ML14059A542
| ML14059A542 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/14/2014 |
| From: | Mcneil D Operations Branch III |
| To: | Stewart B Entergy Nuclear Vermont Yankee |
| Jackson D | |
| Shared Package | |
| ML13204A095 | List: |
| References | |
| TAC U01897 | |
| Download: ML14059A542 (12) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 Facility: Vermont Yankee U1 Date of Exam: 02/14/2014 RO K/A 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 4 3 5 3 2 4 21 4 2 6 Emergency &
Abnormal Plant 2 1 1 1 N/A 1 1 N/A 1 6 1 3 4 Evolutions 5 4 6 4 3 5 27 5 5 10 Tier Totals 1 3 2 2 3 2 2 3 2 3 3 1 26 3 2 5 2.
Plant 2 1 1 1 1 2 1 1 1 1 1 1 12 0 2 1 3 Systems 3 4 4 4 38 5 Tier Totals 4 3 3 4 4 3 4 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 3 2 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A 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 K/A statements.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR ?#
1 2 3 1 2 AA1.07 - Ability to operate and/or monitor the following as they apply to PARTIAL OR 295001 Partial or Complete Loss of Forced COMPLETE LOSS OF FORCED CORE FLOW 3.1 50 R
Core Flow Circulation / 1 & 4 CIRCULATION : Nuclear boiler instrumentation system AK1.05 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL 295003 Partial or Complete Loss of AC / 6 R 2.6 40 OR COMPLETE LOSS OF A.C. POWER : Failsafe component design 2.1.27 - Conduct of Operations: Knowledge of 295004 Partial or Total Loss of DC Pwr / 6 R system purpose and / or function. 3.9 54 AK3.04 - Knowledge of the reasons for the following responses as they apply to MAIN 295005 Main Turbine Generator Trip / 3 R 3.2 52 TURBINE GENERATOR TRIP : Main Generator Trip AK3.01 - Knowledge of the reasons for the 295006 SCRAM / 1 R following responses as they apply to SCRAM : 3.8 45 Reactor water level response AK3.02 - Knowledge of the reasons for the 295016 Control Room Abandonment / 7 R following responses as they apply to CONTROL 3.7 47 ROOM ABANDONMENT : Turbine trip AA1.02 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING 3.3 48 WATER : System loads 295018 Partial or Total Loss of CCW / 8 R S AA2.05 - Ability to determine and/or interpret the 2.9 77 following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : System pressure AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR 295019 Partial or Total Loss of Inst. Air / 8 R 3.5 53 COMPLETE LOSS OF INSTRUMENT AIR :
Instrument air system pressure AK1.01 - Knowledge of the operational implications 295021 Loss of Shutdown Cooling / 4 R of the following concepts as they apply to LOSS 3.6 39 OF SHUTDOWN COOLING : Decay heat 2.4.45 - Emergency Procedures / Plan: Ability to prioritize and interpret the significance of each 4.1 58 annunciator or alarm 295023 Refueling Acc / 8 S R AA2.03 - Ability to determine and/or interpret the following as they apply to REFUELING 3.8 76 ACCIDENTS : Airborne contamination levels EK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE : Drywell integrity: Plant- 4.1 57 Specific 2.4.34 - Emergency Procedures / Plan: Knowledge R of RO tasks performed outside the main control 295024 High Drywell Pressure / 5 R / room during an emergency and the resultant 4.2 64 S operational effects.
2.4.4 - Emergency Procedures / Plan: Ability to recognize abnormal indications for system operating parameters that are entry-level 4.7 79 conditions for emergency and abnormal operating procedures.
EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH 295025 High Reactor Pressure / 3 R 3.9 43 REACTOR PRESSURE : Recirculation pump trip:
Plant-Specific
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR ?#
1 2 3 1 2 EK1.02 - Knowledge of the operational implications 295026 Suppression Pool High Water of the following concepts as they apply to R 3.5 41 Temp. / 5 SUPPRESSION POOL HIGH WATER TEMPERATURE : Steam condensation EK3.01 - Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE : Emergency 3.6 46 295028 High Drywell Temperature / 5 R S depressurization 2.4.31 - Emergency Procedures / Plan: Knowledge 4.1 81 of annunciator alarms, indications, or response procedures.
EA2.02 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION 295030 Low Suppression Pool Wtr Lvl / 5 R 3.9 51 POOL WATER LEVEL : Suppression pool temperature EA1.13 - Ability to operate and/or monitor the 295031 Reactor Low Water Level / 2 R following as they apply to REACTOR LOW 4.3 49 WATER LEVEL : Reactor water level control EK2.04 - Knowledge of the interrelations between SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR 295037 SCRAM Condition Present UNKNOWN and the following: SBLC system 4.4 42 and Reactor Power Above APRM R S EA2.01 - Ability to determine and/or interpret the Downscale or Unknown / 1 following as they apply to SCRAM CONDITION 4.3 82 PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Reactor power 2.1.30 - Conduct of Operations: Ability to locate 295038 High Off-site Release Rate / 9 R and operate components, including local controls. 4.4 55 AK2.04 - Knowledge of the interrelations between PLANT FIRE ON SITE and the following:
2.5 56 Breakers, relays, and disconnects 600000 Plant Fire On Site / 8 R S AA2.03 - Ability to determine and interpret the 3.2 78 following as they apply to PLANT FIRE ON SITE:
Fire alarm AK2.07 - Knowledge of the interrelations between 700000 Generator Voltage and Electric Grid GENERATOR VOLTAGE AND ELECTRIC GRID R 3.6 44 Disturbances / 6 DISTURBANCES and the following:
Turbine/generator control.
K/A Category Totals: 4 3 5 3 2 4 Group Point Total: 21/
/ /
4 2 6
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR ?#
1 2 3 1 2 AA1.03 - Ability to operate and/or monitor the 295007 High Reactor Pressure / 3 R following as they apply to HIGH REACTOR 3.4 62 PRESSURE : RCIC: Plant-Specific AA2.01 - Ability to determine and/or interpret the 295012 High Drywell Temperature / 5 S following as they apply to HIGH DRYWELL 3.9 83 TEMPERATURE : Drywell temperature AK3.01 - Knowledge of the reasons for the following responses as they apply to HIGH 295013 High Suppression Pool Temp. / 5 R 3.6 61 SUPPRESSION POOL TEMPERATURE :
Suppression pool cooling operation AK1.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE : Protection of the 3.8 59 295017 High Off-site Release Rate / 9 R S general public 2.4.31 - Emergency Procedures / Plan: Knowledge 4.1 80 of annunciator alarms, indications, or response procedures.
2.4.1 - Emergency Procedures / Plan: Knowledge of EOP entry conditions and immediate action R steps 4.6 65 295020 Inadvertent Cont. Isolation / 5 & 7 / 2.2.37 - Equipment Control: Ability to determine S operability and / or availability of safety related 4.6 85 equipment.
EK2.02 - Knowledge of the interrelations between 295032 High Secondary Containment HIGH SECONDARY CONTAINMENT AREA R 3.6 60 Area Temperature / 5 TEMPERATURE and the following: Secondary containment ventilation EA2.02 - Ability to determine and/or interpret the 295033 High Secondary Containment following as they apply to HIGH SECONDARY R 3.1 63 Area Radiation Levels / 9 CONTAINMENT AREA RADIATION LEVELS :
Equipment operability 2.4.21 - Emergency Procedures / Plan: Knowledge of the parameters and logic used to assess the 295035 Secondary Containment High status of safety functions, such as reactivity S control, core cooling and heat removal, reactor 4.6 84 Differential Pressure / 5 coolant system integrity, containment conditions, radioactivity release control, etc.
1 2 K/A Category Point Totals: 1 1 1 1 / / Group Point Total: 7/4 1 3
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 System # / Name K K K K K K A A A A G K/A Topic(s) IR ?#
1 2 3 4 5 6 1 2 3 4 A2.11 - Ability to (a) predict the impacts of the following on the RHR/LPCI:
INJECTION MODE (PLANT SPECIFIC) ;
203000 RHR/LPCI: Injection and (b) based on those predictions, use R 3.4 15 Mode procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Motor operated valve failures A1.06 - Ability to predict and/or monitor changes in parameters associated with operating the SHUTDOWN COOLING 3.7 14 SYSTEM (RHR SHUTDOWN COOLING 205000 Shutdown Cooling R S MODE) controls including: Reactor temperatures (moderator, vessel, flange) 4.0 88 2.1.27 - Conduct of Operations: Knowledge of system purpose and / or function.
K1.06 - Knowledge of the physical connections and/or cause- effect relationships between HIGH PRESSURE COOLANT INJECTION SYSTEM and the 3.7 2 following: Suppression chamber:
206000 HPCI R S BWR-2,3,4 4.6 89 2.4.2 - Emergency Procedures / Plan:
Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
A3.05 - Ability to monitor automatic operations of the LOW PRESSURE CORE 209001 LPCS R 3.9 21 SPRAY SYSTEM including: Reactor water level K5.06 - Knowledge of the operational implications of the following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM : Tank level 3.0 10 measurement 211000 SLC R R A1.02 - Ability to predict and/or monitor 3.8 23 changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including:
Explosive valve indication K2.02 - Knowledge of electrical power 212000 RPS R supplies to the following: Analog trip 2.7 4 system logic cabinets A4.06 - Ability to manually operate and/or 215003 IRM R 3.0 19 monitor in the control room: Detector drives A4.07 - Ability to manually operate and/or 215004 Source Range Monitor R monitor in the control room: Verification of 3.4 20 proper functioning/ operability K4.08 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or interlocks which provide 215005 APRM / LPRM R 2.7 8 for the following: Sampling of overall core power in each APRM (accomplished through LPRM assignments and symmetrical rod patterns)
K4.06 - Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) 217000 RCIC R 3.5 7 design feature(s) and/or interlocks which provide for the following: Manual initiation
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 System # / Name K K K K K K A A A A G K/A Topic(s) IR ?#
1 2 3 4 5 6 1 2 3 4 A3.05 - Ability to monitor automatic operations of the AUTOMATIC 218000 ADS R 3.6 17 DEPRESSURIZATION SYSTEM including:
Suppression pool level K3.21 - Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following:
Traversing in-core probe system A2.01 - Ability to (a) predict the impacts of 2.6 6 the following on the PRIMARY R CONTAINMENT ISOLATION 223002 PCIS/Nuclear Steam 3.5 86
/ R SYSTEM/NUCLEAR STEAM SUPPLY Supply Shutoff S SHUT-OFF ; and (b) based on those 4.0 22 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A.C. electrical distribution failures 2.4.11 - Emergency Procedures / Plan:
Knowledge of abnormal condition procedures.
K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on 239002 SRVs R 3.4 12 the RELIEF/SAFETY VALVES : Air (Nitrogen) supply: Plant-Specific K6.05 - Knowledge of the effect that a loss 259002 Reactor Water Level or malfunction of the following will have on R 3.5 11 Control the REACTOR WATER LEVEL CONTROL SYSTEM : Reactor water level input K1.07 - Knowledge of the physical connections and/or cause- effect 261000 SGTS R relationships between STANDBY GAS 3.1 1 TREATMENT SYSTEM and the following:
Elevated release stack K1.02 - Knowledge of the physical connections and/or cause- effect relationships between A.C. ELECTRICAL DISTRIBUTION and the following: D.C.
electrical distribution A2.09 - Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; and (b) based on those 3.3 25 predictions, use procedures to correct, R control, or mitigate the consequences of 262001 AC Electrical 3.1 16 R / those abnormal conditions or operations:
Distribution S Exceeding voltage limitations 3.2 87 A2.10 - Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low reactor water level: Plant-Specific K3.02 - Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on 2.9 5 following: Recirculation pump speed:
262002 UPS (AC/DC) R R Plant-Specific 2.8 26 A4.01 - Ability to manually operate and/or monitor in the control room: Transfer from alternative source to preferred source
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 System # / Name K K K K K K A A A A G K/A Topic(s) IR ?#
1 2 3 4 5 6 1 2 3 4 K4.02 - Knowledge of D.C. ELECTRICAL DISTRIBUTION design feature(s) and/or interlocks which provide for the following:
Breaker interlocks, permissives, bypasses 3.1 24 263000 DC Electrical and cross ties: Plant-Specific R R A3.01 - Ability to monitor automatic Distribution 3.2 18 operations of the D.C. ELECTRICAL DISTRIBUTION including: Meters, dials, recorders, alarms, and indicating lights A1.09 - Ability to predict and/or monitor changes in parameters associated with operating the EMERGENCY 264000 EDGs R GENERATORS (DIESEL/JET) controls 3.0 13 including: Maintaining minimum load on emergency generator (to prevent reverse power)
K5.13 - Knowledge of the operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Filters A2.04 - Ability to (a) predict the impacts of 2.9 9 300000 Instrument Air R S the following on the CCWS and (b) based on those predictions, use procedures to 3.0 90 correct, control, or mitigate the consequences of those abnormal operation: Radiation monitoring system alarm 400000 Component Cooling K2.01 - Knowledge of electrical power R 2.9 3 Water supplies to the following: CCW pumps 2 1 K/A Category Point Totals: 3 2 2 3 2 2 3 / 3 3 / Group Point Total: 26/5 3 2
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 System # / Name K K K K K K A A A A G K/A Topic(s) IR ?#
1 2 3 4 5 6 1 2 3 4 K5.02 - Knowledge of the operational implications of the following concepts 201001 CRD Hydraulic R as they apply to CONTROL ROD 2.6 38 DRIVE HYDRAULIC SYSTEM : Flow indication K3.02 - Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL CONTROL SYSTEM will have on following: Rod block monitor:
Plant-Specific A2.01 - Ability to (a) predict the impacts 2.9 29 of the following on the REACTOR 201002 RMCS R S MANUAL CONTROL SYSTEM ; and 2.8 91 (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod movement sequence timer malfunctions K4.03 - Knowledge of REACTOR WATER CLEANUP SYSTEM design feature(s) and/or interlocks which 204000 RWCU R 2.9 30 provide for the following: Over temperature protection for system components A3.04 - Ability to monitor automatic operations of the ROD BLOCK 215002 RBM R MONITOR SYSTEM including: 3.6 35 Verification or proper functioning/
operability: BWR-3,4,5 A2.06 - Ability to (a) predict the impacts of the following on the RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE ; and (b) based on 219000 RHR/LPCI: Torus/Pool those predictions, use procedures to 2.9 93 S
Cooling Mode correct, control, or mitigate the consequences of those abnormal conditions or operations: D.C. electrical failures K1.12 - Knowledge of the physical connections and/or cause- effect relationships between RHR/LPCI:
226001 RHR/LPCI: CTMT Spray CONTAINMENT SPRAY SYSTEM 3.0 27 R
Mode MODE and the following: Suppression pool (spray penetration): Plant-Specific.
A2.12 - Ability to (a) predict the impacts of the following on the RHR/LPCI:
TORUS/SUPPRESSION POOL SPRAY MODE ; and (b) based on 230000 RHR/LPCI: Torus/Pool those predictions, use procedures to 3.2 34 R
Spray Mode correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve logic failure A1.03 - Ability to predict and/or monitor changes in parameters associated with 234000 Fuel Handling Equipment R operating the FUEL HANDLING 3.4 33 EQUIPMENT controls including: core reactivity level 2.1.23 - Conduct of Operations: Ability to perform specific system and 239001 Main and Reheat Steam S 4.4 92 integrated plant procedures during all modes of plant operation.
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 System # / Name K K K K K K A A A A G K/A Topic(s) IR ?#
1 2 3 4 5 6 1 2 3 4 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate K2.01 - Knowledge of electrical power 259001 Reactor Feedwater R supplies to the following: Reactor 3.3 28 Feedwater Pumps - Motor drive only K5.02 - Knowledge of the operational implications of the following concepts 268000 Radwaste R 3.1 31 as they apply to RADWASTE :
Radiation hazards and ALARA concept 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection K6.02 - Knowledge of the effect that a loss or malfunction of the following will 288000 Plant Ventilation R have on the PLANT VENTILATION 2.5 32 SYSTEMS : Applicable component cooling water system: Plant-Specific 2.2.44 - Equipment Control: Ability to interpret control room indications to verify the status and operation of a 290001 Secondary CTMT R system, and understand how operator 4.2 37 actions and directives effect plant and system conditions.
A4.01 - Ability to manually operate 290003 Control Room HVAC R and/or monitor in the control room: 3.2 36 Initiate/reset system 290002 Reactor Vessel Internals K/A Category Point Totals: 1 1 1 1 2 1 1 1 1 1 1 Group Point Total: 12
/ /
2 1 3
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Vermont Yankee Date of Exam: 02/14/2014 Category K/A # Topic RO SRO-Only IR ?# IR #
2.1.1 Knowledge of conduct of operations requirements. 3.8 66 Ability to interpret reference materials, such as graphs, curves, 2.1.25 3.9 67 tables, etc.
- 1. Ability to identify and interpret diverse indications to validate the Conduct 2.1.45 4.3 75 response of another indicator.
of Operations 2.1.6 Ability to manage the control room crew during plant 4.8 94 transients Subtotal 3 1 Ability to perform pre-startup procedures for the facility, including 2.2.1 operating those controls associated with plant equipment that 4.5 68 could affect reactivity.
Knowledge of less than or equal to one hour technical 2.2.39 3.9 69
- 2. specification action statements for systems.
Equipment Control Ability to track Technical Specification limiting conditions for 2.2.23 4.6 95 operations.
2.2.19 Knowledge of maintenance work order requirements 3.3 97 Subtotal 2 2 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor 2.3.13 alarms, containment entry requirements, fuel handling 3.4 70 responsibilities, access to locked high radiation areas, aligning filters, etc.
Ability to comply with radiation work permit requirements during 2.3.7 3.5 71 normal or abnormal conditions.
- 3. 2.3.11 Ability to control radiation releases. 3.8 74 Radiation Ability to use radiation monitoring systems, such as fixed Control 2.3.5 radiation monitors and alarms, portable survey instruments, 2.9 96 personnel monitoring equipment, etc.
Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as containment entry 2.3.12 3.7 100 requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Subtotal 3 2 Knowledge of system set points, interlocks and automatic actions 2.4.2 4.5 72 associated with EOP entry conditions.
- 4. 2.4.13 Knowledge of crew roles and responsibilities during EOP usage. 4.0 73 Emergency 2.4.18 Knowledge of the specific bases for EOPs. 4.0 97 Procedures / Ability to verify that the alarms are consistent with the plant Plan 2.4.46 4.2 98 conditions.
Subtotal 2 2 Tier 3 Point Total 10 7
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Vermont Yankee Date of Examination: 02/10/2014 Exam Level: RO SRO-I SRO-U X Operating Test No.: 2014301 Administrative Topic Type Describe activity to be performed (see Note) Code*
Conduct of Operations N, S Perform a system walkdown following a RCIC pump and valve operability tests.
Conduct of Operations M, R Review Daily SRM Response Check prior to Conducting Core Alteration Equipment Control M, R Review Completed Surveillance and Take Action for Out of Spec Data Radiation Control M, R Determine the Radiological Protection Requirements for Entering a Locked High Radiation Area Emergency Procedures/Plan N, R Classify a loss of all offsite and onsite AC event while in mode 5 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: 02/11/2014 Exam Level: RO SRO-I SRO-U Operating Test No.: 2014301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function
- a. MTG Startup the Turbine to Rated Speed S, N, A, L 4
- d. n/a n/a
- e. n/a n/a
- f. n/a n/a
- g. n/a n/a
- h. n/a n/a In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- k. n/a
@ 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-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/1/1 (S)imulator