ML13088A265

Final Outlines (Folder 3)

ML13088A265
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/08/2013
From:	Fish T H Operations Branch I
To:	Entergy Nuclear Vermont Yankee
Jackson D E
Shared Package
ML13017A074	List: IR 05000271/2013301 ML13022A311 ML13063A193 ML13088A265 ML13088A275 ML13088A280 ML13128A120
References
ES-401, ES-401-1, TAC U01898
Download: ML13088A265 (28)

Text

___ BWR Examination Outline Form ES-401-1 II nt Date of Exam: RO KIA Category Points SRO-Only Points Tier Group KKK A A K K K 1 2 3 4 5 6 l' 2 '3 I

• Total 1. 1 5 2 3 3 i 5 2 20 II Emergency Evolutions 2 27 l' " II 8 __

' IIII Tier 4 IV1 2.

__+_41-+-_:-;-2_1:: 2 : : Plant Systems I Tier Totals 5 2 3 5 2 4 4@-3-+-3 U --'--+----1--1-8--I11 1 7 2 3 2 Note: Ensure that at least two topics from every applicable KIA category are sampled within each tier of the and SAO-only outlines (Le., except for one category in Tier 3 of the SAO-only outline, the Tier in each KIA category shall not be less than 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. 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. 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. 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. Select SAO topics for Tiers 1 and 2 from the shadEKi systems and KIA categories. 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. 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. 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 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 K 1 K 2 X K 3 A 1 A 2 G KIA Topic(s) Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CmCULATION and AK2.07 Core flow indication IR 3.4 # 1 295003 Partial or Complete Loss of AC / 6 X Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: AA2.04 System lineups 3.5 2 Ability to operate and/or monitor the following as 295004 Partial or Total Loss of DC Pwr / 6 X 3.B 3 they apply to PARTIAL OR COMPLETE LOSS OF 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 3.2 4 they apply to MAIN TURBINE GENERATOR TRIP: AA2.0B Electrical distribution status. Knowledge of the operational implications of the 295006 SCRAM / 1 X 3.4 5 following concepts as they apply to SCRAM : AK1.02 Shutdown margin Knowledge of the reasons for the following 295016 Control Room Abandonment 17 X 3.5 6 responses as they apply to CONTROL ROOM ABANDONMENT:

AK3.03 Disabling control room controls 295018 Partial or Total Loss of CCW 1 8 295019 Partial or Total Loss of Inst. Air 18 295021 Loss of Shutdown Cooling I 4 295023 Refueling Ace I 8 X X 2.4.31 Knowledge of annunciator alarms, indi,eations, or response procedures.

4.2 7 XI Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: AA2.01 Instrument air system pressure 3.5 8 X , Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING: AA 1.01 Reactor water cleanup system 3.4 9 Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS:

AK1.01 Radiation exposure hazards 3.2 10 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 Ability to determine and/or interpret the 295025 High Reactor Pressure I 3 X 3.9 12 following as they apply to HIGH REACTOR . PRI::SSURE:

EA2.03 Suppression pool tern perature.

Knowledge of the interrelations between 295026 Suppression Pool High Water X 3.6 13 SUPPRESSION POOL HIGH WATER 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 3.5 15 SUPPRESSION POOL WATER LEVEL and the 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

19 Knclwledge of the reasons for the following 600000 Plant Fire On Site I 8 responses as they apply to PLANT FIRE ON SITE: 2.8 Actions contained in the abnormal procedure for plant fire on site 700000 Generator Voltage and Electric Grid Disturbances / 6 X Ability to operate and/or monitor the following as I they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES:

AA 1.01 Grid frequency and voltage 3.6 20 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 295008 High Reactor Water Level / 2 X Knowledge of the interrelations between HIGH 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 3.0 22 following concepts as they apply to LOW REACTOR 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 295014 Inadvertent Reactivity Addition /1 X Knowledge of the operational implications of the following concepts as they apply to INADVERTENT REACTIVITY ADDITION:

AK1.02 Reactivity anomaly 3.3 23 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 3.7 25 following concepts as they apply to INADVERTENT 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 295034 Secondary Containment Ventilation High Radiation!

9 X Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION:

EA1.02 Process 3.9 27 radiation monitoring system 295035 Secondary Containment Differential Pressure! 295036 Secondary Containment SumP/Area Water Level! 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 S stems -Tier 21Group 1 (RO / SRO) System # / Name KKK K G KIA Topic(s) IR # 123 45 6 1 2 Knowledge of the physical connections and/or 203000 RHA/LPCI:

Injection x 3.9 28 causeeffect relationships between RHA/LPCI:

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 3.5 31. malfunction of the following will have on the HIGH PRESSURE COOLANT INJECTION SYSTEM: K6.05 Suppression pool level: BWR-2,3,4 207000 Isolation (Emergency)

Suppressed, does not exist at VY Condenser Knowledge of LOW PRESSURE CORE 209001 3.8 32 ttH-I SPRAY SYSTEM design feature(s) and/or interlocks which provide for the following:

K4.08 Automatic system initiation 209002 HPCS Suooressed, does not exist at VY Knowledge of STANDBY LlaUID CONTROL 211000 SLC 4.2 SYSTEM design feature(s) and/or interlocks 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.

212000 RPS X 2.4.34 Knowledge of RO tasks performed outside the main control room during an emergency and the resuHant operational effects. 4.2 35 215OO31RM X Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including:

A3.04 Control rod block status 3.5 36 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 215004 Source Range Monitor X Ability to monitor automatic operations of the SOURCE RANGE MONITOR (SRM) 3.6 38 SYSTEM including:

A3.04 control rod block S1atus 215005 APRM I LPRM X Ability to (a) predict the impacts of the 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 3.3 40 AVERAGE POWER RANGE MONITOR ILOCAL POWER RANGE MONITOR SYSTEM including:

A3.03 Meters and recorders 217000 RCIC X Knowledge of the operational implications of the following concepts as they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) : K5.01 Indications of pump cavitation 2.6 41 218000 ADS X Knowledge of the effect that a loss or malfunction of the following will have on the AUTOMATIC DEPRESSURIZATION SYSTEM: K6.03 Nuclear boiler instrument system (level indication) 3.8 42 223002 PCIS/Nuclear Steam X Knowledge of the effect that a loss or 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 239002 SRVs X Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES: K5.06 Vacuum breaker operation 2.7 44 259002 Reactor Water Level Control X Ability to manually operate and/or monitor in the control room: A4.04 FWRV lockup reset controls 3.7 45 Knowledge of the effect that a loss or 261000 SGTS 3.1 TREATMENT SYSTEM will have following:

K3.04 High pressure coolant injection system: Plant-Specific malfunction of the STANDBY GAS Knowledge of the physical connections and/or 261000 SGTS cause effect relationships between STANDBY 3.2 GAS TREATMENT SYSTEM and following:

Primary containment 262001 AC Electrical X 2.4.11 Knowledge of abnormal condition 4.0 48 Distribution procedures.

262002 UPS (AC/DC) X Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C.lD.C.)

design feature(s) and/or interlocks which provide for the following:

Transfer from preferred power to alternate power supplies 3.1 49 263000 DC Electrical Distribution X Knowledge of the effect that a loss or malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION:

K6.01 A.C. electrical distribution 3.2 50 I I Ability to predict and/or monitor changes in 264000 EDGs X 2.8 51 parameters associated with operating the EMERGENCY GENERATORS (DIESEUJET) controls including:

A 1.03 Operating voltages, currents, and temperatures 300000 Instrument Air X Knowledge of the connections and / or cause effect relationships between INSTRUMENT AIR SYSTEM and the following:

K1.03 Containment air 2.8 52 400000 Component Cooling Water X I Ability to (al predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

A2.03 High/low CCW temperature 2.9 53 Paint Totals: 2 1 2 5 3 3 1 2 3 1 3 Grou Point Total: 5 Form ES-401-1 II ES-401 BWA Examination Outline Plant Svstems -Tier 21GrouD 2lAO I SAO) System # {Name

1. II 11-------------5 6 1 201002 RMCS Bm Ability to (a) predict the impacts of the 201003 Control Rod and Drive X following on the CONTROL ROD AND 3.1 54 DRIVE MECHANISM; and (b) based those predictions, use procedures correct, control, or mitigate consequences of those conditions or operations:

A2.07 Loss CRD drive water 201004 Ases Suppressed, does not exist at VY Suporessed, does not exist at VY Ability to (a) predict the impacts of the 202001 Recirculation x .. 3.1 55 following on the RECIRCULATION 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 Knowledge of RECIRCULATION FLOW 202002 Racirculation Flow Control x 3.1 56 CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

K4.02 Recirculation pump speed control: Plant-Specific ill 11J Knowledge of the physical connections 215001 Traversing In-core Probe X 3.3 57 and/or cause effect relationships between TRAVERSING IN-CORE PROBE and the following:

K1.05 Primary containment isolation system: BWR1) 215OO2RBM 216000 Nuclear Boiler Inst. 219000 RHRlLPCI:

Torus/Pool Cooling Mode X Ability to manually operate and/or monitor in the control room: A4.12 Suppression pool temperature 4.1 58 223001 Primary CTMT and Aux. X Ability to monitor automatic operations of the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES including:

A3.03 System indicating light and alarms 3.4 59 Knowledge of the operational 226001 RHRlLPCI:

CTMT Spray Mode x 2.6 60 im plications of the following concepts as they apply to RHRlLPCI:

CONTAINMENT SPRAY SYSTEM MODE: K5.06 Vacuum breaker operation 230000 RHRlLPCI:

Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup X Ability to predict and/or monitor changes in parameters associated with operating 3.1 61 the FUEL POOL COOLING AND CLEAN-UP controls including:

AI.03 Pool temperature 234000 Fuel Handlino Eouioment 239001 Main and Reheat Steam 239003 MSIV LeakaQe Control I I Knowledge of the effect that a loss or 241000 ReactorfTurbine Pressure x 3.8 62 malfunction of the following will have on Regulator the REACTORfTURBINE PRESSURE REGULATING SYSTEM: K6.06 Reactor pressure 245000 Main Turbine Gen. / Aux. 256000 Reactor Condensate 259001 Reactor Feedwater X Knowledge of electrical power supplies to the following:

K2.01 Reactor feedwater pump(s): Motor-Driven-Only 3.3 63 268000 Radwaste 271000 Offgas X Knowledge of the effect that a loss or malfunction of the following will have on the OFFGAS SYSTEM: K6.11 Condenser vacuum 3.2 64 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

'"'nlv 1. Conduct of Operations 2.1.23 Ability to perform specific system and integrated plant procedures all modes of plant operation.

IR 4.3 # 66 IR # Ability to interpret 11.-:1<"":;"",,, materials, such as 2.1.25 3.9 67 graphs, curves, tables, etc. Subtotal 2 2.2.12 Knowledge of surveillance procedures.

3.7 68 -2. Equipment Control Ability to recognize system parameters that are 2.2.42 3.9 69 entry-level conditions for Technical Specifications.

Knowledge of the bases in Technical Specifications 2.2.25 3.2 70 for limiting conditions for operations and 3 2.3.4 Knowledge of radiation exposure limits under normal or emergency I 3.2 71 3. conditions.

Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.4 72 4. Emergency Procedures I Plan Gotal 2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.6 2 73 Knowledge of how abnormal operating procedures 2.4.8 3.8 are used in conjunction with EOPs. 2.4.18 Knowledge of the specific bases for EOPs. 3.3 Subtotal 75 ES-401 Tier I Randomly Group Selected KIA Tier 11 295023/AK1.02 Group 1 replaced with AK1.01 Tier 21 2003000/K 1.18 Group 1 replaced with K1.0S Tier 21 215004/A3.03 Group 1 replaced with A3.04 Record of Rejected KI As Form ES-401-4 Reason for Rejection This K& A selection resulted in exam overlap with question #5 for the K&A statement about Shutdown margin. Although different topic names/areas the concept is of limited use in operator knowledge discrimination.

Randomly selected AK1.01, Radiation exposure hazards. This K&A statement ask what the physical relationship between 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. This K&A for monitoring SRM operation and RPS status would not 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 This K&A statement was for design features of recirculation flow 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. This K&A statement on the bearing oil malfunction to reactor/turbine 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. Unable to write a sufficiently discriminating question to this KIA. The original KIA was for decay heat generation which the Chief Examiner and the utility agreed would only result in a GFES level Question.

Randomly selected within the topic area. Unable to a sufficiently discriminating question to this KIA. The 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. Unable to an operationally significant question to this KIA for SBGT iodine removal. The Chief Examiner and the utility agreed would only result in a GFES level question.

Randomly selected within the topic area. Tier 21 202002/K4.05 Group 2 replaced with K4.02 Tier 21 241000/KS.14 Group 2 replaced with K6.0S Tier 1/ 295025/EA2.05 Group 1 replaced with EA2.03 Tier 21 239002/K5.0S Group 1 replaced with K1.06 Tier 21 2S1000/K4.05 Group 1 replaced with K1.11