evaluate system or component status (CFR: 41.10 / 45.12).
85 3.9 67 (15)
G2.1.26 (G2.1.26) CONDUCT OF OPERATIONS: Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen) (CFR: 41.10 / 45.12).
86 3.4 68 (6)
G2.1.4 (G2.1.4) CONDUCT OF OPERATIONS: Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10 / 43.2).
87 3.8 94 (82)
G2.1.35 (G2.1.35) CONDUCT OF OPERATIONS: Knowledge of the fuel-handling responsibilities of SROs (CFR: 41.10 / 43.7).
88 3.9 95 (93)
Subtotal 3
2
- 2. Equipment Control G2.2.14 (G2.2.14) EQUIPMENT CONTROL: Knowledge of the process for controlling equipment configuration or status (CFR: 41.10 / 43.3 / 45.13).
89 3.9 69 (1)
G2.2.38 (G2.2.38) EQUIPMENT CONTROL: Knowledge of conditions and limitations in the facility license (CFR: 41.7 / 41.10 / 43.1 / 45.13).
90 3.6 70 (2)
G2.2.5 (G2.2.2) EQUIPMENT CONTROL: Knowledge of the process for making design or operating changes to the facility (CFR: 41.10 / 43.3 /
45.13).
91 3.2 96 (79)
G2.2.23 (G2.2.23) EQUIPMENT CONTROL: Ability to track Technical Specification limiting conditions for operations (CFR: 41.10 / 43.2 /
45.13).
92 4.6 97 (89)
Subtotal 2
2
- 3. Radiation Control G2.3.4 (G2.3.4) RADIATION CONTROL: Knowledge of radiation exposure limits under normal or emergency conditions (CFR: 41.12 / 43.4 / 45.10).
93 3.2 71 (11)
G2.3.7 (G2.3.7) RADIATION CONTROL: Ability to comply with radiation work permit requirements during normal or abnormal conditions (CFR: 41.12 /
45.10).
94 3.5 72 (26)
G2.3.6 (G2.3.6) RADIATION CONTROL: Ability to approve release permits (CFR: 41.13 / 43.4 / 45.10).
95 3.8 98 (76)
Subtotal 2
1
- 4. Emergency Procedures/Plan G2.4.16 (G2.4.16) EMERGENCY PROCEDURES / PLAN: Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines (CFR: 41.10 /
43.5 / 45.13).
96 3.5 73 (20)
G2.4.34 (G2.4.34) EMERGENCY PROCEDURES / PLAN: Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects (CFR: 41.10 / 43.5 / 45.13).
97 4.2 74 (61)
17 G2.4.49 (G2.4.49) EMERGENCY PROCEDURES / PLAN: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls (CFR: 41.10 / 43.2 / 45.6).
98 4.6 75 (35)
G2.4.9 (G2.4.9) EMERGENCY PROCEDURES / PLAN: Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies (CFR:
41.10 / 43.5 / 45.13).
99 4.2 99 (77)
G2.4.22 (G2.4.19) EMERGENCY PROCEDURES / PLAN: Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations. (CFR: 41.7 / 41.10 / 43.5 / 45.12).
100 4.4 100 (78)
Subtotal 3
2