ML12311A098
| ML12311A098 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/14/2012 |
| From: | Todd Fish Operations Branch I |
| To: | Entergy Nuclear Vermont Yankee |
| Jackson D | |
| Shared Package | |
| ML120230228 | List: |
| References | |
| ES-301-2, ES-401-1, ES-401-3, ES-401-4, ES-D-1, TAC U01851 | |
| Download: ML12311A098 (22) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 II Date of Exam: September 24,2012 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G*
Total 1 2 3 4
5 6
1 2 3
4 Total
- 1.
1 5
4 2
4 3
2 20 6
1 7
Emergency &
Abnormal Plant 2
1 2
0 N/A 1
1 N/A 2
7 2
1 3
Evolutions Tier Totals 6
6 2
5 4
4 27 8
2 10 1
3 5
3 2
2 1
2 2
3 2
1 26 1
4 5
- 2.
Plant 2
1 0
0 1
2 2
0 0
3 2
1 12 0
3 0
3 Systems Tier Totals 4
5 3
3 4
3 2
2 6
4 2
38 4
4 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
3 2
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 (Le., 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/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 KIA 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 KlAs 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 KIA categories.
7.*
The generic (G) KlAs 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 D.1.b of ES-401 for the applicable KlAs.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; 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 KlAs that are linked to 10 CFR 55.43.
ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)
E/APE # I Name / Safety Function 295005 Main Turbine Generator Trip / 3 295030 Low Suppression Pool Wtr Lvi/ 5 295028 High Drywell Temperature /5 295026 Suppression Pool High Water Temp. 15 295024 High Drywell Pressure I 5 295031 Reactor Low Water Level 12 295003 Partial or Complete Loss of AC / 6 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip /3 295006 SCRAM / 1 295016 Control Room Abandonment 17 295018 Partial or Total Loss of CCW / 8 295019 Partial or Total Loss of Ins!. Air /8 295021 Loss of Shutdown Cooling / 4 295023 Refueling Ace / 8 K
K K A 1
2 3
1 X
X X
X X
X X
X A
G KIA Topic(s) 2 X
Ability to detennine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP:
AA2.02 Turbine vibration X
Ability to detennine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: EA2.02 Suppression pool temperature X
Ability to detennine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE:
EA2.05 Torus/suppression chamber air space pressure: Plant-Specific X
2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: EA2.04 Suppression Chamber Pressure X
Ability to detennine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:
EA2.04 Adequate Core Cooling X
Ability to detennine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: AA2.04 System lineups X
Ability to detennine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: AA2.06 Nuclear boiler instrumentation Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: AA1.04 D.C. electrical distribution system Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: AK1.05 Loss of breaker protection Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP: AK1.01 Pressure effects on reactor power Knowledge of the interrelations between SCRAM and the following: AK2.04 Turbine trip logic: Plant-Specific Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT:
AA1.06 Reactor Water Level Knowiedge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following: AK2.02 Plant operations Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: AK2.14 Plant Air Systems Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING: AK3.02 Feeding and bleeding reactor vessel IX 2.4.6 Knowledge of EOP mitigation strategies
~~
IR 2.7 3.9 3.8 4.6 3.9 4.8 3.7 3.2 3.6 3.3 4.0 3.6 4.0 3.4 3.2 3.3 3.7 on **
76 C
77 T
78 C
79 T
80 C
~
T 82 C
1 C 2T 3C 4T 5C 6T 7C 8T 9C 10 T
295024 High Drywell Pressure I 5 X
Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE: EK1.01 Drywell integrity:
4.1 11 C
Plant-Specific 295025 High Reactor Pressure I 3 X
Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE:
EA2.04 Suppression pool level 3.9 12 T
295026 Suppression Pool High Water Temp./5 X
Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: EK1.01 3.5 13 C
Pump NPSH 295027 High Containment Temperature I 5 Suppressed, no Mklll containment at VY.
N/A 295028 High Drywell Temperature I 5 X
Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE: EK3.04 Increased drywell cooling 3.6 14 T
295030 Low Suppression Pool Wtr LviI 5 X
Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: EK1.03 3.8 15 C
Heat Capacity Knowledge of the interrelations between REACTOR 295031 Reactor Low Water Levell 2 X
LOW WATER LEVEL and the following: EK2.05 4.2 16 Low pressure coolant injection (RHR)
T 295037 SCRAM Condition Present X
Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND 4.5 17 and Reactor Power Above APRM REACTOR POWER ABOVE APRM DOWNSCALE C
Downscale or Unknown 11 OR UNKNOWN: EA1.05 SBLC 295038 High Off-site Release Rate I 9 X
2.4.11 Knowledge of abnormal condition 4.0 18 procedures.
T 600000 Plant Fire On Site I 8 X
Ability to operate and I or monitor the following as they apply to PLANT FIRE ON SITE: AA1.08 2.6 19C Firefighting equipment used on each class of fire Ability to determine and/or interpret the following as 700000 Generator Voltage and Electric Grid Disturbances I 6 X
they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: AA2.09 3.9 20 T
Operational status of emergency diesel generators KIA Category Totals:
5 4
2 4
2 3
Group Point Total:
201 I
I 7
6 1
I ES-401 3
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)
E/APE # I Name I Safety Function K
K K A A G
KIA Topic(s)
IR 1
2 3
1 2
Ability to determine and lor interpret the following as 500000 High CTMT Hydrogen Conc.1 5 X
3.5 83 they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: EA2.02 Oxygen T
monitorinq system availability Ability to determine and/or interpret the following as 295002 Loss of Main Condenser Vac I 3 X
3.1 84 they apply to LOSS OF MAIN CONDENSER VACUUM: AA2.01 Condenser vacuum/Absolute C
pressure 2.4.50 Ability to verify system alarm setpoints and 295029 High Suppression Pool Wtr LviI 5 X
4.0 85 operate controls identified in the alarm response manual.
T Knowledge of the interrelations between LOSS OF 295002 Loss of Main Condenser Vac I 3 X
2.6 21 MAIN CONDENSER VACUUM and the following:
AK2.11 Seal steam: Plant-Specific C
Knowledge of the operational implications of the 295007 High Reactor Pressure I 3 X
2.9 22 following concepts as they apply to HIGH REACTOR PRESSURE: AK1.01 Pump Shutoff Head T
295011 High Containment Temp 15 Suppressed, no Mklll containment at VY.
N/A 2.4.21 Knowledge of the parameters and logic used to 295013 High Suppression Pool Temp./5 X
4.0 23 assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant C
system integrity, containment conditions, radioactivity release control, etc.
Ability to operate and/or monitor the following as they 295029 High Suppression Pool Wtr LviI 5 X
2.9 24 apply to HIGH SUPPRESSION POOL WATER LEVEL: EA1.03 RHRlLPCI T
Ability to determine and/or interpret the following as 295035 Secondary Containment High X
2.8 25 they apply to SECONDARY CONTAINMENT HIGH Differential Pressure I 5 C
DIFFERENTIAL PRESSURE: EA2.02 tOff-site release rate: Plant-Specific 2.1.7 Ability to evaluate plant performance and make 295036 Secondary Containment High X
4.4 26 operational judgments based on operating Sump/Area Water Levell 5 T
characteristics, reactor behavior, and instrument interpretation.
Knowledge of the interrelations between HIGH 500000 High CTMT Hydrogen Conc. I 5 X
3.3 27 CONTAINMENT HYDROGEN CONCENTRATIONS the following: EK2.08 Containment atmosphere control C
system.
KIA Category Point Totals:
1 2
0 1 1 2
Group Point Total:
7/3 I
I 2
1
ES-401 4
Form ES-401-1 ES-401 BWR Examination Outline II Plant Svstems - Tier 2/Group 1 (RO I SRO)
System # / Name K
K K
K K
K A A
A A
G KIA Topic(s) 1 2
3 4
5 6
1 2
3 4 261000 SGTS X
2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
400000 Component Cooling
~to verify that the alarms are
~-
Water th the plant conditions.
T 2150031RM X
Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on 3.8 88 C
those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.04 UP scale or down scale trips 263000 DC Electrical X
2.4.41 Knowledge of emergency action level thresholds and classifications.
4.6 89 Distribution T
209001 LPCS X
2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or extemal agencies, 4.1 90 C
such as the State, the NRC, or the transmission system operator.
263000 DC Electrical Distribution X
Ability to (a) predict the impacts of the following on the D.C. ELECTRICAL DISTRIBUTION; and (b) based on those 2.8 28C predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.01 Grounds 400000 Component Cooling Water X
Knowledge of the physical connections and I or cause-effect relationships between CCWS and the following: K1.03 2.7 29 T
Radiation monitoring systems 218000 ADS X
Knowledge of the effect that a loss or malfunction of the AUTOMATIC 4.5 30 DEPRESSURIZATION SYSTEM will have on C
following: K3.02 Ability to rapidly depressurize the reactor 215005 APRM I LPRM X
Ability to monitor automatic operations of the AVERAGE POWER RANGE 3.3 1
MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including: A3.04 Annunciator and alarm signals 203000 RHR/LPCI: Injection Mode X
2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator 4.2 32 C
actions and directives affect plant and system conditions.
203000 RHR/LPCI: Injection Mode X
Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: INJECTION MODE (PLANT 3.8 33 T
SPECIFIC). K6.06 Suppression pool
205000 Shutdown Cooling 206000 HPCI 207000 Isolation (Emergency)
Condenser 209001 LPCS 209002 HPCS 211000 SLC 212000 RPS 2150031RM 215004 Source Range Monitor 215005 APRM / LPRM 217000 RCIC 218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution X
Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING 2.9 34 C
MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.10 Valve operation X
Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION 4.2 35 T
SYSTEM controls including: A1.02 Reactor pressure: BWR-2,3,4 Suppressed, system does not exist at VY.
N/A X
Ability to monitor automatic operations of the LOW PRESSURE CORE SPRAY SYSTEM 3.8 36 includinq: A3.02 Pump start C
Suppressed, system does not exist at VY.
N/A X
Ability to manually operate and/or monitor in 3.6 37 the control room: A4.07 Liqhts and alarms T
X Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM: K5.02 3.3 38 C
Specific loqic arranqements X
Knowledge of the effect that a loss or malfunction of the INTERMEDIATE RANGE 3.6 39 MONITOR (IRM) SYSTEM will have on T
followinq: K3.02 Reactor manual control X
Ability to manually operate and/or monitor in the control room: A4.0G Alarms and lights 3.2 40 C
X Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or 4.2 41 T
interlocks which provide for the following:
K4.02 Reactor SCRAM signals X
Knowledge of the operational implications of the following concepts as they apply to REACTOR CORE ISOLATION COOLING 2.7 42 C
SYSTEM (RCIC) : K5.0G Turbine Operation X
Knowledge of electrical power supplies to the following: K2.01 ADS logic 3.1 43 T
X Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT 3.7 44 ISOLATION SYSTEM/NUCLEAR STEAM C
SUPPLY SHUT-OFF will have on following:
K3.01 Reactor water level X
Knowledge of the physical connections and/or cause effect relationships between RELIEF/SAFETY VALVES and the following:
3.5 45 T
K1.07 Suppression Pool X
Knowledge of electrical power supplies to the following: K2.02 Feedwater coolant injection (FWCI) initiation loqic: FWCI/HPCI 3.5 46 C
X Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM 2.8 47 T
controls including: A1.07 SBGTS train temperature X
Knowledge of electrical power supplies to the following: Off-site sources of power K2.01 3.3 48 C
262002 UPS (AC/DC) 263000 DC Electrical Distribution X
X Knowledge of the physical connections and/or cause effect relationships between UNINTERRUPTABLE POWER SUPPLY (A.C.lD.C.) and the following: K1.16 MSIVs:
Plant-Specific Knowledge of electrical power supplies to the following: K2.01 Major D.C. loads 3.1 3.1 49 T
50 C
264000 EDGs X
Knowledge of EMERGENCY GENERATORS (DIESEUJET) design feature(s) and/or interlocks which provide for the following:
K4.05 Load shedding & sequencing 3.2 51 T
300000 Instrument Air X
Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including: A3.02 Air temperature 2.9 52 C
400000 Component Cooling Water X
Knowledge of electrical power supplies to the following: K2.02 CCW valves 2.9 53 T
KIA Category Point Totals:
3 5
3 2 2
1 2
2 I
1 3
2 1
I 4
Group Point Total:
~6/
ES-401 5
Form ES-401-1 I ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
KIA Topic(s)
IR 239001 Main and Reheat Steam X
Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on 3.9 91 T
those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.07 Main steam area high temperature or differential temperature high 214000 RPIS X
Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION SYSTEM; and (b) 3.9 92 C
based on those predictions, use procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations:
A2.03 Overtravel/in-out 290003 Control Room HVAC X
Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC ; and (b) based on those 3.3 93 T
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.04 Initiation/failure of fire protection system 201002 RMCS X
Knowledge of REACTOR MANUAL CONTROL SYSTEM design feature(s) and/or interlocks which provide for the 3.3 54 C
following: K4.06 "Emergency In" rod insertion.
201004 RSCS Suppressed, system does not exist at N/A VY.
201005 RCIS Suppressed, system does not exist at N/A VY.
202001 Recirculation X
Ability to monitor automatic operations of the RECIRCULATION SYSTEM including: A3.05 Pump speed: Plant 2.9 55 T
Specific 215001 Traversing In-core Probe X
Ability to manually operate and/or monitor in the control room: A4.03 Isolation valves: Mark-I&II(Not-BWR1) 3.0 56 C
216000 Nuclear Boiler Ins!.
X Knowledge of the operational implications of the following concepts as they apply to NUCLEAR BOILER 3.5 57 T
INSTRUMENTATION: K5.13 Reference leg flashing: Design-Specific 230000 RHRlLPCI: Torus/Pool Spray Mode X
Knowledge of the effect that a loss or malfunction of the following will have on the RHRlLPCI: TORUS/SUPPRESSION 3.3 58 C
POOL SPRAY MODE: K6.01 A.C.
Electrical 239001 Main and Reheat Steam X
Knowledge of the operational implications of the following concepts as they apply to MAIN AND REHEAT 2.8 59 T
STEAM SYSTEM: K5.05 Flow indication.
239003 MSIV Leakage Control Suppressed, system does not exist at N/A VY.
245000 Main Turbine Gen. / Aux.
X Ability to monitor automatic operations of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS including: A3.01 3.6 60 C
Turbine trip 256000 Reactor Condensate X
Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR CONDENSATE 2.6 61 T
SYSTEM: K6.09 Offaas system 268000 Radwaste X
Knowledge of the operational implications of the following concepts as they apply to RADWASTE : K1.06 2.9 62 C
Drywell Floor Drains 288000 Plant Ventilation X
Ability to monitor automatic operations of the PLANT VENTILATION SYSTEMS including: Isolation/initiation signals 3.8 63 T
A3.01 290003 Control Room HVAC X
Ability to manually operate and/or monitor in the control room: A4.03 2.8 64 Reposition dampers C
226001 RHRlLPCI: CTMT Spray Mode X
2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
4.5 65 T
KIA Category Point Totals:
1 0
0 1
2 2
0 0
3 2
1 Group Point Total:
12/3
/
/
3 0
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 II
. 'ty: Vermont Yankee Date of Exam:
September 24,2012 Category KIA #
Topic RO SRO-Only IR IR
- 1.
Conduct of Operations 2.1.36 2.1.15 2.1.4 Knowledge of procedures and limitations involved in core alterations.
Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, operations memos, etc.
Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.
3.0 2.7 66C 67T 3.8 94C 2.1.36 Knowledge of procedures and limitations involved in core alterations.
4.1 95T Subtotal 2.2.14 Knowledge of the process for controlling equipment configuration or status.
3.9 2
68 T 2
- 2.
Equipment Control 2.2.7 2.2.21 Knowledge of the process for conducting special or infrequent tests.
Knowledge of pre-and post-maintenance operability requirements.
2.9 2.9 69C 70T 2.2.20 2.2.5 Knowledge of the process for managing troubleshooting activities.
Knowledge of the process for making design or operating chanqes to the facility.
3.8 3.2 96T 97 C
- 3.
Radiation Control Subtotal 2.3.4 2.3.11 2.3.13 Knowledge of radiation exposure limits under normal or emergency conditions.
Ability to control radiation releases.
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.
3.2 3.8 3
71 T 72 C 3.8 2
98 T Subtotal 2
1
- 4.
Emergency Procedures I Plan 2.4.25 2.4.22 2.4.9 2.4.38 Knowledge of fire protection procedures.
Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.
Knowledge of low power/shutdown implications in accident (e.g.,
loss of coolant accident or loss of residual heat removal) mitigation strategies.
Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.
3.3 3.6 3.8 73 C 74 T 75 C 4.4 99T 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.
4.5 100 C Subtotal 3
2 Tier 3 Point Total 10 7
ES-401 Tier /
Randomly Group Selected KIA T1/G1 295001 G2.4.45 rejected Generic 2.3.14 Generic 2.1.36 T2/G2 K6.05 T2/G2 268000 K5.02 Generic 2.1.36 T1G1 295031 /EA2. 03 T2/G2 245000 A2.04 T2/G2 290002 T1/G2 295007 AK1.02 T1/G1 295024 EA2.09 T2/G1 239002 K1.03 T2/G1 24600 K4.04 T1/G1 295023 2.4.3 Record of Rejected K/As Form ES-401-4 Reason for Rejection Rejected due to oversampling; KIA tested repeatedly in scenarios.
Rejected due to oversampling; similar test item used in Admin
..IPM.
Rejected due to unsuitable testable material (2.1.20 selected in place of 2.1.36)
Rejected due to oversampling; similar KIA used in previous written questions (203000 # 33)
Rejected due to unsuitable test material (radiation hazards and ALARA Rejected due to unsuitable testable material (2.1.36 selected in place)
Rejected due to unable to write question. Replaced with EA2.04 Changed to A3.01 due to unsuitable test material Changed 29002 (RX Vessel Internals) to 226001 RHRlLPCI CTMT Spray Mode -> unsuitable test material Changed to AK1.01 -> unsuitable test material Changed to EA2.04 -> unsuitable test material Changed to K1.04 -> duplicate KA selected (057)
Changed to K4.05 -> unable to find operationally oriented exam material for selected KA Changed to 2.4.6 -> unable to find operationally oriented material.
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Vermont Yankee Examination Level: RoxD Administrative Topic (see Note)
RO A-1 Conduct of Operations RO A-2 Conduct of Operations RO A-3 Equipment Control Radiation Control RO A-4 Emergency Procedures/Plan SRO D Type Code*
M,R R,D M,R N/A R,N Date of Examination: 9/24/12 Operating Test Number:
1 Describe activity to be performed 2.1.5 Evaluate Overtime Request with Respect to Work Hour Limits 2.1.7 Perform Reactor Coolant Temperature Checks 2..2.15 Isolate leaking Core Spray Weld NIA 2.4.21 Determination of Offgas Release Rate NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- 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 Administrative Topics Outline Form ES-301-1 Facility:
Vermont Yankee Examination Level: RO D Administrative Topic (see Note)
SRO A-1 Conduct of Operations SRO A-2 Conduct of Operations SRO A-3 Equipment Control SRO A-4 Radiation Control SRO A-5 Emergency Procedures/Plan SRO xD Type Code*
N,R M,R M,R M,R M,R Date of Examination: 9/24/12 Operating Test Number:
1 Describe activity to be performed Evaluate Reactor Water Chemistry Results Evaluate Control Room Logs and Determine Actions Isolate leaking Core Spray weld and determine technical specification required actions Review and Approve Emergency Plan Allowed Radiation Exposure Determine Protective Action Recommendations and Complete Event Notification Form NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (;::: 1)
(P)revious 2 exams (~ 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Vermont Yankee Date of Examination: 9/24/2012 Exam Level: RO xD SRO-I D SRO-U D Operating Test Number:
1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title 5-1 Recirculation System/Recirculation Flow Control System Startup the Idle Recirc Pump With the Other Pump Running 5-2 RHR/LPCI Mode (Alternate Path)
SIU Torus Cooling During Normal Operation (RHR Pump 'A' Seal Leakage) 5-3 Reactor PressurelTurbine Regulating System (Alternate Path)
Normal Reactor Ops EPR Performance Test (Failure results in placing MPR in seNice) 5-4 Core Spray Place 'B' Core Spray in Normal Standby Alignment 5-5 Primary Containment Isolation System/NSSSF Defeating HPCI Group VI Isolation Interlocks for Alternate RPV Depressurization 5-6 AC Electrical Distribution System Reactor @ 25% power, Transfer Station Loads to Aux. Transformer 5-7 Reactor Protection System RPS Bus "A" Power Supply Swap 5-8 Standby Gas Treatment (Alternate Path)
Manually Initiate SBGT Train 'A'-(Failure of Fan 'A' to Start)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 Component Cooling/Instrument Air/Fire Protection Transfer of RBCCW Heat Exchangers from 'A' to 'B' P-2 Emergency Diesel Generators (Alternate Path)
Alternate Shutdown Alt. 4 EDG Starts Fails to Load Type Code*
Safety Function A,M,S 1 (Reactivity Control)
A,M,S,EN 2 (Reactor Water Inventory Control)
A,M,S 3 (Reactor Pressure Control)
L,N,S,EN 4 (Heat Removal From the Core)
E,L,N,S 5 (Containment Integrity)
L,D,S 6 (Electrical)
D,EN,S 7
(Instrumentation)
A,N,S,EN 9 (Radioactivity Release)
N,R 8 (Plant Service Systems)
A,D,E 6 (Electrical)
P-3 RCIC L,D,EN,E 4 (Heat Removal Reactor Scram with subsequent Control Room evacuation.
From the Core)
Inject RCIC from Alternate Shutdown Panel All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
"Type Codes Criteria for RO / SRO-II SRO-U (A}lternate path 4-6 14-6/2-3 (C}ontrol room (D)irectfrom bank
- 9/
- ;;;8/s4 (E}mergency or abnormal in-plant 2'1/2'1/2'1 (EN)gineered safety feature 1 2'1 (control room system)
(L)ow-Power 1Shutdown 2'1/2'1/2'1 (N)ew or (M)odified from bank including 1(A) 2'2/2'2/2'1 (P)revious 2 exams
- 31
- ;;; 3/
- s; 2 (randomly selected)
(R)CA 2'1/2'1/2'1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Vermont Yankee Date of Examination: 9/24/2012 Exam Level: RO 0 5RO-1 xD SRO-U 0 Operating Test Number:
1 Control Room Systems@ (8 for RO); (7 for 5RO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function 5-1 Recirculation System/Recirculation Flow Control System A,M,S 1 (Reactivity Startup the Idle Recirc Pump With the Other Pump Running Control) 5-2 RHR/LPCI Mode (Alternate Path)
A,M,S,EN 2 (Reactor Water S/U Torus Cooling During Normal Operation (RHR Pump W Seal Leakage)
Inventory Control) 5-3 Reactor PressurelTurbine Regulating System (Alternate Path)
A,M,S 3 (Reactor Normal Reactor Ops EPR Performance Test (Failure results in placing MPR in service) 5-4 Core Spray Place 'B' Core Spray in Normal Standby Alignment 5-5 Primary Containment Isolation System/NSSSF Defeating HPCI Group VI Isolation Interlocks for Alternate RPV Depressurization 5-7 Reactor Protection System RPS Bus "A" Power Supply Swap 5-8 Standby Gas Treatment (Alternate Path)
Manually Initiate SBGT Train ~'-(Failure of Fan 'A' to Start)
~ nt Systems@ (3 for RO); (3 for 5RO-I); (3 or 2 for SRO-U)
P-1 Component Cooling/Instrument Air/Fire Protection Transfer of RBCCW Heat Exchangers from ~' to 'B' P-2 Emergency Diesel Generators (Alternate Path)
Alternate Shutdown Aft. 4 EDG Starts Fails to Load P-3 RCIC Reactor Scram with subsequent Control Room evacuation.
Inject RCIC from Alternate Shutdown Panel Pressure Control)
L,N,S,EN 4 (Heat Removal From the Core)
E,L,N,S 5 (Containment Integrity)
D,EN,S 7
(Instrumentation)
A,N,S,EN 9 (Radioactivity Release)
N,R 8 (Plant Service Systems)
A,D,E 6 (Electrical)
L,D,EN,E 4 (Heat Removal From the Core)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1Shutdown (N)ew or {M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator Criteria for RO f SRO-I f SRO-U 4-6 f 4-6 12-3
- 9/
- S:8/:S:4
- 1/;
- ;
- 1/;:;:1 f ;?:1 (control room system)
- ?
- 1/;?:1/;?:1
- 2/;
- ;
- 2/;:;:1
- s: 31::; 3/:S: 2 (randomly selected)
- 1 1;
- ;
- 1 I;?: 1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Vermont Yankee Date of Examination: 9/24/2012 Exam Level: RO D SRO-I D SRO-U xD Operating Test Number:
1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title S-2 RHRlLPCI Mode (Alternate Path)
S/U Torus Cooling During Normal Operation (RHR Pump ~'Seal Leakage)
S-5 Primary Containment Isolation System/NSSSF Defeating HPCf Group VI Isolation Interlocks for Alternate RPV Depressurization S-8 Standby Gas Treatment (Alternate Path)
Manually Initiate SBG T Train ~'-(Failure of Fan ~'to Start)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 Component Cooling/Instrument Air/Fire Protection Transfer of RBCCW Heat Exchangers from ~'to 'B' P-2 Emergency Diesel Generators (Alternate Path)
Alternate Shutdown Att. 4 EDG Starts Fails to Load Type Code*
Safety Function A,M,S,EN 2 (Reactor Water Inventory Control)
E,L,N,S 5 (Containment Integrity)
A,N,S,EN 9 (Radioactivity Release)
N,R 8 (Plant Service Systems)
A,D,E 6 (Electrical)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes (A)ltemate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)
{P)revious 2 exams (R}CA
{S}imulator Criteria for RO 1SRO-II SRO-U 4-6 1 4-6/2-3
$9/$8/$04
~1/;:::1/;:::1
- I - 1 ~1 (control room system)
- 1/;
- ::1/;:::1
- 2/;
- ::2/;:::1
$ 31 $ 31 $ 2 (randomly selected)
- 1/;
- ::1/;:::1
Appendix D Scenario Outline Form ES-D-1 Facility:
Vermont Yankee Scenario No.:._1__ Op-Test No.: VY NRC 2012 Examiners:
Operators:
SRO ATC BOP Initial Conditions: 100% Reactor Power
-Perform monthly TBCCW/RBCCW pump swaps lAW RP 4183 and OP 2182.
Event Malt.
Event Event No.
No.
Type*
Description 1
N/A N -BOP MonthlyTBCCW/RBCCW pump swaps lAW OP 0150, OP2182, and RP 4182 2
AD09A TS-CRS Electrical short in SRV-71A (TS Entry) 3 mfSW01 C-RO Respond to a trip of the 'A' RBCCW pump B
mfSW23 A
4 rfHP10 I-BOP HPCI inverter failure (TS Entry)
TS-CRS 5
CD01 C-RO
'B' Condensate pump trips and failure of 40% auto recirc runback.
R-RO 6
mfRD15 C-RO CRD FCV fails in Auto 7
ED17 M-AII Loss of normal power (LNP), small break LOCA, RCIC fails in auto control RR01 RC02 8
C-BOP RHR-39A(B) fails to open RC02 C-RO RCIC Turbine trips 9
RR01A M-AII Medium break LOCA RC01 10 mfRH07A C-BOP Low pressure systems fail to auto inject (all injection valves fail to auto IB open) mfCS03A IB (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility:
VY Scenario No.:
4 Op-Test No.:
Examiners:
Operators:
SRO RO BOP Initial Conditions:
Plant operating normally at 90% power "An RHR in suppression pool cooling mode
- 2 Circulating Pump to be returned to service this shift.
Turnover: Secure RHR sUQQression Qool cooling with #2 Circulating PumQ to be returned to service this shift.
Event Malt.
Event Event No.
No.
Type*
Description N/A N/A N-BOP Secure suppression pool cooling lineup 1
mfRH01 C-BOP Trip of 'A' RHR pump (TS Entry)
A CRS-TS 2
CRS-TS Loss of 'B' EDG (TS Entry) 3 EG05A C-BOP Loss of Stator Cooling
&EG12B 4
SPE C-BOP Trip of 'B' Steam Packing Exhaust Blower override and alarm 5
MC_08 R-RO
'B' Recirc pump vibration and Trip C-RO mfRR05 B
6 mfRR11 1-RO
'A' Recirc pump controller fails downscale, power oscillations, RPS A
failure 7
RD 12A M -ALL Failure to Scram, Hydraulic ATWS
&-B 8
SL 01B C-RO SLC Pump Failures 9
RD11A 1-RO CRD Flow Controller Failure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: Vermont Yankee Scenario No.: ~
Op-Test No.: VY NRC 2012 Examiners:
Operators:
SRO RO BOP Initial Conditions: -90% RTP; Summer Lineup Turnover: -None Event Malf.
Event Event No.
No.
Type*
Description 1
FW28C I-All Steam Flow transmitter failure 2
RC05 C-BOP Inadvertent isolation of RCIC with failure of one isolation valve to auto close TS-CRS 3
MC01A C-BOP/
Trip of the 'A' Circ Water pump RO R-RO 4
mfRD05 C-AII Control rod drift out 3023 TS-CRS 5
HP09 M-AII Unisolable leak in HPCI steam piping, RB area approaching max safe operating rad level 6
DG08A C-BOP Failure of 'A' EDG to auto start 7
RP17 C-BOP PCIS Group III failure to auto close ED21 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1