ML15275A363
| ML15275A363 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/11/2015 |
| From: | Todd Fish Operations Branch I |
| To: | Talen Energy |
| Shared Package | |
| ML15063A453 | List: |
| References | |
| TAC U01916 | |
| Download: ML15275A363 (28) | |
Text
ES-401 Written Examination Outline Form ES-401-1 LOC27 NRC Written Facility: Date of Exam: 8/17115 Exam Outline RO Kl A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total l 2 3 4 5 6 1 2 3 4 *
- 1. 1 3 4 3 3 3 4 20 3 4 7 Emergency
& 2 1 l 1 l l 2 7 2 1 3 Plant Tier Evolutions 4 5 4 4 4 6 27 5 5 10 Totals 1 3 2 2 3 2 2 2 2 3 3 2 26 3 2 5 2.
Plant 2 1 I 2 1 1 1 I 1 1 1 1 12 0 1 2 3 Systems Tier 4 3 4 4 3 3 3 3 4 4 3 38 4 4 8 Totals l 2 3 4 l 2 3 4
- 3. Generic Knowledge & Abilities IO 7 Categories 2 2 3 3 2 2 I 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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 section D.1.b of ES-401, for guidance regarding elimination of inappropriate KlA 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 KAs having an importance rating (IR) of2.5 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 Kl A categories.
7.* The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D. l .b of ES-40 l for the applicable KIA's
- 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
- 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, !Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10CFR55.43
ES-401 2 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#
AA2.05 - Ability to detennine and/or interpret the following as they apply to 295006 SCRAM I I x SCRAM: Whether a reactor SCRAM has 4.6 76 occurred AA2.04 - Ability to detem1ine and/or 295005 Main Turbine Generator interpret the following as they apply to Trip/ 3 x MAIN TURBINE GENERATOR TRIP:
3.8 77 Reactor pressure EA2.03 - Ability to determine and/or 295028 High Drywell Temperature interpret the following as they apply to 15 x HIGH DRYWELL TEMPERATURE:
3.9 78 Reactor water level 2.4. I 1 - Emergency Procedures I Plan:
295038 High Off-site Release Rate 19 x Knowledge of abnormal condition 4.2 79 procedures.
2.2.25 - Equipment Control: Knowledge 700000 Generator Voltage and of the bases in Technical Specifications for Electric Grid Disturbances x limiting conditions for operations and 4.2 80 safety limits.
2.4.9 - Knowledge of low power/shutdown 295001 Partial or Complete Loss of implications in accident (e.g., loss of Forced Core Flow Circulation I 1 & x coolant accident or loss of residual heat 4.2 81 4
removal) mitigation strategies.
2.2.44 - Equipment Control: Ability to interpret control room indications to verify 295004 Partial or Complete Loss of the status and operation of a system, and DC Power I 6 x understand how operator actions and 4.4 82 directives affect plant and system conditions.
AKI.OJ - Knowledge of the operational implications of the following concepts as 295006 SCRAM I I x they apply to SCRAM: Decay heat 3.7 39 generation and removal AKl.01 - Knowledge of the operational 295021 Loss of Shutdown Cooling implications of the following concepts as 14 x they apply to LOSS OF SHUTDOWN 3.6 40 COOLING: Decay heat AKI.03 - Knowledge of the operational implications of the following concepts as 295004 Partial or Complete Loss of DC Power I 6 x they apply to PARTIAL OR COMPLETE 2.9 41 LOSS OF D.C. POWER: Electrical bus divisional separation EK2.03 - Knowledge of the interrelations between SCRAM CONDITION PRESENT 295037 SCRAM Conditions AND REACTOR POWER ABOVE Present and Reactor Power Above x APRM DOWNSCALE OR UNKNOWN 4.1 42 APRM Downscale or Unknown I I and the following: ARI/RPT/ATWS:
Plant-Specific EK2.02 - Knowledge of the interrelations 295030 Low Suppression Pool between LOW SUPPRESSION POOL Water Level I 5 x WATER LEVEL and the following: RCIC:
3.7 43 Plant-Specific AK2.06 - Knowledge of the interrelations 700000 Generator Voltage and between GENERATOR VOLTAGE AND Electric Grid Disturbances x ELECTRIC GRID DISTURBANCES and 3.9 44 the following: Reactor power.
AK3.0l - Knowledge of the reasons for the 295016 Control Room following responses as they apply to Abandonment I 7 x CONTROL ROOM ABANDONMENT:
4.1 45 Reactor SCRAM
ES-401 2 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#
AK3.04 - Knowledge of the reasons for the following responses as they apply to 600000 Plant Fire On-site I 8 x PLANT FIRE ON SITE: Actions contained 2.8 46 in the abnormal procedure for plant fire on site EK3. 02 - Knowledge of the reasons for the 295038 High Off-site Release Rate following responses as they apply to HIGH 19 x OFF-SITE RELEASE RATE: System 3.9 47 isolations EAi.OJ -Ability to operate and/or monitor the following as they apply to HIGH 295025 High Reactor Pressure I 3 x REACTOR PRESSURE: Main steam line 2.9 48 drains AAl.03 -Ability to operate and/or monitor the following as they apply to 295023 Refueling Accidents I 8 x REFUELING ACCIDENTS: Fuel handling 3.3 49 equipment AAl.01 - Ability to operate and/or monitor 295005 Main Turbine Generator the following as they apply to MAIN Trip I 3 x TURBINE GENERATOR TRIP:
3.1 50 Recirculation system: Plant-Specific EA2.02 - Ability to determine and/or 295031 Reactor Low Water Level I interpret the following as they apply to 2
x REACTOR LOW WATER LEVEL:
4.0 51 Reactor power AA2.03 - Ability to determine and/or interpret the following as they apply to 295018 Partial or Complete Loss of CCW/8 x PARTIAL OR COMPLETE LOSS OF 3.2 52 COMPONENT COOLING WATER:
Cause for partial or complete loss AA2.02 - Ability to determine and/or interpret the following as they apply to 295019 Partial or Complete Loss of PARTIAL OR COMPLETE LOSS OF Instrument Air I 8 x INSTRUMENT AIR: Status of safety-3.6 53 related instrument air system loads (see AK2. l - AK2.19) 2.4.1 - Emergency Procedures I Plan:
295003 Partial or Complete Loss of AC/6 x Knowledge ofEOP entry conditions and 4.6 54 immediate action steps.
295001 Partial or Complete Loss of 2.1.32 - Conduct of Operations: Ability to Forced Core Flow Circulation I I & x explain and apply all system limits and 3.8 55 4 precautions.
2.4.20 - Emergency Procedures I Plan:
295026 Suppression Pool High Water Temp. I 5 x Knowledge of operational implications of 3.8 56 EOP warnings, cautions, and notes.
EK2.04 - Knowledge of the interrelations 295028 High Drywell Temperature between HIGH DRYWELL 15 x TEMPERATURE and the following:
3.6 57 Drywell ventilation 2.1.23 - Ability to perform specific system 295024 High Drywell Pressure I 5 x and integrated plant procedures during all 4.3 58 modes of plant operation.
Kl A Category Totals: 3 4 3 3 3/3 4/4 Group Point Total:
I 20/7
ES-401 3 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#
EA2.01 - Ability to detem1ine and/or 295029 High Suppression Pool interpret the following as they apply to Water Level I 5 x HIGH SUPPRESSION POOL WATER 3.9 83 LEVEL: Suppression pool water level 2.4.35 - Emergency Procedures I Plan:
Knowledge of local auxiliary operator tasks 295007 High Reactor Pressure I 3 x during emergency and the resultant 4.0 84 operational effects.
AA2.05 - Ability to determine and/or 295014 Inadvertent Reactivity interpret the following as they apply to Addition I I x INADVERTENT REACTIVITY 4.6 85 ADDITION: Violation of safety limits AKl.02 - Knowledge of the operational 295017 High Off-site Release Rate implications of the following concepts as 19 x they apply to HIGH OFF-SITE RELEASE 3.8 59 RATE: Protection of the general public EK2.03 - Knowledge of the interrelations 295034 Secondary Containment between SECONDARY CONTAINMENT Ventilation High Radiation I 9 x VENTILATION HIGH RADIATION and 4.3 60 the following: SBGT/FRVS: Plant-Specific AK3.02 - Knowledge of the reasons for the following responses as they apply to LOW 295009 Low Reactor Water Level I 2
x REACTOR WATER LEVEL: Reactor 2.7 61 feedpump runout flow control: Plant-Specific AAI .01 -Ability to operate and/or monitor 295015 Incomplete SCRAM I I x the following as they apply to 3.8 62 INCOMPLETE SCRAM: CRD hydraulics EA2.02 - Ability to determine and/or 295029 High Suppression Pool interpret the following as they apply to Water Level I 5 x HIGH SUPPRESSION POOL WATER 3.5 63 LEVEL: Reactor pressure 2.4.21 - Emergency Procedures I Plan:
Knowledge of the parameters and logic used to assess the status of safety functions, such 295036 Secondary Containment High Sump/Area Water Level I 5 x as reactivity control, core cooling and heat 4.0 64 removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
2.2.22 - Equipment Control: Knowledge of 295010 High Drywell Pressure I 5 x limiting conditions for operations and safety 4.0 65 limits.
KIA Category Totals: 1 1 1 1 1/2 2/1 Group Point Total: 713 I
ES-401 4 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G Q#
1 2 3 4 5 6 1 3 4 A2.02 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based on 215004 Source Range Monitor x those predictions, use procedures to 3.7 86 correct, control, or mitigate the consequences of those abnormal conditions or operations: SRM inop condition A2.03 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those 400000 Component Cooling predictions, use procedures to Water x correct, control, or mitigate the 3.0 87 consequences of those abnormal operation: High/low CCW tern perature 2.2.42 - Equipment Control: Ability to recognize system parameters that 239002 SRVs x are entry-level conditions for 4.6 88 Technical Specifications.
2.2.12 - Equipment Control:
218000 ADS x Knowledge of surveillance 4.1 89 procedures.
A2.06 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and 215005 APRM I LPRM x (b) based on those predictions, use 3.5 90 procedures to correct, control, or mitigate the consequences of those abnormal conditions Recirculation flow channels upscale Kl.05 - Knowledge of the physical connections and/or cause- effect relationships between 239002 SRVs x RELIEF/SAFETY VAL YES and 3.1 I the following: Plant air systems:
Plant-Specific Kl.OJ - Knowledge of the physical connections and/or cause- effect relationships between 215003 IRM x INTERMEDIATE RANGE 3.9 2 MONITOR (IRM) SYSTEM and the following: RPS K2.02 - Knowledge of electrical 203000 RHR/LPCI: Injection Mode x power supplies to the following: 2.5 3 Valves K2.0l - Knowledge of electrical 400000 Component Cooling Water x power supplies to the following: 2.9 4 CCWpumps K3.03 - Knowledge of the effect that a loss or malfunction of the 209001 LPCS x LOW PRESSURE CORE SPRAY 2.9 5 SYSTEM will have on following:
Emergency generators
ES-401 4 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G Q#
1 2 3 4 5 6 1 3 4 K3.02 - Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL 211000 SLC x SYSTEM will have on following:
3.0 6 Core spray line break detection system: Plant-Specific K4.08 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or interlocks 215005 APRM I LPRM x which provide for the following:
2.7 7 Sampling of overall core power in each APRM (accomplished through LPRM assignments and symmetrical rod patterns)
K4.0l - Knowledge of SOURCE RANGE MONITOR (SRM) 215004 Source Range Monitor x SYSTEM design feature(s) and/or 3.7 8 interlocks which provide for the following: Rod withdrawal blocks K5.02 - Knowledge of the operational implications of the following concepts as they apply to 212000 RPS x REACTOR PROTECTION 3.3 9 SYSTEM: Specific logic arrangements K5.06 - Knowledge of the operational implications of the 264000 EDGs x following concepts as they apply to 3.4 10 EMERGENCY GENERA TORS (DIESEL/JET): Load sequencing K6.0l - Knowledge of the effect that a loss or malfunction of the following will have on the 218000 ADS x AUTOMATIC 3.9 II DEPRESSURIZATION SYSTEM:
RHR/LPCI system pressure: Plant-Specific K6.0l - Knowledge of the effect that a loss or malfunction of the 263000 DC Electrical Distribution x following will have on the D.C. 3.2 12 ELECTRICAL DISTRIBUTION:
A.C. electrical distribution Al .07 - Ability to predict and/or monitor changes in parameters associated with operating the 217000 RCIC x REACTOR CORE ISOLATION 3.3 13 COOLING SYSTEM (RCIC) controls including: Suppression pool level Al .09 - Ability to predict and/or monitor changes in parameters associated with operating the SHUTDOWN COOLING 205000 Shutdown Cooling x SYSTEM (RHR SHUTDOWN 2.8 14 COOLING MODE) controls including: SDC/RHR pump/system discharge pressure
ES-401 4 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 System # I Name K K K K K K A A A Imp A2 G Q#
1 2 3 4 5 6 1 3 4 A2.03 - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) 259002 Reactor Water Level Control x based on those predictions, use 3.6 15 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Loss of reactor water level input A2.07 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF; and 223002 PCIS/Nuclear Steam Supply Shutoff x (b) based on those predictions, use 2.7 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Various process instrumentation failures A3.02 - Ability to monitor 262001 AC Electrical automatic operations of the AC.
Distribution x ELECTRICAL DISTRIBUTION 3.2 17 including: Automatic bus transfer A3.02 -Ability to monitor automatic operations of the 261000 SGTS x STANDBY GAS TREATMENT 3.2 18 SYSTEM including: Fan start A4.13 - Ability to manually operate 206000 HPCI x and/or monitor in the control room: 4.1 19 Turbine reset control: BWR-2,3,4 A4.0l -Ability to manually operate 3 00000 Instrument Air x and/or monitor in the control room: 2.6 20 Pressure gauges 2.4.8 - Emergency Procedures I Plan: Knowledge of how abnormal 262002 UPS (AC/DC) x operating procedures are used in 3.8 21 conjunction with EOPs.
2.1.20 - Conduct of Operations:
215004 Source Range Monitor x Ability to interpret and execute 4.6 22 procedure steps.
A4.0l Ability to manually operate 400000 Component Cooling and I or monitor in the control 3.1 23 Water x room: CCW indications and control A3.0l - Ability to monitor automatic operations of the EMERGENCY GENERATORS 264000 EDGs x (DIESEL/JET) including:
3.0 24 Automatic starting of compressor and emergency generator Kl.13 - Knowledge of the physical connections and/or cause-effect relationships between 262002 UPS (AC/DC) x UNINTERRUPTABLE POWER 2.5 25 SUPPLY (A.C./D.C.) and the following: Recirculation pump speed control: Plant-Specific
ES-401 4 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G Q#
1 2 3 4 5 6 1 3 4 K4.14- Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design feature(s) and/or 259002 Reactor Water Level Control x interlocks which provide for the 3.4 26 following: Selection of various instruments to provide reactor water level input KIA Category Totals: 3 2 2 3 2 2 2 2/3 3 3 2/2 Group Point Total: 2615 I
ES-401 5 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G Imp.
1 2 3 4 5 6 1 3 4 #
A2.08 - Ability to (a) predict the impacts of the following on the CRD HYDRAULIC SYSTEM; and (b) based on those predictions, use 201001 CRD Hydraulic x procedures to correct, control, or 2.8 91 mitigate the consequences of abnonnal conditions or operations:
Inadequate system flow 2.2.40 - Equipment Control: Ability 230000 RHR/LPCI:
Torus/Pool Spray Mode x to apply technical specifications for 4.7 92 a system.
2.1.30 - Conduct of Operations:
290002 Reactor Vessel Ability to locate and operate Internals x components, including local 4.0 93 controls.
Kl.04 - Knowledge of the physical connections and/or cause- effect 290002 Reactor Vessel Internals x relationships between REACTOR 3.4 27 VESSEL INTERNALS and the following: HPCI: Plant-Specific K2.02 - Knowledge of electrical 233000 Fuel Pool Cooling/Cleanup x power supplies to the following: 2.8 28 RHRpumps K3. 03 - Knowledge of the effect that a loss or malfunction of the 201003 Control Rod and Drive Mechanism x CONTROL ROD AND DRIVE 3.2 29 MECHANISM will have on following: Shutdown margin K4.01 - Knowledge of TRAVERSING IN-CORE PROBE 21500 I Traversing In-core design feature(s) and/or interlocks Probe x which provide for the following:
3.4 30 Primary containment isolation:
Mark-l&ll(Not-BWRI)
K5.04 - Knowledge of the operational implications of the 286000 Fire Protection x following concepts as they apply to 2.9 31 FIRE PROTECTION SYSTEM:
Valve operation K6.05 - Knowledge of the effect that a loss or malfunction of the 215002 RBM x following will have on the ROD 2.8 32 BLOCK MONITOR SYSTEM:
LPRM detectors: BWR-3,4,5 Al.OJ - Ability to predict and/or monitor changes in parameters associated with operating the 201002 RMCS x REACTOR MANUAL CONTROL 2.8 33 SYSTEM controls including: CRD drive water flow A2.01 - Ability to (a) predict the impacts of the following on the RADWASTE; and (b) based on those predictions, use procedures to 268000 Radwaste x correct, control, or mitigate the 2.9 34 consequences of those abnormal conditions or operations: System rupture
ES-401 5 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System #I Name A2 G Imp.
1 2 3 4 5 6 1 3 4 #
A3.02 - Ability to monitor automatic operations of the SECONDARY CONTAINMENT 290001 Secondary CTMT x including: Normal building 3.5 35 differential pressure: Plant-Specific A4. l 0 - Ability to manually operate 245000 Main Turbine Gen. I Aux.
x and/or monitor in the control room: 2.6 36 Hydrogen gas pressure 2.2.38 - Equipment Control:
201001 CRD Hydraulic x Knowledge of conditions and 3.6 37 limitations in the facility license.
K3.05 - Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION 288000 Plant Ventilation x SYSTEMS will have on following:
3.1 38 Reactor building pressure: Plant-Specific KIA Category Totals: 1 1 2 1 1 1 1 1/1 1 1 1/2 Group Point Total:
I 12/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 LOC27 NRG Written Exam Facility: Date: 8/17/15 Outline RO SRO-Only Category KIA# Topic IR Q# IR Q#
Knowledge of facility requirements for 2.1.13 3.2 94 controllinq vital I controlled access.
Ability to use procedures to determine the effects on reactivity of plant changes, such as 2.1.43 4.3 98 RCS temperature, secondary plant, fuel depletion, etc.
Knowledge of individual licensed operator
- 1. responsibilities related to shift staffing, such Conduct 2.1.4 as medical requirements, "no-solo" operation, 3.3 66 of Operations maintenance of active license status, 10CFR55, etc.
Ability to evaluate plant performance and make operational judgements based on 2.1.7 4.4 67 operating characteristics, reactor behavior, and instrument interpretation.
Subtotal 2 2 Knowledge of the process for conducting 2.2.7 3.6 95 special or infrequent tests.
Knowledge of the process for managing maintenance activities during shutdown 2.2.18 3.9 100 operations, such as risk assessments, work prioritization, etc.
2.
Equipment Knowledge of tagging and clearance Control 2.2.13 4.1 68 procedures.
(multi-unit license) Knowledge of the design, 2.2.3 procedural, and operational differences 3.8 69 between units.
Subtotal 2 2 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.5 2.9 96 portable survey instruments, personnel 3.
monitorinq equipment, etc.
Radiation Control
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor 2.3.13 3.4 70 alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.
Knowledge of radiation exposure limits under 2.3.4 3.2 71 normal or emerqencv conditions.
Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.5 2.9 72 portable survey instruments, personell monitorinq equipment, etc.
Subtotal 3 1 Ability to recognize abnormal indications for system operating parameters which are 2.4.4 4.7 97 entry-level conditions for emergency and abnormal operating procedures.
Knowledge of facility protection requirements, 2.4.26 including fire brigade and portable fire fighting 3.6 99 equipment usaqe.
4.
Emergency Procedures I Plan Ability to identify post-accident 2.4.3 3.7 73 instrumentation.
2.4.18 Knowledge of the specific bases for EOPs. 3.3 74 Knowledge of the lines of authority during 2.4.37 3.0 75 implementation of the emergency plan.
Subtotal 3 2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/A's Form ES-401-4 Tier I Group Randomly Selected KIA Reason for Rejection Question 9 An operationally relevant question could not be developed for the randomly selected KIA.
212000 RPS Randomly re-selected KIA 212000 RPS K5.02 -
K5.01 - Knowledge of the Knowledge of the operational implications of the 2I 1 operational implications of the following concepts as they apply to REACTOR following concepts as they PROTECTION SYSTEM: Specific logic apply to REACTOR arrangements.
PROTECTION SYSTEM: Fuel thermal time constant Question 21 An acceptable question could not be developed for the randomly selected KIA without testing minutia.
262002 UPS (AC/DC)
Randomly re-selected KIA 262002 UPS (AC/DC) 2.4.50 - Emergency 2.4.8 - Emergency Procedures I Plan: Knowledge of 2/1 Procedures I Plan: Ability to how abnormal operating procedures are used in verify system alarm setpoints conjunction with EOPs.
and operate controls identified in the alarm response manual.
Question 22 There are no bases in EOPs related specifically to the SRMs that support developing an acceptable 215004 Source Range question.
Monitor 2I 1 Randomly re-selected KIA 215004 Source Range 2.4.18 - Emergency Monitor 2.4.49 - Ability to perform without reference to Procedures I Plan: Knowledge procedures those actions that require immediate of the specific bases for operation of system components and controls.
EOPs.
Question 23 The randomly selected KIA is the exact same KIA as for Question 87. Re-selecting to limit overlap.
400000 Component Cooling Water Randomly re-selected KIA 400000 Component A2.03 - Ability to (a) predict Cooling Water A4.01 - Ability to manually operate and the impacts of the following on I or monitor in the control room: CCW indications and the CCWS and (b) based on control.
2I 1 those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
High/low CCW temperature
ES-401 Record of Rejected K/A's Form ES-401-4 Question 24 The randomly selected KJA overlaps with the KJA for question 10.
264000 EDGs Randomly re-selected KJA 264000 EDGs A3.01 -
A3.05 - Ability to monitor Ability to monitor automatic operations of the 2/1 automatic operations of the EMERGENCY GENERATORS (DIESEL/JET)
EMERGENCY including: Automatic starting of compressor and GENERATORS (DIESEL/JET) emergency generator.
including: Load shedding and sequencing Question 25 The facility does not have motor-generators sets associated with system 262002 UPS (AC/DC).
262002 UPS (AC/DC)
Randomly re-selected KJA 262002 UPS (AC/DC)
A 1. 02 - Ability to predict K1 .13 - Knowledge of the physical connections and/or 2/ 1 and/or monitor changes in cause-effect relationships between parameters associated with UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)
operating the and the following: Recirculation pump speed control:
UNINTERRUPTABLE Plant-Specific POWER SUPPLY (A.C./D.C.)
controls including: Motor generator outputs Question 29 An acceptable question could not be developed for the randomly selected KJA without testing GFE 201003 Control Rod and Drive knowledge.
Mechanism Randomly re-selected KJA 201003 Control Rod and 2/2 Drive Mechanism K3.03 - Knowledge of the effect that K3.02 - Knowledge of the a loss or malfunction of the CONTROL ROD AND effect that a loss or DRIVE MECHANISM will have on following:
malfunction of the CONTROL Shutdown margin.
ROD AND DRIVE MECHANISM will have on following: Flux shaping Question 31 An acceptable question could not be developed at the license level for the randomly selected KJA.
286000 Fire Protection Randomly re-selected KJA 286000 Fire Protection K5.04 - Knowledge of the operational implications of K5.03 - Knowledge of the the following concepts as they apply to FIRE 212 operational implications of the PROTECTION SYSTEM: Valve operation.
following concepts as they apply to FIRE PROTECTION SYSTEM : Effect of water spray on electrical components
ES-401 Record of Rejected K/A's Form ES-401-4 Question 80 An acceptable SRO level question cannot be developed for the randomly selected generic KIA 700000 Generator Voltage because less than one hour Technical Specifications and Electric Grid Disturbances are required RO knowledge.
1I 1 2.2.39 - Equipment Control:
Knowledge of less than one Randomly re-selected KIA 700000 Generator Voltage hour technical specification and Electric Grid Disturbances 2.2.25 - Equipment action statements for systems. Control: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Question 39 A question cannot be developed for the randomly selected KIA without overlapping Question 76.
295006 SCRAM Randomly re-selected KIA 295006 SCRAM AK1 .01 -
1I 1 Knowledge of the operational implications of the AK1 .02 - Knowledge of the following concepts as they apply to SCRAM: Decay operational implications of the following concepts as they heat generation and removal.
apply to SCRAM: Shutdown margin Question 58 A question cannot be developed for the randomly selected combination of emergency plant evolution 295024 High Drywell Pressure and generic KIA without testing minutia.
1I 1 2.4.50 - Emergency Randomly re-selected KIA 295024 High Drywell Procedures I Plan: Ability to Pressure 2.1.23 - Ability to perform specific system verify system alarm setpoints and integrated plant procedures during all modes of and operate controls identified plant operation.
in the alarm response manual Question 59 An operationally oriented question cannot be developed at the appropriate license level for the 295017 High Off-site Release randomly selected KIA.
Rate Randomly re-selected KIA 295017 High Off-site Release Rate AK1 .02 - Knowledge of the operational AK1 .03 - Knowledge of the implications of the following concepts as they apply to operational implications of the HIGH OFF-SITE RELEASE RATE: Protection of the following concepts as they 1I 2 general public.
apply to HIGH OFF-SITE RELEASE RATE:
Meteorological effects on off-site release
ES-401 Record of Rejected K/A's Form ES-401-4 Question 61 A discriminating question cannot be developed for the randomly selected KIA without overlapping concepts 295009 Low Reactor Water tested in Question 50.
Level Randomly re-selected KIA 295009 Low Reactor Water 1I 2 Level AK3.02 - Knowledge of the reasons for the AK3.01 - Knowledge of the following responses as they apply to LOW REACTOR reasons for the following WATER LEVEL: Reactor feedpump runout flow responses as they apply to control: Plant-Specific.
LOW REACTOR WATER LEVEL: Recirculation pump run back: Plant-Specific Question 65 An acceptable question cannot be developed at the appropriate license level for the given abnormal plant 295010 High Drywell Pressure evolution with the randomly selected generic KIA Randomly re-selected KIA 295010 High Drywell 1I 2 2.2.36 - Equipment Control:
Pressure 2.2.22 - Knowledge of limiting conditions for Ability to analyze the effect of operations and safety limits.
maintenance activities, such as degraded power sources, on the status of limiting conditions for operations Question 68 The randomly selected KIA is oversampled (also selected for Question 95).
2.2.7 - Equipment Control:
3 Knowledge of the process for Randomly re-selected KIA 2.2.13 - Knowledge of conducting special or tagging and clearance procedures.
infrequent tests.
Question 81 An acceptable question cannot be developed for the given abnormal plant evolution with the randomly 295001 Partial or Complete selected generic KIA due to a lack of difference Loss of Forced Core Flow between the Units for this topic.
Circulation Randomly re-selected KIA 295001 Partial or Complete Loss of Forced Core Flow Circulation 2.4.9 -
2.2.3 - Equipment Control:
Knowledge of low power/shutdown implications in (multi-unit license) Knowledge 1I 1 accident (e.g., loss of coolant accident or loss of of the design, procedural, and residual heat removal) mitigation strategies.
operational differences between units.
ES-401 Record of Rejected K/A's Form ES-401-4 Question 22 A question cannot be developed for the randomly selected KIA due to lack of immediate actions 215004 Source Range associated with the SRMs.
Monitor Randomly re-selected KIA 215004 Source Range 2.4.49 - Emergency Monitor 2.1.20 - Conduct of Operations: Ability to 2I 1 Procedures I Plan: Ability to interpret and execute procedure steps.
perform without reference to procedures those actions that require immediate operation of system components and controls.
Question 66 A discriminating question cannot be developed for the randomly selected KIA at the license level.
2.1.18 - Ability to make accurate, clear and concise Randomly re-selected KIA 2.1.4 - Knowledge of 3
logs, records, status boards, individual licensed operator responsibilities related to and reports. shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susguehanna, LLC Date of Examination: 8/17/2015 Examination Level: RO [8J SRO D Operating Test Number: U01916 Administrative Topic Type Describe activity to be performed (See Note) Code*
Cooldown Rate Calculation Conduct of Operations R,N (OO.G0.1178.101)
C001 General KIA- 2.1.7 RO 4.4 SRO 4.7 Review Failed ST and Determine Required Action Conduct of Operations R,D (51.S0.1944.151)
C002 General KIA - 2.2.12 RO 3. 7 SRO 4.1 Blocking and Tagging Equipment Control R,D (OO.AD.3274.202)
EC General KIA- 2.2.41 RO 3.5 SRO 3.9 Radiation Control Emergency Plan Communications Emergency Plan S,D (OO.EP.1135.001)
EP General KIA - 2.4.39 RO 3.9 NOTE: All items (five total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~ 3 for ROs; ~ 4 for SR Os & RO retakes)
(N)ew or (M)odified from bank (~ 1)
(P)revious 2 exams (~ 1; randomly selected)
ES 301, Page 22 of 27
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susguehanna, LLC Date of Examination: 8/17/2015 Examination Level: RO D SRO ~ Operating Test Number: U01916 Administrative Topic Type Describe activity to be performed (See Note) Code*
Determine NRG Notification Requirements Conduct of Operations R,D (00.AD.1032.001)
C001 General KIA-2.81.18 SRO 3.8 Review failed ST and determine required actions Conduct of Operations R,D (51.S0.1944.151)
C002 General KIA - 2.2.12 RO 3.7 SRO 4.1 Blocking and Tagging Equipment Control R,D (OO.AD.327 4.201)
EC General KIA- 2.2.41 RO 3.5 SRO 3.9 Calculate and Approve Emergency Exposure Radiation Control R,D (OO.EP.1132.185)
RC General KIA- 2.3.4 SRO 3.7 Make EAL Classification Emergency Plan S,N (OO.EP.1132.180)
EP General KIA- 2.4.41 SRO 4.6 NOTE: All items (five total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all five items).
- 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)
ES 301, Page 22 of 27
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Susguehanna, LLC Date of Examination: 8/17/2015 Exam Level: RO [81 SRO-I D SRO-U D Operating Test Number: U01916 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U Safety System I JPM Title Type Code*
Function
- a. Respond to Control Rod Drift In During Performance of Rod Exercise A,D,P,S 1 Test (55.0N.1998.151)
- b. Quick Recovery of the Condensate System, Respond to a Loss of A,N,S 2 TBCCW (44.0P.4652.151)
- c. Quarterly Turbine Valve Cycling (93.S0.2467.101) D,S 3
- d. Core Spray System Shutdown (51.0P.1933.101) D,S 4
- e. Shutdown Cooling Temperature Control (49.0N.1869.151) A,D,EN,L,S 5
- g. Restore Offgas System IAW ON-143-001 (72.0N.1786.151) A,P,S 9
- h. APRM Gain Adjust (78.0P.3677.101) D,S 7 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- k. Manual Emergency Shutdown of Diesel Generator 'A' (24.0P.1443.051) D,E 6
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~91 ~8 I ~4 (E)mergency or abnormal in-plant :::_ 1 I > 1 I :::_ 1 (EN)gineered safety feature :::_1 I :::_1 I:::_ 1(control room system)
(L)ow-Power I Shutdown :::_ 1 I :::. 1 I :::_ 1 (N)ew or (M)odified from bank including 1(A) > 2 I :::_2 I :::_ 1 (P)revious 2 exams ~3I ~3 I~ 2 (randomly selected)
(R)CA :::_ 1 I > 1 I :::_ 1 (S)imulator ES-301, Page 23 of 27
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Susguehanna, LLC Date of Examination: 8/17/2015 Exam Level: RO D SRO-I ~ SRO-U D Operating Test Number: U01916 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U Safety System I JPM Title Type Code*
Function
- a. Respond to Control Rod Drift In During Performance of Rod Exercise A,D,P,S 1 Test (55.0N.1998.151)
- b. Quick Recovery of the Condensate System, Respond to a Loss of A, N,S 2 TBCCW (44.0P.4652.151)
- c. Quarterly Turbine Valve Cycling (93.S0.2467.101) D,S 3
- d. Core Spray System Shutdown (51.0P.1933.101) D,S 4
- e. Shutdown Cooling Temperature Control (49.0N.1869.151) A,D,EN,L,S 5
- h. APRM Gain Adjust (78.0P.3677.101) D,S 7 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- k. Manual Emergency Shutdown of Diesel Generator 'A' (24.0P.1443.051) D,E 6
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 I SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~9/ ~8 I ~4 (E)mergency or abnormal in-plant _:: 1 I .'.: 1 I _:: 1 (EN)gineered safety feature _::1 I _:: 1 I _:: 1(control room system)
(L)ow-Power I Shutdown _:: 1 I .'.: 1 I _:: 1 (N)ew or (M)odified from bank including 1(A) _:: 2 I _::2 I _:: 1 (P)revious 2 exams ~ 31 ~3 /~ 2 (randomly selected)
(R)CA > 1 I .'.: 1 I _:: 1 (S)imulator ES-301, Page 23 of 27
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Susguehanna, LLC Date of Examination: 8/17/2015 Exam Level: RO 0 SRO-I 0 SRO-U [8J Operating Test Number: U01916 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U Safety System I JPM Title Type Code*
Function a.
- b. Quick Recovery of the Condensate System, Respond to a Loss of A,N,S 2 TBCCW (44.0P.4652.151) c.
d.
- e. Shutdown Cooling Temperature Control (49.0N.1869.151) A,D,EN,L,S 5
h.
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- k. Manual Emergency Shutdown of Diesel Generator 'A' (24.0P.1443.051) D,E 6
- All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 I SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~91 ~8 I ~4 (E)mergency or abnormal in-plant '.'.:. 1 I '.'.:. 1 I '.'.:. 1 (EN)gineered safety feature :::.1 I :::.1 I :::. 1(control room system)
(L)ow-Power I Shutdown '.'.:. 1 I '.'.:. 1 I '.'.:. 1 (N)ew or {M)odified from bank including 1(A) '.'.:. 2 I :::.2 I '.'.:. 1 (P)revious 2 exams ~3 / ~3 I~ 2 (randomly selected)
(R)CA '.'.:. 1 I '.'.:. 1 I '.'.:. 1 (S)imulator ES-301, Page 23 of 27
Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Scenario No.: 2 Op-Test No.: U01916 Examiners: Operators:
Initial Conditions IC-12 Reactor A~~roach to Run, Mode Switch in Startu~
Turnover
- A Reactor Startup is in progress following a refueling outage .
- The Reactor Mode Switch is in Startup .
- Reactor power is approximately 3% with the IRMs on Range 9 .
- Reactor Pressure is 940 psig with 1/2 bypass valve open .
- G0-100-002 is complete through step 5.59.2
- Main condenser back pressure has lowered to allow placing Off Gas in service.
- The Off Gas system is prepared for placing SJAE in-service .
- The directions to the shift are to:
- Place Off Gas in service and secure the Mechanical Vacuum Pump
- Continue the reactor startup.
Event Malf. No. Event Event No. Type* Description N Place Off Gas in Service 1 N/A SRO, BOP R Raise Reactor Power by Withdrawing Control Rods 2 N/A SRO,ATC mfRD155007 c Uncoupled Control Rod 3 mfRD155006 TS SRO,ATC mfRWMIOM I Rod Worth Minimizer Failure 4 ALF TS mfJM156004 SRO,ATC 5
DEL mfRD155006 c Control Rod Drop SRO,ATC 6 mfRR179003 c Fuel Failure SRO,BOP cmfAV04_ M SDIV Vent and Drain Valves Fail to Close 7 XV147 All
mfCU161007 Reactor Water Cleanup Pipe Break Without Auto cmfMVOG_
8 HV144F001 Isolation cmfMVOG_ All HV144F004 cmfMV09_
HV144F001 c Reactor Water Cleanup Isolation Valves Fail to Close 9 cmfMV09_ SRO, BOP HV144F004
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Scenario Actual Target Quantitative Attributes (Per Scenario; See Section D.5.d)
Events Attributes
- 1. Malfunctions after EOP entry (1-2) 6,8,9 3
- 2. Abnormal events (2-4) 3,4 2
- 3. Major transients (1-2) 7 1
- 4. EOPs entered/requiring substantive actions (1-2) Secondary Containment 1 Control
- 5. EOP contingencies requiring substantive actions (0-2) Emergency Depressurization 1
- 6. Critical tasks (2-3) 2 CT-1 Recognize a failure to scram condition and initiate a manual scram within 60 seconds.
CT-2 Perform Emergency Depressurization when Two Secondary Containment areas exceed maximum safe radiation levels with a Primary System discharging into Secondary Containment.
Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Scenario No.: 3 Op-Test No.: U01916 Examiners: Operators:
Initial Conditions Unit 1 approximately 23% power during shutdown, BOL Turnover
- A Reactor Shutdown is in progress in preparation for a turbine outage .
- Reactor power is approximately 23% .
- G0-100-004 is complete through step 5.2.1
- The directions to the shift are to:
- Reduce reactor power to 20%
- Transfer the auxiliary busses to the startup transformer Event Malf. No. Event Event No. Type* Description R Lower Reactor Power by Inserting Control Rods 1 N/A SRO,ATC N Transfer Auxiliary Susses 2 N/A SRO,BOP cmfTD04 PD I Narrow Range Instrument Failure 3 TC321N004 TS SRO,BOP mfDS003007 c Loss of Auxiliary Bus 11 B 4 cmfBR03_ TS 1A10204 All 5 mfMC143001 c Loss of Vacuum ALL mfRP158007 M ATWS due to RPS and ARI Failing to Actuate 6 cmfRL01 -
All 63X114 7 mfSL 153001 c SBLC Fails to Inject SRO,BOP 8 mfRD155002 c CRD Pump Trip and Flow Control Valve Failure SRO, BOP
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Scenario Actual Target Quantitative Attributes (Per Scenario; See Section 0.5.d)
Events Attributes
- 1. Malfunctions after EOP entry (1-2) 7,8 2
- 2. Abnormal events (2-4) 3,4,5, 3
- 3. Major transients (1-2) 6 1
- 5. EOP contingencies requiring substantive actions (0-2) Level/Power 1
Control
- 6. Critical tasks (2-3) 2 CT-1 Lowers RPV level to < -60" but > -179" CT-2 Inserts control rods IAW E0-000-113 Sht. 2
Appendix D Scenario Outline Form ES-D-1 Facility: SSES Units 1 and 2 Scenario No.: Op-Test No.:
U01916 Examiners: Operators:
Initial Conditions Unit 1 approximate!~ 97% power MOL Turnover Reactor power 97% following rod exercising.
SRV Pis leaking. Tailpipe temperature is approximately 235°F.
Unit 2 is at rated power.
Directions to the shift is to raise power to 100% using recirculation flow.
Event Malf. Event Event No. No. Type* Description R Raise Reactor Power with Recirc Flow 1 N/A SRO,ATC mfNM17800 I APRM Fails Upscale 2 7A TS SRO,ATC mfHP15200 c Inadvertent HPCI Initiation 3 4 TS SRO,BOP 4 N/A N Shutdown HPCI and Place in a Standby Lineup SRO,BOP 5
cmfEB01_1 A201 c Electrical Fault on ESS Bus 1A (1A201)
ALL mfMS18300 M Main Steam Leak into Turbine Building 6 8 ALL cmfAVOG_H V141F028D I MSIVs Fail to Automatically Close 7
cmfAVOG_H SRO,BOP V141F022D mfDS00300 7 M Loss of Offsite Power 8 mfDS00300 ALL 8
mfDG02400 9
SC mfDG02400 c EOG C Fails to Start, EDGs B and D Fail to Auto-Start SRO, BOP 18(0)
mfRC15000 HPCI and RCIC Fail to Auto-Initiate and Initiation 10 1 diHS15012 c Pushbuttons Fail to ARM ALL CB
- (N)ormal, (R)eactivity, (l}nstrument, (C)omponent, (M)ajor Scenario Actual Target Quantitative Attributes (Per Scenario; See Section D.5.d)
Events Attributes
- 1. Malfunctions after EOP entry (1-2) 7,9,10 3
- 2. Abnormal events (2-4) 3,5 2
- 3. Major transients (1-2) 6,8 2
- 5. EOP contingencies requiring substantive actions (0-2) 0
- 6. Critical tasks (2-3) 2 CT-1 Manually isolate a Main Steam Line break.
CT-2 Restore power to an ESS Bus by manually starting an emergency diesel generator.