ML23055B052
| ML23055B052 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/01/2022 |
| From: | NRC/RGN-I/DORS/OB |
| To: | Public Service Enterprise Group |
| References | |
| Download: ML23055B052 (1) | |
Text
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 Facility:
Hope Creek K/A Catalog Rev. 2 Rev.
0 Date of Exam:
8/7/2022 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
5 4
4 2
20 4
3 7
2 1
1 1
1 1
1 6
1 2
3 Tier Totals 3
4 6
5 5
3 26 5
5 10
- 2.
Plant Systems 1
3 1
2 2
2 3
2 2
3 4
2 26 2
3 5
2 2
1 1
1 0
1 0
2 1
1 1
11 0
1 2
3 Tier Totals 5
2 3
3 2
4 2
4 4
5 3
37 3
5 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 6
1 2
3 4
7 2
2 1
1 2
2 1
2
- 4. Theory Reactor Theory 3
Thermodynamics 3
6 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 a1re 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.
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4
- 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.
ES-401 BWR Examination Outline (Hope Creek)
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
(295001) (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION / 1 & 4 (G2.4.45) EMERGENCY PROCEDURES / PLAN: Ability to prioritize and interpret the significance of each annunciator or alarm (CFR: 41.10 / 43.5 / 45.3
/ 45.12).
4.1 57 2
(295003) (APE 3)
PARTIAL OR COMPLETE LOSS OF AC POWER / 6 X
(295003AA2.02) Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.
POWER (CFR: 41.10 / 43.5 / 45.13): Reactor power / pressure /
and level 4.2 52 3
(295004) (APE 4)
PARTIAL OR COMPLETE LOSS OF DC POWER / 6 X
(295004AK3.02) Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER (CFR: 41.5 / 45.6): Ground isolation/fault determination 2.9 41 4
(295005) (APE 5) MAIN TURBINE GENERATOR TRIP / 3 X
(295005AA1.07) Ability to operate and/or monitor the following as they apply to MAIN TURBINE GENERATOR TRIP (CFR: 41.7 /
45.6): A.C. electrical distribution 3.3 63 5
(295006) (APE 6)
SCRAM / 1 X
(295006AA1.05) Ability to operate and/or monitor the following as they apply to SCRAM (CFR: 41.7 / 45.6): Neutron monitoring system 4.2 43
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 6
(295016) (APE 16)
CONTROL ROOM ABANDONMENT / 7 X
(295016AA2.05) Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT (CFR: 41.10
/ 43.5 / 45.13): Drywell pressure 3.8 68 7
(295018) (APE 18)
PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW) / 8 X
(295018AA1.03) Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CFR: 41.7 / 45.6): Affected systems so as to isolate damaged portions 3.3 10 8
(295019) (APE 19)
PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR / 8 X
(295019AA2.02) 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): Status of safety-related instrument air system loads (see AK2.1 - AK2.19) 3.6 24 9
(295021) (APE 21)
LOSS OF SHUTDOWN COOLING / 4 X
(295021AA1.02) Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING (CFR: 41.7 /
45.6): RHR/shutdown cooling 3.5 67 10 (295023) (APE 23)
REFUELING ACCIDENTS / 8 X
(295023AK2.04) Knowledge of the interrelations between REFUELING ACCIDENTS and the following (CFR: 41.7 / 45.8):
RMCS/Rod control and information system 3.2 6
11 (295024) (EPE 1) HIGH DRYWELL PRESSURE
/ 5 X
(295024EK3.05) Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE (CFR:
41.5 / 45.6): RPV flooding 3.5 60 12 (295025) (EPE 2) HIGH REACTOR PRESSURE
/ 3 X
(295025EK3.01) Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE (CFR:
41.5 / 45.6): Safety/relief valve opening.
4.2 64 13 (295026) (EPE 3)
SUPPRESSION POOL HIGH WATER TEMPERATURE / 5 X
(295026EK2.04) Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following (CFR: 41.7 / 45.8): SPDS/ERIS/CRIDS/GDS: Plant-Specific 2.5 72 14 (295028) (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY) / 5 X
(295028EK1.01) Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE (CFR: 41.8 to 41.10): Reactor water level measurement 3.5 4
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 1
16 (295031) (EPE 8)
REACTOR LOW WATER LEVEL / 2 X
(295031EK2.04) Knowledge of the interrelations between REACTOR LOW WATER LEVEL and the following (CFR: 41.7 /
45.8): Reactor core isolation cooling: Plant-Specific 4
22 17 (295037) (EPE 14)
SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN / 1 X
(295037EK3.03) 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): Lowering reactor water level 4.1 51 18 (295038) (EPE 15)
HIGH OFFSITE RADIOACTIVITY RELEASE RATE / 9 X
(295038 EK3.02) Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE (CFR: 41.5 / 45.6): System isolations 3.9 56 19 (600000) (APE 24)
PLANT FIRE ON SITE /
8 X
(600000 AA2.17) Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Systems that may be affected by the fire 3.1 47
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 20 (700000) (APE 25)
GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES / 6 X
(700000) (APE 25) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES / 6 (G2.2.44) EQUIPMENT CONTROL:
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 48 21 (295005) (APE 5) MAIN TURBINE GENERATOR TRIP / 3 X
(295005AA2.03) Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP (CFR: 41.10 / 43.5 / 45.13): Turbine valve position 3.1 100 22 (295016) (APE 16)
CONTROL ROOM ABANDONMENT / 7 X
(295016AA2.01) Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT (CFR: 41.10 / 43.5 / 45.13): Reactor power 4.1 97 23 (295018) (APE 18)
PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW) / 8 X
(295018) (APE 18) PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW) / 8 (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 76 24 (295026) (EPE 3)
SUPPRESSION POOL HIGH WATER TEMPERATURE / 5 X
(295026) (EPE 3) SUPPRESSION POOL HIGH WATER TEMPERATURE / 5 (G2.4.41) EMERGENCY PROCEDURES /
PLAN: Knowledge of the emergency action level thresholds and classifications (CFR: 41.10 / 43.5 / 45.11).
4.6 86 25 (295037) (EPE 14)
SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN / 1 X
(295037EA2.07) Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN (CFR: 41.10 / 43.5 / 45.13): Containment conditions/isolations 4.2 90 26 (295038) (EPE 15)
HIGH OFFSITE RADIOACTIVITY RELEASE RATE / 9 X
(295038EA2.04) Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE (CFR: 41.10 / 43.5 / 45.13): Source of off-site release 4.5 84 27 (700000) (APE 25)
GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES / 6 X
(700000) (APE 25) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES / 6 (G2.4.18) EMERGENCY PROCEDURES / PLAN: Knowledge of the specific bases for EOPs (CFR: 41.10 / 43.1 / 45.13).
4 91 K/A Category Totals:
2 3
5 4
8 5
Group Point Total:
27
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 ES-401 BWR Examination Outline (Hope Creek)
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#
29 (295010) (APE 10)
HIGH DRYWELL PRESSURE / 5 X
(295010AA2.01) Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE (CFR: 41.10 / 43.5
/ 45.13): Leak rates 3.4 9
30 (295015) (APE 15)
INCOMPLETE SCRAM /
1 -- DELETED X
(295015AA1.07) Ability to operate and/or monitor the following as they apply to INCOMPLETE SCRAM (CFR: 41.7 / 45.6): Neutron monitoring system 3.6 36 31 (295017) (APE 17)
ABNORMAL OFFSITE RELEASE RATE / 9 X
(295017AK3.01) Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE (CFR: 41.5 / 45.6): System isolations 3.6 50 32 (295020) (APE 20)
INADVERTENT CONTAINMENT ISOLATION / 5 & 7 X
(295020AK1.04) Knowledge of the operational implications of the following concepts as they apply to INADVERTENT CONTAINMENT ISOLATION (CFR: 41.8 to 41.10): Bottom head thermal stratification 2.5 45 33 (295029) (EPE 6) HIGH SUPPRESSION POOL WATER LEVEL / 5 X
(295029) (EPE 6) HIGH SUPPRESSION POOL WATER LEVEL /
5 (G2.2.44) EQUIPMENT CONTROL: 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) #26 on 2019 4.2 20 34 (295033) (EPE 10)
HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS / 9 X
(295033EK2.02) Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS and the following (CFR: 41.7 / 45.8): Process radiation monitoring system 3.8 74 35 (295002) (APE 2) LOSS OF MAIN CONDENSER VACUUM / 3 X
(295002) (APE 2) LOSS OF MAIN CONDENSER VACUUM / 3 (G2.4.11) EMERGENCY PROCEDURES/PLAN: Knowledge of abnormal condition procedures. (CFR: 41.10 / 43.5 / 45.13) 4.2 88 36 (295032) (EPE 9) HIGH SECONDARY CONTAINMENT AREA TEMPERATURE / 5 X
(295032EA2.02) Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE (CFR: 41.10 / 43.5 / 45.13): Equipment operability 3.5 92 37 (295034) (EPE 11)
SECONDARY CONTAINMENT VENTILATION HIGH RADIATION / 9 X
(295034) (EPE 11) SECONDARY CONTAINMENT VENTILATION HIGH RADIATION / 9 (G2.1.30) CONDUCT OF OPERATIONS: Ability to locate and operate components, including local controls (CFR: 41.7 / 45.7).
4 98 K/A Category Totals:
1 1
1 1
2 3
Group Point Total:
9
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 ES-401 BWR Examination Outline (Hope Creek)
Form ES-401-1 Plant Systems Tier 2/Group 1 (RO/SRO)
Item #
System / 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
(203000A2.01) Ability to (a) predict the impacts of the following on the RHR/LPCI:INJECTION MODE (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): Initiating logic failure 3.8 8
39 (203000) (SF2, SF4 RHR/LPCI) RHR/LPCI:
INJECTION MODE X
(203000A3.02) Ability to monitor automatic operations of the RHR/LPCI:INJECTION MODE (PLANT SPECIFIC) including (CFR: 41.7 / 45.7): Pump start 4
7 40 (291002K1.09)
SENSORS/DETECTORS X
X (291002K1.09) Sensors/Detectors (CFR: 41.7): Modes of failure.
3.3 13 41 (206000) (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM X
(206000A2.04) Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION 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): A.C.
failures:BWR-2,3,4 2.7 69 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 17
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 43 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X
(209001K6.01) Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSTEM (CFR: 41.7 / 45.7): A.C.
power 3.4 75 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 2
45 (212000) (SF7 RPS)
(212000K4.12) Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following (CFR: 41.7): Bypassing of selected SCRAM signals (manually and automatically): Plant-Specific 3.9 54 46 (215003) (SF7 IRM)
INTERMEDIATE RANGE MONITOR SYSTEM X
(215003A3.03) Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including (CFR: 41.7 / 45.7): RPS status 3.7 16 47 (215004) (SF7 SRMS)
SOURCE RANGE MONITOR SYSTEM X
(215004A3.02) Ability to monitor automatic operations of the SOURCE RANGE MONITOR (SRM) SYSTEM including (CFR:
41.7 / 45.7): Annunciator and alarm signals 3.4 18 48 (215005) (SF7 PRMS)
AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X
(215005A1.07) Ability to predict and/or monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including (CFR:
41.5 / 45.5): APRM (gain adjustment factor) 3 21 49 (217000) (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM X
(217000K4.07) Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) design feature(s) and/or interlocks which provide for the following (CFR:
41.7): Alternate supplies of water 3.6 33 50 (217000) (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM X
(217000K6.03) Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) (CFR:
41.7 / 45.7): Suppression pool water supply 3.5 65
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 51 (218000) (SF3 ADS)
AUTOMATIC DEPRESSURIZATION SYSTEM X
(218000A4.04) AUTOMATIC DEPRESSURIZATION SYSTEM:
Ability to manually operate and/or monitor in the control room (CFR:
41.7 / 45.5 to 45.8): ADS inhibit:
Plant-Specific 4.1 71 52 (218000) (SF3 ADS)
AUTOMATIC DEPRESSURIZATION SYSTEM X
(218000K2.01) AUTOMATIC DEPRESSURIZATION SYSTEM:
Knowledge of electrical power supplies to the following (CFR:
41.7): ADS logic 3.1 12 53 (223002) (SF5 PCIS)
PRIMARY CONTAINMENT ISOLATION SYSTEM /
NUCLEAR STEAM SUPPLY SHUTOFF X
(223002A1.04) Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including (CFR: 41.5 / 45.5):
System indicating lights and alarms 3.5 37 54 (239002) (SF3 SRV)
(239002A4.01) RELIEF/SAFETY VALVES: Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8): SRV's 4.4 61 55 (259002) (SF2 RWLCS)
REACTOR WATER LEVEL CONTROL SYSTEM X
(259002A4.02) 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 in the automatic mode 3.7 66 56 (261000) (SF9 SGTS)
STANDBY GAS TREATMENT SYSTEM X
(261000A4.01) STANDBY GAS TREATMENT SYSTEM: Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8): Off-site release levels:
Plant-Specific 3.2 59 57 (262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION X
(262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION (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).
4.3 31 58 (262001) (SF6 AC) AC ELECTRICAL DISTRIBUTION X
(262001K1.04) Knowledge of the physical connections and/or cause-effect relationships between A.C.
ELECTRICAL DISTRIBUTION and the following (CFR: 41.2 to 41.9 /
45.7 to 45.8): Uninterruptible power supply 3.1 29
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 59 (262002) (SF6 UPS)
UNINTERRUPTABLE POWER SUPPLY (AC/DC)
X (262002K1.08) Knowledge of the physical connections and/or cause-effect relationships between UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): Containment isolation system: Plant-Specific 2.9 46 60 (263000) (SF6 DC) DC ELECTRICAL DISTRIBUTION X
(263000K5.01) Knowledge of the operational implications of the following concepts as they apply to D.C. ELECTRICAL DISTRIBUTION (CFR: 41.5 / 45.3):
Hydrogen generation during battery charging.
2.6 53 61 (264000) (SF6 EGE)
EMERGENCY GENERATORS (DIESEL/JET)
X (264000K1.02) Knowledge of the physical connections and/or cause-effect relationships between EMERGENCY GENERATORS (DIESEL/JET) and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8):
D.C. electrical distribution 3.3 58 62 (300000) (SF8 IA)
INSTRUMENT AIR SYSTEM X
(300000K5.01) Knowledge of the operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM (CFR: 41.5 / 45.3): Air compressors 2.5 73 63 (400000) (SF8 CCS)
COMPONENT COOLING WATER SYSTEM X
(400000K6.05) Knowledge of the effect that a loss or malfunction of the following will have on the CCWS (CFR: 41.7 / 45.7): Motors 2.8 39 64 (215003) (SF7 IRM)
INTERMEDIATE RANGE MONITOR SYSTEM X
(215003A2.04) 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): Up scale or down scale trips 3.8 94
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 65 (215005) (SF7 PRMS)
AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X
(215005) (SF7 PRMS) AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR (G2.4.1)
EMERGENCY PROCEDURES /
PLAN: Knowledge of EOP entry conditions and immediate action steps (CFR: 41.10 / 43.5 / 45.13) 4.8 89 66 (239002) (SF3 SRV)
(239002) (SF3 SRV) SAFETY RELIEF VALVES (G2.4.20)
EMERGENCY PROCEDURES /
PLAN: Knowledge of the operational implications of EOP warnings, cautions, and notes (CFR: 41.10 / 43.5 / 45.13).
4.3 83 67 (262002) (SF6 UPS)
UNINTERRUPTABLE POWER SUPPLY (AC/DC)
X (262002) (SF6 UPS)
UNINTERRUPTABLE POWER SUPPLY (AC/DC) (G2.1.31)
CONDUCT OF OPERATIONS:
Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup (CFR: 41.10
/ 45.12).
4.3 99 68 (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 2.8 79 K/A Category Totals:
3 1
2 2
2 3
2 4
3 4
5 Group Point Total:
31
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 ES-401 BWR Examination Outline (Hope Creek)
Form ES-401-1 Plant Systems Tier 2/Group 2 (RO/SRO)
Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
69 (201001) (SF1 CRDH)
CRD HYDRAULIC SYSTEM X
(201001A2.01) Ability to (a) predict the impacts of the following on the CONTROL ROD DRIVE HYDRAULIC 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): Pumps trips 3.2 28 70 (201002) (SF1 RMCS)
REACTOR MANUAL CONTROL SYSTEM X
(201002A4.05) REACTOR MANUAL CONTROL SYSTEM:
Ability to manually operate and/or monitor in the control room (CFR:
41.7 / 45.5 to 45.8): Rod select matrix 3.1 15 71 (201003) (SF1 CRDM)
CONTROL ROD AND DRIVE MECHANISM X
(201003K1.04) Knowledge of the physical connections and/or cause-effect relationships between CONTROL ROD AND DRIVE MECHANISM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8):
Reactor vessel 2.9 14 72 (201006) (SF7 RWMS)
ROD WORTH MINIMIZER SYSTEM X
(201006K4.07) Knowledge of ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) design feature(s) and/or interlocks which provide for the following (CFR:
41.7): Display of out of position control rods without rod blocks (transition zone):P-Spec(Not-BWR6) 3.1 3
73 (215001) (SF7 TIP)
TRAVERSING IN CORE PROBE X
(215001K1.05) Knowledge of the physical connections and/or cause-effect relationships between TRAVERSING IN-CORE PROBE and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): Primary containment isolation system:(Not-BWR1) 3.3 35
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 74 (215002) (SF7 RBMS)
ROD BLOCK MONITOR SYSTEM X
(215002K6.04) Knowledge of the effect that a loss or malfunction of the following will have on the ROD BLOCK MONITOR SYSTEM (CFR:
41.7 / 45.7) : APRM reference channel: BWR-3,4,5 2.8 34 75 (219000) (SF5 RHR SPC) RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE X
(219000A2.11) Ability to (a) predict the impacts of the following on the RHR/LPCI:TORUS/SUPPRESSION POOL COOLING MODE; 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): Motor operated valve failures 3.1 19 76 (230000) (SF5 RHR SPS) RHR/LPCI:
TORUS/SUPPRESSION POOL SPRAY MODE X
(230000K2.02)
RHR/LPCI:TORUS/SUPPRESSION POOL SPRAY MODE: Knowledge of electrical power supplies to the following (CFR: 41.7): Pumps 2.8*
2.8 42 78 (234000) (SF8 FH)
FUEL HANDLING X
(234000K3.03) Knowledge of the effect that a loss or malfunction of the FUEL HANDLING EQUIPMENT will have on following (CFR: 41.7 /
45.4): Fuel handling operations 3.1 62 79 (291004K1.12) PUMPS X
(291004K1.12) Pumps (CFR 41.3):
"Runout" of a centrifugal pump (definition, indications, causes, effects, and corrective measures) 2.8 32 80 (290003) (SF9 CRV)
CONTROL ROOM VENTILATION X
(290003A3.01) Ability to monitor automatic operations of the CONTROL ROOM HVAC including (CFR: 41.7 / 45.7):
Initiation/reconfiguration
- 64 on 2019 3.3 70 81 (204000) (SF2 RWCU)
REACTOR WATER CLEANUP SYSTEM X
(204000A2.13) Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP 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): Signal received which results in a system isolation.
3.4 80
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 82 (245000) (SF4 MTGEN)
MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS X
(245000) (SF4 MTGEN) MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS (G2.1.7)
CONDUCT OF OPERATIONS:
Ability 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).
4.7 95 83 (272000) (SF7, SF9 RMS) RADIATION MONITORING SYSTEM X
(272000) (SF7, SF9 RMS)
RADIATION MONITORING SYSTEM (G2.4.31) EMERGENCY PROCEDURES / PLAN:
Knowledge of annunciator alarms, indications, or response procedures (CFR: 41.10 / 45.3).
4.1 77 K/A Category Totals:
2 1
1 1
0 1
0 3
1 1
3 Group Point Total:
14
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 ES-401 BWR Examination Outline (Hope Creek)
Form ES-401-3 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)
Facility:
Hope Creek Date of Exam:
8/7/2022 Category K/A #
Topic RO SRO-Only Item #
IR Q#
IR Q#
- 1. Conduct of Operations G2.1.7 (G2.1.7) CONDUCT OF OPERATIONS: Ability 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).
84 4.4 23 G2.1.31 (G2.1.31) CONDUCT OF OPERATIONS: Ability to locate control room switches, controls, and indications and to determine that they correctly reflect the desired plant lineup (CFR: 41.10 / 45.12).
85 4.6 30 G2.1.32 (G2.1.32) CONDUCT OF OPERATIONS: Ability to explain and apply system limits and precautions (CFR: 41.10 / 43.2 / 45.12) #79 on 2018 87 4.0 93 G2.1.35 (G2.1.35) CONDUCT OF OPERATIONS: Knowledge of the fuel-handling responsibilities of SROs (CFR: 41.10 / 43.7). 33974 88 3.9 82 Subtotal 2
2
- 2. Equipment Control G2.2.17 (G2.2.13) EQUIPMENT CONTROL: Knowledge of tagging and clearance procedures. (CFR: 41.10 / 45.13) 89 4.1 5
G2.2.22 (G2.2.22) EQUIPMENT CONTROL: Knowledge of limiting conditions for operations and safety limits (CFR: 41.5 / 43.2 / 45.2).
90 4.0 38 G2.2.21 (G2.2.21) EQUIPMENT CONTROL: Knowledge of pre-and post-maintenance operability requirements (CFR: 41.10 / 43.2).
91 4.1 87 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).
92 4.5 85 Subtotal 2
2
- 3. Radiation Control G2.3.13 (G2.3.13) RADIATION CONTROL: Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc (CFR: 41.12 / 43.4 / 45.9 /
45.10).
94 3.4 25 G2.3.11 (G2.3.11) RADIATION CONTROL: Ability to control radiation releases (CFR: 41.11 / 43.4 / 45.10).
95 4.3 96 Subtotal 1
1
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4
- 4. Emergency Procedures/Plan G2.4.17 (2.4.17) Knowledge of EOP terms and definitions. (CFR: 41.10 /
45.13) 96 3.9 11 G2.4.22 (G2.4.22) EMERGENCY PROCEDURES / PLAN: Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations (CFR:
41.7 / 41.10 / 43.5 / 45.12).
99 4.4 81 G2.4.30 (G2.4.30) EMERGENCY PROCEDURES / PLAN: 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). #76 on 2018 100 4.1 78 Subtotal 1
2
ES-401 Written Examination Outline, Generic Knowledge and Abilities, Rejected K/As Form ES-401-1,3,4 ES-401 BWR Examination Outline (Hope Creek)
Form ES-401-3 Theory (Tier 4) (RO)
Facility:
Hope Creek Date of Exam:
8/7/2022 Category K/A #
Topic RO Item #
IR Q#
Reactor Theory Thermodynamics (292008K1.22)
REACTOR OPERATIONAL PHYSICS (292008K1.22) Reactor Operational Physics (CFR 41.5):
Explain the effect that opening steam bypass valves, during power operation, will have on reactor power.
28 3.5 49 (292006K1.14) FISSION PRODUCT POISONS (292006K1.14) Fission Product Poisons (CFR 41.1):
Explain the process and reasons for the Reactor Operator to compensate for the time dependent behavior of Xenon-135 concentration in the reactor.
77 3.1 44 (292002K1.07)
NEUTRON LIFE CYCLE (292002K1.07) Neutron Life Cycle (CFR 41.1): Define critical, subcritical, and supercritical with respect to a reactor.
86 3.5 55 (293009K1.19) CORE THERMAL LIMITS (293009K1.19) Core Thermal Limits (CFR 41.14): Explain the basis of the limiting condition for CPR.
93 2.8 40 (293008K1.37)
THERMAL HYDRAULICS(CFR41.14 (293008K1.37) Thermal Hydraulics (CFR 41.14):
Describe means by which the operator can enhance natural circulation.
97 3.2 27 (293006K1.05) FLUID STATICS (CFR: 41.14)
(293006K1.05) Fluid Statics (CFR 41.14): Explain operational implications of fluid hammer 98 3.2 26 Subtotal 6