ML13088A265
ML13088A265 | |
Person / Time | |
---|---|
Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
Issue date: | 03/08/2013 |
From: | Todd Fish Operations Branch I |
To: | Entergy Nuclear Vermont Yankee |
Jackson D | |
Shared Package | |
ML13017A074 | List: |
References | |
ES-401, ES-401-1, TAC U01898 | |
Download: ML13088A265 (28) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 II nt Yankee Date of Exam:
RO KIA Category Points SRO-Only Points KKK A A ~-A4-Y-G--'----;II--A-2--r--G-*-'--T-o-ta-I-;1 Tier Group K K K 1 2 3 4 5 6 l' 2 '3 I
- Total
- 1. 1 5 2 3 3 i 5 2 20 I 7 Emergency &
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1 Evolutions Tier Totals 8 4 __ 3 2 27' IIII l'IV
" II II 2.
Plant Systems I I--_~:__
Tier Totals
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7 Categories ___
2 3 2 3 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the AO and SAO-only outlines (Le., except for one category in Tier 3 of the SAO-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 NAC revisions.
The final AO 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 ouUine; 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. Aefer 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 (IA) of 2.5 or higher shall be selected.
Use the AO and SAO ratings for the AO and SAO'only portions, respectively.
- 6. Select SAO topics for Tiers 1 and 2 from the shadEKi 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. Umit SRO selections to KlAs that are linked to 10 CFR 55.43.
ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emeraencv and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)
ElAPE # / Name / Safety Function K K K A A G KIA Topic(s) IR #
1 2 3 1 2 Knowledge of the interrelations between PARTIAL 295001 Partial or Complete Loss of Forced X OR COMPLETE LOSS OF FORCED CORE FLOW 3.4 1 Core Flow Circulation / 1 & 4 CmCULATION and AK2.07 Core flow indication Ability to determine and/or interpret the following as 295003 Partial or Complete Loss of AC / 6 X they apply to PARTIAL OR COMPLETE LOSS OF 3.5 2 A.C. POWER:
AA2.04 System lineups Ability to operate and/or monitor the following as 295004 Partial or Total Loss of DC Pwr / 6 X they apply to PARTIAL OR COMPLETE LOSS OF 3.B 3 D.C. POWER:
AA 1.02 Systems necessary to assure safe plant shutdown Ability to determine and/or interpret the following as 295005 Main Turbine Generator Trip / 3 X they apply to MAIN TURBINE GENERATOR TRIP: 3.2 4 AA2.0B Electrical distribution status.
Knowledge of the operational implications of the 295006 SCRAM / 1 X following concepts as they apply to SCRAM : 3.4 5 AK1.02 Shutdown margin
Knowledge of the reasons for the following 295016 Control Room Abandonment 17 X responses as they apply to CONTROL ROOM 3.5 6 ABANDONMENT: AK3.03 Disabling control room controls 295018 Partial or Total Loss of CCW 1 8 X 2.4.31 Knowledge of annunciator alarms, 4.2 7 indi,eations, or response procedures.
Ability to determine and/or interpret the following as 295019 Partial or Total Loss of Inst. Air 18 XI they apply to PARTIAL OR COMPLETE LOSS OF 3.5 8 INSTRUMENT AIR: AA2.01 Instrument air system pressure Ability to operate and/or monitor the following as 295021 Loss of Shutdown Cooling I 4 X they apply to LOSS OF SHUTDOWN COOLING: 3.4 9 AA 1.01 Reactor water cleanup system Knowledge of the operational implications of the 295023 Refueling Ace I 8 X following concepts as they apply to REFUELING 3.2 10 ACCIDENTS: AK1.01 Radiation exposure hazards
Ability to operate and/or monitor the following as 295024 High Drywell Pressure /5 X they apply to HIGH DRVWELL PRESSURE: EA 1.20 3.5 11 Standby gas treatmentlFRVS: Plant-Specific K&J~: Ability to determine and/or interpret the 295025 High Reactor Pressure I 3 X following as they apply to HIGH REACTOR 3.9 12
. PRI::SSURE: EA2.03 Suppression pool tern perature.
Knowledge of the interrelations between 295026 Suppression Pool High Water X SUPPRESSION POOL HIGH WATER 3.6 13 Temp. 15 TEMPERATURE and the following: EK2.02 Suppression pool spray: Plant-Specific 295027 Hlgh Containment Temperature 15 no MK III containment at VY Knowledge of the operational implications of the 295028 High Drywell Temperature 15 X follOwing concepts as they apply to HIGH 3.5 14 DRVWELL TEMPERATURE: EK1.01 Reactor water level measurement
Knowledge of the interrelations between LOW 295030 Low Suppression Pool Wtr Lvi / 5 X SUPPRESSION POOL WATER LEVEL and the 3.5 15 following: EK2.07 Downcomer/ horizontal vent submergence Ability to determine and/or interpret the following as 295031 Reactor Low Water Levell 2 X they apply to REACTOR LOW WATER LEVEL: 4.0 16 EA2.02 Reactor power 295037 SCRAM Condition Present X 2.4.18 Knowledge of the specific bases for EOPs. 3.3 17 and Reactor Power Above APRM Downscale or Unknown 11 Knowledge of the reasons for the following 295038 High Off-site Release Rate / 9 X responses as they apply to HIGH OFF-SITE 3.9 18 RELEASE RATE: EK3.02 System isolations I
Knclwledge of the reasons for the following 600000 Plant Fire On Site I 8 X responses as they apply to PLANT FIRE ON SITE: 2.8 19 AK~I.04 Actions contained in the abnormal procedure for plant fire on site Ability to operate and/or monitor the following as I 700000 Generator Voltage and Electric Grid X they apply to GENERATOR VOLTAGE AND 3.6 20 Disturbances / 6 ELECTRIC GRID DISTURBANCES: AA 1.01 Grid frequency and voltage 2017
ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergenc and Abnormal Plant Evolutions - Tier 1/Group 2 CRO / SRO)
ElAPE # / Name / Safety Function K K K A A G KIA Topic(s) IR #
1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 295007 HiQh Reactor Pressure / 3 Knowledge of the interrelations between HIGH 295008 High Reactor Water Level / 2 X REACTOR WATER LEVEL and the following: AK2.05 3.8 21 HPCI: Plant-Specific Knowledge of the operational implications of the 295009 Low Reactor Water Level / 2 X following concepts as they apply to LOW REACTOR 3.0 22 WATER LEVEL: AK1.02 Recirculation pump net positive suction head: Plant- Specific 295010 Hiah Drvwell Pressure / 5 295011 HiQh Containment Temp / 5 SUPIJressed, no MK III containment at VY 295012 HiQh Drvwell Temperature / 5 295013 HiQh Suppression Pool Temp. / 5 Knowledge of the operational implications of the 295014 Inadvertent Reactivity Addition /1 X following concepts as they apply to INADVERTENT 3.3 23 REACTIVITY ADDITION:
AK1.02 Reactivity anomaly
Ability to determine andlor interpret the following as 295015 Incomplete SCRAM 11 X they apply to INCOMPLETE SCRAM: AA2.01 Reactor 4.1 24 POWElr 295017 High Off-site Release Rate I 9 Knowledge of the operational implications of the 295020 Inadvertent Cont. Isolation I 5 & 7 X following concepts as they apply to INADVERTENT 3.7 25 CONITAINMENT ISOLATION: AK1.01 Loss of normal heat sink 295022 Loss of CRD Pumps 11 295029 Hiah SUDPression Pool Wtr LviI 5 Knowledge of the interrelations between HIGH 295032 High Secondary Containment X SECONDARY CONTAINMENT AREA 3.6 26 Area Temperature 15 TEMPERATURE and the following: EK2.04 PCIS/NSSSS 295033 High Secondary Containment Area Radiation Levels I 9
Ability to operate and/or monitor the following as 295034 Secondary Containment X they apply to SECONDARY CONTAINMENT 3.9 27 Ventilation High Radiation! 9 VENTILATION HIGH RADIATION: EA1.02 Process radiation monitoring system 295035 Secondary Containment High Differential Pressure! 5 295036 Secondary Containment High SumP/Area Water Level! 5 Hvdrooen Conc.! 5 II : 0 1 1 0 Gr 7/3
ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1
~
Iant S stems - Tier 21Group 1 (RO / SRO)
System # / Name KKK K G KIA Topic(s) IR #
123 4 5 6 1 2 Knowledge of the physical connections and/or 203000 RHA/LPCI: Injection x causeeffect relationships between RHA/LPCI: 3.9 28 Mode INJECTION MODE (PLANT SPECIFIC) and the following: K1.06 Automatic depressurization Knowledge of electrical power supplies to the 205000 Shutdown Cooling x following: K2.02 Motor operated valves 2.5 29 Knowledge of HIGH PRESSURE COOLANT 206000 HPCI x INJECTION SYSTEM design feature(s) 4.0 30 and/or interlocks which provide for the following: K4.04 Resetting system isolations:
BWR-2,3,4
Knowledge of the effect that a loss or 206000 HPCI X . malfunction of the following will have on the 3.5 31 HIGH PRESSURE COOLANT INJECTION SYSTEM: K6.05 Suppression pool level:
BWR-2,3,4 207000 Isolation (Emergency) Suppressed, does not exist at VY Condenser 209001 LPCS ttH-I Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design feature(s) and/or interlocks which provide for the following:
K4.08 Automatic system initiation 3.8 32 209002 HPCS I Suooressed, does not exist at VY Knowledge of STANDBY LlaUID CONTROL 211000 SLC X SYSTEM design feature(s) and/or interlocks 4.2 33 which provide for the following: K4.08 System initiation upon operation of SBLC control switch
211000 SLC X 2.1.32 Ability to explain and apply system 3.8 34 limits and precautions.
2.4.34 Knowledge of RO tasks performed 212000 RPS X outside the main control room during an 4.2 35 emergency and the resuHant operational effects.
Ability to monitor automatic operations of the 215OO31RM X INTERMEDIATE RANGE MONITOR (IRM) 3.5 36 SYSTEM including: A3.04 Control rod block status
Knowledge of the operational implications of 215004 Source Range Monitor X the following concepts as they apply to 2.8 37 SOURCE RANGE MONITOR (SRM)
SYSTEM: K5.03 Changing detector position Ability to monitor automatic operations of the 215004 Source Range Monitor X SOURCE RANGE MONITOR (SRM) 3.6 38 SYSTEM including: A3.04 control rod block S1atus Ability to (a) predict the impacts of the 215005 APRM I LPRM X following on the AVERAGE POWER RANGE 13.5 39 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct.
control, or mitigate the consequences of those abnormal conditions or operations:
A2.05 Loss of recirculation flow signal
Ability to monitor automatic operations of the 215005 APRM I LPRM X AVERAGE POWER RANGE MONITOR 3.3 40 ILOCAL POWER RANGE MONITOR SYSTEM including: A3.03 Meters and recorders Knowledge of the operational implications of 217000 RCIC X the following concepts as they apply to 2.6 41 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) : K5.01 Indications of pump cavitation Knowledge of the effect that a loss or 218000 ADS X malfunction of the following will have on the 3.8 42 AUTOMATIC DEPRESSURIZATION SYSTEM: K6.03 Nuclear boiler instrument system (level indication)
Knowledge of the effect that a loss or 223002 PCIS/Nuclear Steam X malfunction of the PRIMARY CONTAINMENT 3.7 43 Supply Shutoff ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following:
K3.07 Reactor pressure Knowledge of the operational implications of 239002 SRVs X the following concepts as they apply to 2.7 44 RELIEF/SAFETY VALVES: K5.06 Vacuum breaker operation Ability to manually operate and/or monitor in 259002 Reactor Water Level X the control room: A4.04 FWRV lockup reset 3.7 45 Control controls
Knowledge of the effect that a loss or 261000 SGTS X malfunction of the STANDBY GAS 3.1 46 TREATMENT SYSTEM will have on following: K3.04 High pressure coolant injection system: Plant- Specific Knowledge of the physical connections and/or 261000 SGTS X cause effect relationships between STANDBY 3.2 47 GAS TREATMENT SYSTEM and the following: Primary containment pressure
262001 AC Electrical X 2.4.11 Knowledge of abnormal condition 4.0 48 Distribution procedures.
Knowledge of UNINTERRUPTABLE POWER 262002 UPS (AC/DC) X SUPPLY (A.C.lD.C.) 3.1 49 design feature(s) and/or interlocks which provide for the following: Transfer from preferred power to alternate power supplies Knowledge of the effect that a loss or 263000 DC Electrical X malfunction of the following will have on the 3.2 50 Distribution D.C. ELECTRICAL DISTRIBUTION: K6.01 A.C. electrical distribution I
I
Ability to predict and/or monitor changes in 264000 EDGs X parameters associated with operating the 2.8 51 EMERGENCY GENERATORS (DIESEUJET) controls including: A 1.03 Operating voltages, currents, and temperatures Knowledge of the connections and / or cause 300000 Instrument Air X effect relationships between INSTRUMENT 2.8 52 AIR SYSTEM and the following: K1.03 Containment air I Ability to (al predict the impacts of the 400000 Component Cooling X following on the CCWS and (b) based on 2.9 53 Water those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: A2.03 High/low CCW temperature I
Paint Totals: 2 1 2 5 3 3 1 2 3 1 3 Grou Point Total:
ES-401 5 Form ES-401-1 ES-401 BWA Examination Outline II Plant Svstems - Tier 21GrouD 2lAO I SAO) ~I
~K~K~~A~I~~I~A~A~!,';;G~~~====KI=A=T=OP=i=C(=S)====-""=IA-I Bm System # {Name # II 11------------- 5 6 1 ~3_l_.:44___J.--------------_+-_I--_I1 1~~~l00~l~e~A~D~H~wlm~ul~~~------
201002 RMCS I~~=.:..:.:.::=-------- Ability to (a) predict the impacts of the 201003 Control Rod and Drive X following on the CONTROL ROD AND 3.1 54 Mechanism DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.07 Loss of CRD drive water flow 201004 Ases Suppressed, does not exist at VY
~1005Aels Suporessed, does not exist at VY
~1006AWM
Ability to (a) predict the impacts of the 202001 Recirculation x .. following on the RECIRCULATION 3.1 55 SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A2.22 Loss 01 component cooling water 202002 Racirculation Flow Control x Knowledge of RECIRCULATION FLOW CONTROL SYSTEM design feature(s) 3.1 56 and/or interlocks which provide for the following: K4.02 Recirculation pump speed control: Plant- Specific
~u ill 11J
215001 Traversing In-core Probe X Knowledge of the physical connections 3.3 57 and/or cause effect relationships between TRAVERSING IN-CORE PROBE and the following: K1.05 Primary containment isolation system: (Not BWR1) 215OO2RBM 216000 Nuclear Boiler Inst.
219000 RHRlLPCI: Torus/Pool Cooling Ability to manually operate and/or X 4.1 58 Mode monitor in the control room: A4.12 Suppression pool temperature 223001 Primary CTMT and Aux.
Ability to monitor automatic operations of X 3.4 59 the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES including:
A3.03 System indicating light and alarms
Knowledge of the operational 226001 RHRlLPCI: CTMT Spray Mode x im plications of the following concepts as 2.6 60 they apply to RHRlLPCI:
CONTAINMENT SPRAY SYSTEM MODE: K5.06 Vacuum breaker operation 230000 RHRlLPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup Ability to predict and/or monitor changes X 3.1 61 in parameters associated with operating the FUEL POOL COOLING AND CLEAN-UP controls including: AI.03 Pool temperature 234000 Fuel Handlino Eouioment 239001 Main and Reheat Steam I
239003 MSIV LeakaQe Control I
Knowledge of the effect that a loss or 241000 ReactorfTurbine Pressure x malfunction of the following will have on 3.8 62 Regulator the REACTORfTURBINE PRESSURE REGULATING SYSTEM: K6.06 Reactor pressure 245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate 259001 Reactor Feedwater Knowledge of electrical power supplies X 3.3 63 to the following: K2.01 Reactor feedwater pump(s): Motor-Driven-Only 268000 Radwaste 271000 Offgas Knowledge of the effect that a loss or X 3.2 64 malfunction of the following will have on the OFFGAS SYSTEM: K6.11 Condenser vacuum
Knowledge of the effect that a loss or 272000 Radiation Monitoring 3.5 65 malfunction of the RADIATION MONITORING System will have on following: K3.05 Offgas system 286000 Fire Protection 288000 Plant Ventilation 290001 SecondarY CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals
- I I I I I I 2 1 2 I I Graue Point Total: 1213
Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 II Date of Exam:
Category KIA # Topic RO ~r'"' '"'nlv IR # IR #
2.1.23 Ability to perform specific system and integrated 4.3 66 plant procedures durin~J all modes of plant
- 1. operation.
Conduct of Operations 2.1.25 Ability to interpret 11.-:1<"":;"",,, materials, such as 3.9 67 graphs, curves, tables, etc.
2.
Equipment Subtotal 2.2.12 Knowledge of surveillance procedures. 3.7 2
68 -
Control 2.2.42 Ability to recognize system parameters that are 3.9 69 entry-level conditions for Technical Specifications.
2.2.25 Knowledge of the bases in Technical Specifications 3.2 70 for limiting conditions for operations and safety limits.
~lJhtot~1 I~~
3 2.3.4 Knowledge of radiation exposure limits under 3.2 71 normal or emergency I conditions.
3.
Radiation Control 2.3.14 Knowledge of radiation or contamination hazards 3.4 72 that may arise during normal, abnormal, or emergency conditions or activities.
Gotal 2 2.4.1 Knowledge of EOP entry conditions and immediate 4.6 73 action steps.
4.
Emergency Procedures I Plan
2.4.8 Knowledge of how abnormal operating procedures 3.8 74 are used in conjunction with EOPs.
2.4.18 Knowledge of the specific bases for EOPs. 3.3 75 Subtotal
ES-401 Record of Rejected KIAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA Tier 11 295023/AK1.02 This K& A selection resulted in exam overlap with question #5 for Group 1 replaced with the K&A statement about Shutdown margin. Although different topic AK1.01 names/areas the concept is of limited use in operator knowledge discrimination. Randomly selected AK1.01, Radiation exposure hazards.
Tier 21 2003000/K 1.18 This K&A statement ask what the physical relationship between Group 1 replaced with K1.0S RHR/LPCI and the Reactor vessel is. It would be difficult to write an adequate question beyond what the RHR to vessel flowpath is.
Randomly selected K1.0S for the ADS relationship to RHA.
Tier 21 215004/A3.03 This K&A for monitoring SRM operation and RPS status would not Group 1 replaced with A3.04 have resulted in a valid question. The only connection would be using the concept of RPS shorting links removed which VY has not done in many years and has no operational intention or need of doing to make the logic system non-coincidence. A question about control rod block status is more operationally relevant Tier 21 202002/K4.05 This K&A statement was for design features of recirculation flow Group 2 replaced with K4.02 control that limited recirc pump speed mismatch. There are no design features at VY that do this. Another statement was randomly chosen resulting in a much broader area of knowledge in this topic.
Tier 21 241000/KS.14 This K&A statement on the bearing oil malfunction to reactor/turbine Group 2 replaced with K6.0S pressure control was a low value (2.7) and would result in limited topics for a valid RO question. Randomly chose KS.OS for a better higher cognitive question result.
Tier 1/ 295025/EA2.05 Unable to write a sufficiently discriminating question to this KIA. The Group 1 replaced with original KIA was for decay heat generation which the Chief EA2.03 Examiner and the utility agreed would only result in a GFES level Question. Randomly selected within the topic area.
Tier 21 239002/K5.0S Unable to writ4~ a sufficiently discriminating question to this KIA. The Group 1 replaced with K1.06 original KIA was for vacuum breaker operation on SRV's which the Chief Examiner and the utility agreed would only result in a GFES level Question. Randomly selected within the topic area.
Tier 21 2S1000/K4.05 Unable to writl~ an operationally significant question to this KIA for Group 1 replaced with K1.11 SBGT iodine removal. The Chief Examiner and the utility agreed would only result in a GFES level question. Randomly selected within the topic area.