ML15244A314
| ML15244A314 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/30/2015 |
| From: | Todd Fish Operations Branch I |
| To: | Susquehanna |
| Shared Package | |
| ML15063A453 | List: |
| References | |
| TAC U01916 | |
| Download: ML15244A314 (24) | |
Text
ES-401 Written Examination Outline Form ES-401-1 Facility:
LOC27 NRC Written Date of Exam:
08/17/15 Exam Outline RO Kl A Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
1 2
3 4
5 6
1 2
3 4
Total A2 G*
Total
- 1.
1 3
4 3
3 3
4 20 3
4 7
Emergency 2
1 1
1 1
1 2
7 2
1 3
Plant Tier
,,, I,'
Evolutions 4
5 4
4 4
6 27 5
5 10 Totals 1
2 2
2 3
2 2
3 3
3 2
2 26 3
2 5
- 2.
Plant 2
1 1
2 1
1 1
1 1
1 1
1 12 0
1 2
3 Systems Tier Totals 3
3 4
4 3
3 4
4 4
3 3
38 4
4 8
- 3. Generic Knowledge & Abilities 1
2 3
4 1
2 3
4 10 7
Categories 2
2 3
3 2
2 1
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 0.1.b ofES-401, for guidance regarding elimination of inappropriate Kl 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 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 1 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 0.1.b of ES-401 for the applicable K/A's
- 8.
On the following pages, enter the Kl A 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, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to IOCFR55.43
ES-401 2
Form ES-401-1 LOC27 NRG Written Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A 1 A2 G
KIA Topic(s)
AA2.05 - Ability to detennine and/or 295006 SCRAM I I x
interpret the following as they apply to SCRAM : Whether a reactor SCRAM has occurred AA2.04 - Ability to detem1ine and/or 295005 Main Turbine Generator x
interpret the following as they apply to Trip I 3 MAIN TURBINE GENERA TOR TRIP :
Reactor pressure EA2.03 - Ability to determine and/or 295028 High Drywell Temperature x
interpret the following as they apply to 15 HIGH DRYWELL TEMPERATURE:
Reactor water level 295038 High Oft:site Release Rate 2.4.11 - Emergency Procedures I Plan:
x Knowledge of abnormal condition 19 procedures.
700000 Generator Voltage and 2.2.39 - Equipment Control: Knowledge of Electric Grid Disturbances x
less than one hour technical specification action statements for systems.
295001 Partial or Complete Loss of 2.2.3 - Equipment Control: (multi-unit Forced Core Flow Circulation I I &
x license) Knowledge of the design, 4
procedural, and operational differences between units.
2.2.44 - Equipment Control: Ability to interpret control room indications to verify 295004 Partial or Total Loss of DC x
the status and operation of a system, and Pwr/6 understand how operator actions and directives effect plant and system conditions.
AKl.02 - Knowledge of the operational 295006 SCRAM I I x
implications of the following concepts as they apply to SCRAM : Shutdown margin AKI.OJ - Knowledge of the operational 295021 Loss of Shutdown Cooling x
implications of the following concepts as
/4 they apply to LOSS OF SHUTDOWN COOLING : Decay heat AKl.03 - Knowledge of the operational 295004 Partial or Total Loss of DC implications of the following concepts as Pwr/6 x
they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Electrical bus divisional separation EK2.03 - Knowledge of the interrelations 295037 SCRAM Conditions between SCRAM CONDITION PRESENT Present and Reactor Power Above x
AND REACTOR POWER ABOVE APRM APRM Downscale or Unknown I I DOWNSCALE OR UNKNOWN and the following: ARVRPT/ATWS: Plant-Specific EK2.02 - Knowledge of the interrelations 295030 Low Suppression Pool x
between LOW SUPPRESSION POOL Water Level I 5 WATER LEVEL and the following:
RCIC: Plant-Specific AK2.06 - Knowledge of the interrelations 700000 Generator Voltage and x
between GENERA TOR VOLTAGE AND Electric Grid Disturbances ELECTRIC GRID DISTURBANCES and the followinq: Reactor power.
AK3.01 - Knowledge of the reasons for 295016 Control Room x
the following responses as they apply to Abandonment I 7 CONTROL ROOM ABANDONMENT :
Reactor SCRAM AK3.04 - Knowledge of the reasons for 600000 Plant Fire On-site I 8 x
the following responses as they apply to PLANT FIRE ON SITE: Actions Imp.
Q#
4.6 76 3.8 77 3.9 78 4.2 79 4.5 80 3.9 81 4.4 82 3.4 39 3.6 40 2.9 41 4.1 42 3.7 43 3.9 44 4.1 45 2.8 46
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) contained in the abnormal procedure for plant fire on site EK3.02 - Knowledge of the reasons for 295038 High Off-site Release Rate x
the following responses as they apply to 19 HIGH OFF-SITE RELEASE RATE:
Svstem isolations EA 1.01 - Ability to operate and/or 295025 High Reactor Pressure I 3 x
monitor the following as they apply to HIGH REACTOR PRESSURE: Main steam line drains AA 1.03 - Ability to operate and/or 295023 Refueling Ace Cooling x
monitor the following as they apply to Mode/ 8 REFUELING ACCIDENTS : Fuel handling equipment AA 1.01 - Ability to operate and/or 295005 Main Turbine Generator x
monitor the following as they apply to Trip/ 3 MAIN TURBINE GENERATOR TRIP:
Recirculation system: Plant-Specific EA2.02 - Ability to determine and/or 295031 Reactor Low Water Level x
interpret the following as they apply to
/2 REACTOR LOW WATER LEVEL:
Reactor power AA2.03 - Ability to determine and/or 295018 Partial or Total Loss of interpret the following as they apply to CCW/8 x
PARTIAL OR COMPLETE LOSS OF 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 Total Loss of x
PARTIAL OR COMPLETE LOSS OF Inst. Air/ 8 INSTRUMENT AIR : Status of safety-related instrument air system loads (see AK2.1 - AK2.19l 295003 Partial or Complete Loss 2.4.1 - Emergency Procedures I Plan:
of AC I 6 x
Knowledge of EOP entry conditions and immediate action steps.
295001 Partial or Complete Loss 2.1.32 - Conduct of Operations: Ability of Forced Core Flow Circulation I 1 x
to explain and apply all system limits
&4 and precautions.
295026 Suppression Pool High 2.4.20 - Emergency Procedures I Plan:
Water Temp./ 5 x
Knowledge of operational implications of EOP warninqs, cautions, and notes.
EK2.04 - Knowledge of the interrelations 295028 High Drywell Temperature x
between HIGH DRYWELL I 5 TEMPERATURE and the following:
Orywell ventilation 2.4.50 - Emergency Procedures I Plan:
295024 High Drywell Pressure I 5 x
Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Kl A Category Totals:
3 4
3 3
3/3 4/4 Group Point Total:
Imp.
Q#
3.9 47 2.9 48 3.3 49 3.1 50 4.0 51 3.2 52 3.6 53 4.6 54 3.8 55 3.8 56 3.6 57 4.2 58 I
2017
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)
EA2.0l - Ability to determine and/or 295029 High Suppression Pool x
interpret the following as they apply to Water Level I 5 HIGH SUPPRESSION POOL WATER LEVEL : Suppression pool water level 2.4.35 - Emergency Procedures I Plan:
295007 High Reactor Pressure I 3 x
Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects.
AA2.05 - Ability to determine and/or 295014 Inadvertent Reactivity x
interpret the following as they apply to Addition/ I INADVERTENT REACTIVITY ADDITION : Violation of safety limits AKl.03 - Knowledge of the operational 295017 High Off-site Release implications of the following concepts as x
they apply to HIGH OFF-SITE RELEASE Rate/ 9 RATE: Meteorological effects on off-site release EK2.03 - Knowledge of the interrelations 295034 Secondary Containment x
between SECONDARY CONTAINMENT Ventilation High Radiation/ 9 VENTILATION HIGH RADIATION and the following: SBGT/FRVS: Plant-Specific AK3.01 - Knowledge of the reasons for the 295009 Low Reactor Water Level x
following responses as they apply to LOW 12 REACTOR WATER LEVEL : Recirculation pump run back: Plant-Specific AAl.01 - Ability to operate and/or monitor 295015 Incomplete SCRAM I 1 x
the following as they apply to INCOMPLETE SCRAM : CRD hydraulics EA2.02 - Ability to determine and/or 295029 High Suppression Pool x
interpret the following as they apply to Water Level I 5 HIGH SUPPRESSION POOL WATER LEVEL : Reactor pressure 2.4.21 - Emergency Procedures I Plan:
Knowledge of the parameters and logic used 295036 Secondary Containment to assess the status of safety functions, such x
as reactivity control, core cooling and heat High Sump/Area Water Level I 5 removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
2.2.36 - Equipment Control: Ability to 295010 High Drywell Pressure I 5 x
analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
KIA Category Totals:
1 1
1 1
1/2 2/1 Group Point Total:
Imp.
Q#
3.9 83 4.0 84 4.6 85
- 2.
59 7
4.3 60
- 3.
61 2
- 3.
8 62
- 3.
63 5
- 4.
64 0
- 3.
65 I
I 713
ES-401 System # I Name K
K 1
2 215004 Source Range Monitor 400000 Component Cooling Water 239002 SRVs 218000 ADS 215005 APRM I LPRM 239002 SRVs x
215003 IRM x
203000 RHR/LPCI: Injection Mode x
400000 Component Cooling x
Water 209001 LPCS 4
Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
K A A2 A
A G
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 x
those predictions, use procedures to 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 x
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: High/low CCW tern perature 2.2.42 - Equipment Control::
Ability to recognize system x
parameters that are entry-level conditions for Technical Specifications.
2.2.12 - Equipment Control:
x Knowledge of surveillance procedures.
A2.06 - Ability to (a) predict the impacts of the following on the A VERA GE POWER RANGE MONITOR/LOCAL POWER x
RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnomml conditions Recirculation flow channels upscale Kl.05 - Knowledge of the physical connections and/or cause-effect relationships between RELIEF/SAFETY VAL YES and the following: Plant air systems:
Plant-Specific K1.01 - Knowledge of the physical connections and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM and the followino: RPS K2.02 - Knowledge of electrical power supplies to the following:
Valves K2.01 - Knowledge of electrical power supplies to the following:
CCWpumps K3.03 - Knowledge of the effect that a loss or malfunction of the x
LOW PRESSURE CORE SPRAY SYSTEM will have on following: Emergency oenerators Imp Q#
3.7 86 3.0 87 4.6 88 4.1 89 3.5 90 3.1 I
3.9 2
2.5 3
2.9 4
2.9 5
ES-401 System #I Name K
K 1
2 211000 SLC 215005 APRM I LPRM 215004 Source Range Monitor 212000 RPS 264000 EDGs 218000 ADS 263000 DC Electrical Distribution 217000 RCIC 4
Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
K A
A2 A
A G
3 4
5 6
1 3
4 K3.02 - Knowledge of the effect that a loss or malfunction of the x
STANDBY LIQUID CONTROL SYSTEM will have on following:
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 x
interlocks which provide for the following: Sampling of overall core power in each APRM (accomplished through LPRM assignments and symmetrical rod patterns)
K4.01 - Knowledge of SOURCE RANGE MONITOR (SRM) x SYSTEM design feature(s) and/or interlocks which provide for the following: Rod withdrawal blocks KS.01 - Knowledge of the operational implications of the x
following concepts as they apply to REACTOR PROTECTION SYSTEM : Fuel thermal time constant KS.06 - Knowledge of the operational implications of the x
following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET) :
Load sequencina K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the x
AUTOMATIC DEPRESSURIZATION SYSTEM
- RHR/LPCI system pressure:
Plant-Specific K6.01 - Knowledge of the effect that a loss or malfunction of the x
following will have on the D.C.
ELECTRICAL DISTRIBUTION :
A.G. electrical distribution A 1.07 - Ability to predict and/or monitor changes in parameters associated with operating the x
REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: Suppression pool level Imp Q#
3.0 6
2.7 7
3.7 8
2.7 9
3.4 IO 3.9 11 3.2 12 3.3 13
ES-401 System # I Name K
K 1
2 205000 Shutdown Cooling 259002 Reactor Water Level Control 223002 PCIS/Nuclear Steam Supply Shutoff 262001 AC Electrical Distribution 261000 SOTS 206000 HPCI 300000 Instrument Air 262002 UPS (AC/DC) 215004 Source Range Monitor 4
Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
K A
A2 A
A G
3 4
5 6
1 3
4 A 1.09 - Ability to predict and/or monitor changes in parameters associated with operating the SHUTDOWN COOLING x
SYSTEM (RHR SHUTDOWN COOLING MODE) controls including: SDC/RHR pump/system discharge pressure A2.03 -Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b) x based on those predictions, use 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 x
SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abn cond or ops. Various process instrumentation failures A3.02 - Ability to monitor x
automatic operations of the A.C.
ELECTRICAL DISTRIBUTION includinq: Automatic bus transfer A3.02 - Ability to monitor x
automatic operations of the STANDBY GAS TREATMENT SYSTEM including: Fan start A4.13 - Ability to manually x
operate and/or monitor in the control room: Turbine reset control: BWR-2,3,4 A4.01 - Ability to manually x
operate and/or monitor in the control room: Pressure gauges 2.4.50 - Emergency Procedures I Plan: Ability to verify system x
alarm setpoints and operate controls identified in the alarm response manual.
2.4.18 - Emergency Procedures x
I Plan: Knowledge of the specific bases for EOPs.
Imp Q#
2.8 14 3.6 15 2.7 16 3.2 17 3.2 18 4.1 19 2.6 20 4.2 21 3.3 22
ES-401 System # I Name K
K 1
2 400000 Component Cooling Water 264000 EDGs 262002 UPS (AC/DC) 259002 Reactor Water Level Control KIA Category Totals:
2 2
4 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
K A
A2 A
A G
3 4
5 6
1 3
4 A2.03 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those x
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: High/low CCW temperature A3.05 - Ability to monitor automatic operations of the x
EMERGENCY GENERATORS (DIESEUJET) including: Load shedding and sequencing A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the x
UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outouts K4.14 - Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design x
feature(s) and/or interlocks which provide for the following:
Selection of various instruments to provide reactor water level input 2
3 2
2 3
3/3 3
2 212 Group Point Total:
Imp Q#
2.9 23 3.4 24 2.5 25 3.4 26 I 26/5
ES-401 System # I Name K
K 1
2 201001 CRD Hydraulic 230000 RHR/LPCI:
Torus/Pool Spray Mode 290002 Reactor Vessel Internals 290002 Reactor Vessel Internals x
233000 Fuel Pool Cooling/Cleanup x
201003 Control Rod and Drive Mechanism 215001 Traversing In-core Probe 286000 Fire Protection 215002 RBM 201002 RMCS 268000 Radwaste 5
Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K
K A
A2 A
A G
3 4
5 6
1 3
4 A2.08 - Ability to (a) predict the impacts of the following on the CRD HYDRAULIC SYSTEM ;
x and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of abnormal conditions or operations:
Inadequate svstem flow 2.2.40 - Equipment Control: Ability x
to apply technical specifications for a system.
2.1.30 - Conduct of Operations:
x Ability to locate and operate components, including local controls.
Kl.04 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR VESSEL INTERNALS and the following: HPCI: Plant-Specific K2.02 - Knowledge of electrical power supplies to the following:
RHRpumps K3.02 - Knowledge of the effect that a loss or malfunction of the x
CONTROL ROD AND DRIVE MECHANISM will have on following: Flux shaping K4.01 - Knowledge of TRAVERSING IN-CORE x
PROBE design feature(s) and/or interlocks which provide for the following: Primary containment isolation: Mark-l&ll(Not-BWR1)
K5.03 - Knowledge of the operational implications of the x
following concepts as they apply to FIRE PROTECTION SYSTEM : Effect of water spray on electrical components K6.05 - Knowledge of the effect that a loss or malfunction of the x
following will have on the ROD BLOCK MONITOR SYSTEM :
LPRM detectors: BWR-3,4,5 A 1.01 - Ability to predict and/or monitor changes in parameters x
associated with operating the REACTOR MANUAL CONTROL 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 x
those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Svstem rupture Imp.
Q 2.8 91 4.7 92 4.0 93 3.4 27 2.8 28 2.8 29 3.4 30 3.3 31 2.8 32 2.8 33 2.9 34
ES-401 System #I Name K
K 1
2 290001 Secondary CTMT 245000 Main Turbine Gen. I Aux.
201001 CRD Hydraulic 288000 Plant Ventilation KIA Category Totals:
1 1
5 Form ES-401-1 LOC27 NRC Written Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K
K A
A2 A
A G
3 4
5 6
1 3
4 A3.02 - Ability to monitor automatic operations of the x
SECONDARY CONTAINMENT including: Normal building differential pressure: Plant-Specific A4.1 O - Ability to manually x
operate and/or monitor in the control room: Hydrogen gas pressure 2.2.38 - Equipment Control:
x Knowledge of conditions and limitations in the facilitv license.
K3.05 - Knowledge of the effect that a loss or malfunction of the x
PLANT VENTILATION SYSTEMS will have on following: Reactor building pressure: Plant-Specific 2
1 1
1 1
1/1 1
1 1/2 Group Point Total:
Imp.
Q 3.5 35 2.6 36 3.6 37 3.1 38 I
1213
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
LOC27 NRC Written Exam Date:
08/17/15 Outline RO SRO-Only Category KIA#
Topic Q#
Q#
IR IR 2.1.13 Knowledge of facility requirements for 3.2 94 controllinq vital I controlled access.
Ability to use procedures to determine the 2.1.43 effects on reactivity of plant changes, such as 4.3 98 RCS temperature, secondary plant, fuel depletion, etc.
- 1.
Conduct 2.1.18 Ability to make accurate, clear and concise 3.6 66 of Operations loqs, records, status boards, and reports.
Ability to evaluate plant performance and 2.1.7 make operational judgements based on 4.4 67 operating characteristics, reactor behavior, and instrument interpretion.
Subtotal 2
2 2.2.7 Knowledge of the process for conducting 3.6 95 special or infrequent tests.
Knowledge of the process for managing 2.2.18 maintenance activities during shutdown 3.9 100 operations, such as risk assessments, work prioritization, etc.
- 2.
Equipment Knowledge of the process for conducting Control 2.2.7 special or infrequent tests.
2.9 68 (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, 2.3.5 such as fixed radiation monitors and alarms, 2.9 96 portable survey instruments, personel monitorinq equipment, etc.
- 3.
Radiation Control Knowledge of Radialogical Safety Procedures pertaining to licensed operator 2.3.13 duties, such as response to radiation monitor 3.4 70 alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 2.3.4 Knowledge of radiation exposure limits under 3.2 71 normal or emergency conditions.
Ability to use radiation monitoring systems, 2.3.5 such as fixed radiation monitors and alarms, 2.9 75 portable survey instruments, personell monitoring equipment, etc.
Subtotal 3
1 Ability to recognize abnormal indications for 2.4.4 system operating parameters which are entry-4.7 97 level conditions for emergency and abnormal operating procedures.
Knowledge of facility protection 2.4.26 requirements, including fire brigade and 3.6 99
- 4.
portable fire fiqhtinq equipment usaqe.
Emergency Procedures I Plan 2.4.3 Ability to identify post-accident 3.7 72 instrumentation.
2.4.18 Knowledge of the specific bases for EOPs.
3.3 73 2.4.37 Knowledge of the lines of authority during 3.0 74 implementation of the emergency plan.
Subtotal 3
2 Tier 3 Point Total 10 7
ES-401 Tier I Group Randomly Selected KIA Record of Rejected K/A's Form ES-401-4 Reason for Rejection
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susguehanna, LLC Date of Examination: 8/17/2015 Examination Level: RO [gl 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 K/A - 2.1.7 RO 4.4 SRO 4.7 Conduct of Operations Review Failed ST and Determine Required Action R,D (51.S0.1944.151)
C002 General K/A-2.2.12 RO 3.7 SRO 4.1 Equipment Control Blocking and Tagging R,D (OO.AD.327 4.202)
EC General K/A-2.2.41 RO 3.5 SRO 3.9 Radiation Control Emergency Plan Emergency Plan Communications S,D (OO.EP.1135.001)
EP General K/A - 2.4.39 R03.9 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 (S 3 for ROs; s 4 for SROs & RO retakes)
(N)ew or (M)odified from bank(_:: 1)
(P)revious 2 exams Cs 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 [8J Operating Test Number: U01916 Administrative Topic Type Describe activity to be performed (See Note)
Code*
Conduct of Operations Determine NRC Notification Requirements R,D (OO.AD.1032.001)
C001 General KIA-2.81.18 SRO 3.8 Conduct of Operations Review failed ST and determine required actions R,D (51.S0.1944.151)
C002 General KIA - 2.2.12 RO 3.7 SRO 4.1 Equipment Control Blocking and Tagging R,D (OO.AD.3274.201)
EC General KIA-2.2.41 RO 3.5 SRO 3.9 Radiation Control Calculate and Approve Emergency Exposure RC R,D (OO.EP.1132.185)
General KIA-2.3.4 SRO 3.7 Make EAL Classification Emergency Plan EP S,N (OO.EP.1132.180)
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 (.S 3 for ROs;.s 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (:::_ 1)
(P)revious 2 exams (.S 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 [8J SRO-I 0 SRO-U 0 Operating Test Number: U01916 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*
Safety Function
- a. Respond to Control Rod Drift In During Performance of Rod Exercise A,D,P,S 1
Test (55.0N.1998.151)
- b. Perform Quick Recovery of the Condensate System N,S 2
- c. Quarterly Turbine Valve Cycling/241000 D,S 3
- d. Core Spray System Shutdown/209001 D,S 4
- e. PCIS/SDC Restoration/223002 A,D,EN,L,S 5
- g. Restore Offgas System IAW ON-143-001 D,E,S 9
- h. APRM Gain Adjust/215005 D,S 7
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- k. Secure Non-class 1E 250 VDC Loads IAW E0-100-030 D,E,R 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
- 5_9/
- 5.8 I :5_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
- 5. 3 I
- 5.3 1:5. 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 [8] SRO-U D Operating Test Number: U01916 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*
Safety Function
- a. Respond to Control Rod Drift In During Performance of Rod Exercise A,D,P,S 1
Test (55.0N.1998.151)
- b. Perform Quick Recovery of the Condensate System N,S 2
- c. Quarterly Turbine Valve Cycling/241000 D,S 3
- d. Core Spray System Shutdown/209001 D,S 4
- e. PCIS/SDC Restoration/223002 A,D,EN,L,S 5
- g.
- h. APRM Gain Adjust/215005 D,S 7
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- k. Secure Non-class 1 E 250 VDC Loads IAW E0-100-030 D,E,R 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 /
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)
~21 ~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
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 IZI Operating Test Number: U01916 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*
Safety Function
- a.
- b. Perform Quick Recovery of the Condensate System N,S 2
- c.
- d.
- e. PCIS/SDC Restoration/223002 A,D,EN,L,S 5
- g.
- h.
In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j.
- k. Secure Non-class 1 E 250 VDC Loads IAW E0-100-030 D,E,R 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
~3 I
~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-xx Reactor Aeeroach to Run, Mode Switch in Startue 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 RBCCW Pump "A" is OOS and is not available.
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 startue.
Event Malt. No.
Event Event No.
Type*
Description 1
N/A N
Place Off Gas in Service SRO,BOP 2
N/A R
Raise Reactor Power by Withdrawing Control Rods SRO,ATC mfRD155007 c
Uncoupled Control Rod 3
mfRD155006 TS SRO,ATC mfRWMIOM I
Rod Worth Minimizer Failure 4
DEL c
Control Rod Drop mfRD155006 SRO,ATC 6
c Fuel Failure mfRR179003 SRO,BOP 7
cmfAV04_
M SDIV Vent and Drain Valves Fail to Close XV147 All
8 mfCU161007 cmfMV06_
HV144F001 cmfMV06_
HV144F004 SRO,BOP Reactor Water Cleanup Pipe Break Without Auto Isolation 9
cmfMV09_
HV144F001 cmfMV09_
HV144F004 c
Reactor Water Cleanup Isolation Valves Fail to Close SRO,BOP
- (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d)
- 1. Malfunctions after EOP entry (1-2)
- 2. Abnormal events (2-4)
- 3. Major transients (1-2)
- 4. EOPs entered/requiring substantive actions (1-2)
- 5. EOP contingencies requiring substantive actions (0-2)
- 6. Critical tasks (2-3)
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.
Scenario Actual Events Attributes 6,8,9 3
3,4 2
7 1
Control Emergency 1
Depressurization 2
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 IC-XX 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 RBCCW Pump "A" is OOS and is not available.
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 1
N/A R
Lower Reactor Power by Inserting Control Rods SRO,ATC 2
N/A N
Transfer Auxiliary Susses SRO,BOP cmfTD04_PD I
Narrow Range Instrument Failure 3
TC321N004 TS SRO,BOP mfDS003007 c
Loss of Auxiliary Bus 118 4
cmfBR03 TS 1A10204 All 5
c Loss of Vacuum mfMC143001 ALL mfRP158007 M
ATWS due to RPS and ARI Failing to Actuate 6
cmfRL01 -
63X114 All 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
Target Quantitative Attributes (Per Scenario; See Section D.5.d)
Scenario Actual 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
- 4. EOPs entered/requiring substantive actions (1-2)
RPV Control 1
- 5. EOP contingencies requiring substantive actions (0-2)
Level/Power Control 1
- 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.:
4 Op-Test No.:
U01916 Examiners:
Operators:
Initial Conditions Unit 1approximate!~11% power during startup, BOL Turnover Continue power ascension by withdrawing control rods; complete the next four control rod movement steps in the startup sequence.
Then, place Feedwater pump 1A in the flow control mode per OP-145-001 section 2.10. Start at step 2.10.8.
Event Malf.
Event Event No.
No.
Type*
Description 1
N/A R
Raise Reactor Power with Control Rods SRO,ATC 2
N/A N
Place First Feedwater Pump in Flow Control Mode SRO,ATC mfNM17800 I
APRM Fails Upscale 3
cmfEB01_1 c
Electrical Fault on ESS Bus 1A (1A201)
A201 ALL mfHP15200 c
Inadvertent HPCI Initiation 5
mfMS18300 M
Main Steam Leak into Turbine Building 8
ALL cmfAV06_H V141F028D I
MSIVs Fail to Automatically Close 7
cmfAV06_H SRO,BOP V141F022D mfDS00300 Loss of Offsite Power 8
7 M
mfDS00300 ALL 8
mfDG02400 9
SC c
EOG C Fails to Start, EDGs B and D Fail to Auto-Start mfDG02400 SRO,BOP 1B(D)
10 mfRC15000 1
diHS15012 CB c
ALL HPCI and RCIC Fail to Auto-Initiate and Initiation Pushbuttons Fail to ARM
- (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)
- 2. Abnormal events (2-4)
- 3. Major transients (1-2)
- 4. EOPs entered/requiring substantive actions (1-2)
- 5. EOP contingencies requiring substantive actions (0-2)
- 6. Critical tasks (2-3)
CT-1 Manually isolate a Main Steam Line break.
CT-2 Restore power to an ESS Bus by manually starting an emergency diesel generator.
7,9,10 3
4,5 2
6,8 2
RPV Control 1
0 2