ML090790241

From kanterella
Revision as of 02:11, 12 July 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search

Final Outlines (Folder 3)
ML090790241
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 02/05/2009
From:
Entergy Nuclear Operations
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML082600332 List:
References
TAC U01743
Download: ML090790241 (23)
v • d • e


Text

Written & 1. (i.e., +1 Systems/evolutions D.1 .b KAs 7.* WAS D.1 .b WA's #1 IRs, WAS ES-401 Examination Form ES-401-1 3. Generic Knowledge Abilities Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines Note: except for one category in Tier 3 of the SRO-only outline, the " Tier Totals" in each WA category shall not be less than two). 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 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. within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section of ES-401, for guidance regarding elimination of inappropriate WA 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 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. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

The generic (G) in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section of ES-401 for the applicable On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category.

Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note does not apply). Use duplicate pages for RO and SRO-only exams. For Tier 3, select topics from Section 2 of the WA Catalog, and enter the WA numbers, descriptions, and point totals (#) on Form ES-401-3. Limit SRO selections to that are linked to 10CFR55.43 76 77 78 82 45 Pa~tial Inst. i i of / / 1 Partial Forceci & i Drywell ! / Drywell / Inst. 18 - and/or INS'TRUMENT safety- - AA2.02 - and/or MAIN TRIP - andior D.C. 2.1.19 - - Corltrol: - and alarm. - aridlor tlie tollowing HIGH DRYWELL AKl MAIN TRIP EKl HIGH DRYWELL EK1 HIGH - FIRE SITE 3.7 2.7 2,9 3,9 3.3 2 Form ES-401-1 Vermont Yankee Written Examination Emergency and Abnormal Plant Evolutions

-Tier 1 Group 29501 9 or Total Loss of Air 8 X AA2.02 Ability to deterrnine interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF AIR : Status of related instrument air system loads (see AK2.1 AK2.19) 295005 Main Turbine Generator Trip 3 X Ability to determine interpret the following as they apply to TURBINE GENERATOR

Turbine vibration 295004 Partial or Total Loss DC Pwr 6 X AA2.03 Ability to determine interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF POWER : Battery voltage 295006 SCRAM X Conduct of Operatioris:

Ability to use plant computers to evaluate system or component status. 3.8 79 295001 or Complete Loss of Core Flow Circulation 1 4 X 2.2.40 Equipment Ability to apply technical specifications for a system. 4.7 80 295025 High Reactor Pressure 3 X 2.4.45 Ability to prioritize interpret the significance of each annunciator or 4.3 81 295028 High Temperature 5 X EA2.02 Ability to determine interpret as they apply to TEMPERATURE

Reactor pressure 295005 Main Turbine Generator Trip 3 X .O1 -Knowledge of the operational implications of the following concepts as they apply to TURBINE GENERATOR
Pressure effects on reactor power 4.0 39 295028 High Temperature I 5 X .O1 -Knowledge of the operational implications of the following concepts as they apply to TEMPERATURE
Reactor water level measurement 3.5 40 295030 Low Suppression Pool Water Level 15 .O1 -Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: Steam condensation 3.8 41 295026 Suppression Pool High Water Temp. 5 X EK2.06 -Knowledge of the interrelations between SUPPRESSION POOL WATER TEMPERATURE and the following:

Suppression pool level 3.5 42 29501 9 Partial or Total Loss of Air X AK2.04 -Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following:

Reactor water cleanup 2.8 43 600000 Plant Fire On-site 18 X AK2.04 Knowledge of the interrelations between PLANT ON and the following:

Breakers, relays, and disconnects 2.5 44 295023 Refueling Accidents X AK3.03 -Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS:

Ventilation isolation.

47 -- 51 52 / / / 11 / / 1 / & Drywell / / / / / - - GRID AA1 and/or - and/or 3,5 3.4 4.0 ----- tem - and/or - - - / X 314 4/3 2017 2 Form ES-401-1 Vermont Yankee Written Examination Emergency and Abnormal Plant Evolutions

-Tier 1 Group 46 48 49 50 29501 8 Partial or Total Loss of CCW 8 29501 6 Control Room Abandonment 7 700000 Generator Voltage and Electric Grid Disturbances 295004 Partial or Total Loss of DC Pwr 6 295006 SCRAM 295021 Loss of Shutdown Cooling 4 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown X X 295001 Partial or Complete Loss of Forced Core Flow Circulation 1 4 295024 High Pressure 5 295038 High Off-site Release Rate 9 295031 Reactor Low Water Level 2 295003 Partial or Complete Loss of AC 6 295025 High Reactor Pressure 3 WA Category Totals: AK3.04 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Starting standby pump AK3.03 -Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT

Disabling control room controls AA1.05 Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC DISTURBANCES:

Engineered safety features. .O1 -Ability to operate monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : D.C. electrical distribution systems AA1.06 Ability to operate and/or monitor the following as they apply to SCRAM : CRD hydraulic system AA2.05 -Ability to determine interpret the following as they apply to LOSS OF SHUTDOWN COOLING : Reactor vessel metal temperature EA2.04 -Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : 3.3 3.9 3.3 3.5 X 4 X X X 3 Suppression pool perature AA2.06 Ability to determine interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION

Nuclear boiler instrumentation 2.1.30 -Conduct of Operations:

Ability to locate and operate components, including local controls.

2.1.23 Conduct of Operations:

Ability to perform specific system and integrated plant procedures during all modes of plant operation.

2.4.46 -Emergency Procedures I Plan: Ability to verify that the alarms are consistent with the plant conditions.

AK3.01 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER : Manual and auto bus transfer 2.4.34 Emergency Procedures Plan: Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. Group Point Total: X X 3 3 3.2 53 X X X 4.4 54 I 4.3 55 4.2 56 3.3 57 4.2 58 2,9 4,4 3,2 3,4 Cor?der>ser Vac i High / Temperatirre Drywell 15 15 19 Conc. / 83 84 59 Offgas system 2.1.23 - perform system nlodes - s~~ch giaptis, HIGH DRYWELL - Plant-Specilic EK3.01 HIGH - andlor HIGH 2.1.28 - andlor HIGH SUMPIAREA 112 11 SumplArea

/ WA 4,1 x 211 64 3 Form ES-401-1 Vermont Yankee Written Examination Emergency and Abnormal Plant Evolutions

-Tier 1 Group 4.2 3.3 295002 Loss of Main 3 295017 Off-site Release Rate 9 295013 High Suppression Pool !5 295010 High Pressure 295029 High Suppression Pool Water Level 295033 High Secondary Containment Area Radiation Levels 500000 High CTMT Hydrogen 5 85 61 AA2.04 Ability to determine andior interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM : flow Conduct of Operations:

Ability to specific and integrated plant procedures during all of plant operation.

2.1.25 Ability to interpret reference materials, as curves. tables, etc. AK1.03 -Knowledge of the operational implications of the following concepts as they apply to PRESSURE : Temperature increases EK2.02 Knowledge of the interrelations between HlGH SUPPRESSION POOL WATER LEVEL and the following:

HPCI: -Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT AREA RADIATION LEVELS : Emergency depressurization EA1.03 -Ability to operate and monitor the following as they apply to HlGH CONTAINMENT HYDROGEN CONTROL: Containment atmosphere control system EA2.01 Ability to determine X X interpret the following as they apply to SECONDARY CONTAINMENT AREA TEMPERATURE

Area temperature

-Conduct of Operations:

Knowledge of the purpose and function of major system components and controls.

EA2.03 Ability to determine interpret the following as they apply to SECONDARY CONTAINMENT WATER LEVEL : Cause of the high water level Group Point Total: X 3.4 X 62 X 295032 High Secondary Containment Area Temperature 15 295015 Incomplete SCRAM 295036 Secondary Containment High Water Level 5 Category Totals: 1 1 I 3.8 1 63 1 X 3.4 65 713 (AC!DC) X A2.14. - ; (b) or) use faiicire - the : and (bj consequences steam flow inputs - operatior]

system - - LIQUID ; (b) rnitigate clostlres - LIQUID - 1 3,2 4 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems -Tier 2 Group 1 203000 RHRILPCI:

Injection Mode Abiiity to (a) predict the impacts of the following on the RHRILPCI:

INJECTION MODE (PLANT SPECIFIC) and based those predictions, procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations:

Initiating logic 3.9 86 259002 Reactor Water Level Control X A2.01 Ability to (a) predict the impacts of the following on REACTOR WATER LEVEL CONTROL SYSTEM based on ttiose predictions, use procedures to correct. control, or rnitigate the of those abnormal conditions or operations:

Loss of any number of rnain 3.4 87 400000 Component Cooling Water 2.4.49 Etnergency Procedures

!Plan: Ability to perforrn without reference to procedures those actioris that require irnrnediate of components and controls.

4.4 88 262002 UPS 2.1.20 Ability to interpret and execute procedure steps. 4.6 89 21 1000 SLC X A2.07 Ability to (a) predict the impacts ot the following on the STANDBY CONTROL SYSTEM and based on those predictions, use procedures to correct. control, or ttie consequences of those abnormal conditions or operations:

Valve 90 21 1000 SLC X K1.03 Knowledge of the physical connections and/or cause-effect relationships between STANDBY CONTROL SYSTEM and the following:

Plant air systems: Plant-Specific 2.5 1 400000 Component Cooling Water K1.03 Knowledge of the physical connections and or cause-effect relationships between CCWS and the following:

Radiation monitoring systems 2.7 2 263000 DC Electrical Distribution X K2.01 -Knowledge of electrical power supplies to the following:

Major D.C. loads 3.1 3 205000 Shutdown Cooling X K2.02 -Knowledge of electrical power supplies to the following:

Motor operated valves 2.5 4 13 EDGs RHRILPCI:

SRVs - feature(s) andlor - feature(s) andlor - - EFISAFETY andlor andlor 3,9 2.7 3,8 3.8 4 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems -Tier 2 Group 1 K3.04 -Knowledge of the effect that a loss or malfunction of the 262001 AC Electrical Distribution X A.C. ELECTRICAL DISTRIBUTION will have on 3.1 5 following:

Uninterruptible power supply K3.02 -Knowledge of the effect that a loss or malfunction of the 264000 X EMERGENCY GENERATORS (DIESEUJET) will have on following:

A.C. electrical distribution K4.01 Knowledge of STANDBY GAS TREATMENT 261 000 SGTS X SYSTEM design interlocks which provide 3.7 7 for the following:

Automatic system initiation K4.05 Knowledge of RHWLPCI: INJECTION MODE 203000 Injection Mode X (PLANT SPECIFIC) design interlocks 3.2 8 which provide for the following:

Prevention of water hammer K5.01 Knowledge of the operational implications of the 21 2000 RPS X following concepts as they apply to REACTOR PROTECTION SYSTEM : Fuel thermal time constant K5.01 Knowledge of the operational implications of the 218000 ADS X following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM : ADS logic operation K6.01 -Knowledge of the effect that a loss or malfunction of the 209001 LPCS X following will have on the LOW 3.4 11 PRESSURE CORE SPRAY SYSTEM : A.C. power K6.04 -Knowledge of the effect that a loss or malfunction of the 239002 X following will have on the 3.0 12 RELI VALVES : D.C. power: Plant-Specific A1 .O1 -Ability to predict monitor changes in parameters 259002 Reactor Water Level Control X associated with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including:

Reactor water level A1.04 -Ability to predict monitor changes in parameters 21 5004 Source Range Monitor X associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls 3.5 14 including:

Control rod block status (ACIDC) PClSlNuclear

/ RClC HPCl X 4,1 4.0 2,7 - ; - UNINTERRUPTABLE (A.C.1D.C.)

- SYS'TEMINUCLEAR

~- -- ~ MONITOWLOCAL converter/comparator and/or and/or BWR-2,3,4

/ / 19 20 22 I 4 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems -Tier 2 Group 1 215003 IRM 262002 UPS 223002 Steam Supply Shutoff 215005 APRM LPRM 217000 206000 300000 Instrument Air 262001 AC Electrical Distribution X X X X X X 3.7 2.6 3.4 3.3 4.5 A2.04 Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Up scale or down scale trips A2.01 Ability to (a) predict the impacts of the following on the POWER SUPPLY and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Under voltage A3.01 Ability to monitor automatic operations of the PRIMARY CONTAINMENT ISOLATION STEAM SUPPLY SHUT-OFF including:

System indicating lights and alarms A3.05 -Ability to monitor automatic operations of the AVERAGE POWER RANGE POWER RANGE MONITOR SYSTEM including:

Flow alarms A4.05 -Ability to manually operate monitor in the control room: Reactor water level A4.02 -Ability to manually operate monitor in the control room: Flow controller:

2.4.4 -Emergency Procedures Plan: Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

2.4.30 -Emergency Procedures Plan; Knowledge of events related to system operation I status that must be reported to internal organizations or external agencies, such as the state, the NRC, or the transmission system operator.

15 16 17 18 21 3,8 ; - feature@)

andlor - - 24 I 32S2 KIA 2615 4 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems -Tier 2 Group 1 A2.14 -Ability to (a) predict the impacts of the following on the RHWLPCI: INJECTION MODE 203000 RHWLPCI: Injection Mode X (PLANT SPECIFIC) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of 3.8 23 those abnormal conditions or operations:

Initiating logic failure K4.03 Knowledge of AUTOMATIC 21 8000 ADS X DEPRESSURIZATION SYSTEM design interlocks which provide for the following:

ADS logic control A3.02 Ability to monitor 21 5004 Source Range Monitor X automatic operations of the SOURCE RANGE MONITOR (SRM) SYSTEM including:

3.4 25 Annunciator and alarm signals K2.02 Knowledge of electrical 215005 APRM LPRM X power supplies to the following:

2.6 26 APRM channels Category Totals: 2 3 2 3 2 2 2 33 Group Point Total:

Rad~vaste RWCU Primaty ToruslPool CoolinglCleanup of FIRE : (b) 2.2.36 maintenance or) the for - Enlergency

/ andlor P-Spec(Not-BWR6) - - RHRILPCI:

TORUSISLIPPRESSION feature@)

INTERNALS 3'1 2,7 27 33 5 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems -Tier 2 Group 2 286000 Fire Protection X A2.08 -Ability to (aj predict the impacts the following on the PROTECTION SYSTEM and based on those predictions, use procedures to correct, control. or mitigate the consequences ot those abnormal conditions or operations:

failure to actuate when required 3.3 91 268000 -Equipment Control: Ability to analyze the effect of activities, such as degraded power sources. status of limiting conditions operations.

4.2 92 204000 2.4.6 Procedures Plan: Knowledge symptom based EOP mitigation strategies.

4.7 93 201 006 RWM X K1.04 -Knowledge of the physical connections cause-effect relationships between ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) and the following:

Steam flowlreactor power: 223001 CTMT and Aux. X K2.08 Knowledge of electrical power supplies to the following:

Containment cooling air handling units: Plant-Specific 2.7 28 256000 Reactor Condensate X K3.04 Knowledge of the effect that a loss or malfunction of the REACTOR CONDENSATE SYSTEM will have on following:

Reactor Feedwater System 3.6 29 230000 RH WLPCI: Spray Mode X K4.02 -Knowledge of POOL SPRAY MODE design and/or interlocks which provide for the following:

Redundancy 3.1 30 290002 Reactor Vessel lnternals X K5.07 -Knowledge of the operational implications of the following concepts as they apply to REACTOR VESSEL : Safety Limits 3.9 31 201 002 RMCS X K6.01 -Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR MANUAL CONTROL SYSTEM : Select matrix power 2.5 32 233000 Fuel Pool X A1.07 -Ability to predict and/or monitor changes in parameters associated with operating the FUEL POOL COOLING AND CLEAN-UP controls including:

System temperature WA 11111111/1 - ; - and/or - / 3,1 3,4 34 36 11212 213 3,6 37 4,2 38 5 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems -Tier 2 Group 2 A2.08 Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM and (b) based on those predictions, use procedures to 202001 Recirculation X correct, control, or mitigate the consequences of those abnormal conditions or operations:

Recirculation flow mismatch:

Plant-Specific A3.10 -Ability to monitor automatic operations of the 3.4 35 259001 Reactor Feedwater X REACTOR FEEDWATER SYSTEM including:

Pump trips A4.02 Ability to 234000 Fuel operate monitor in the X control room: Control rod drive system Equipment 2.2.37 Equipment Control: Ability to determine operability 290001 Secondary CTMT and or availability of safety related equipment.

2.4.47 -Emergency Procedures I Plan: Ability to diagnose 272000 recognize trends in an accurate Monitoring and timely manner utilizing the appropriate control room reference material.

1 Category Totals: Group Point Total:

0711 # .39 2'125 2'1'8 conservat~ve decisran mak~ng practices.

Ab~l~ty mater~als, etc, 10CFR55, IR IR Q# Q# 2'2'35 2.2'21 2.2.40 2'2'37 Ab~lity determ~ne Techn~cal Specification post-ma~ntenance operab~lty requlrements.

and/or lequipment.

2'3'4 Ability rad~atian responsib~lities, high- ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility:

Vermont Yankee Written Date: 7/08 Category WA Topic RO SRO-Only 1. Conduct of Operations Knowledge of 4.3 94 to Interpret reference such as graphs, curves, tables, 4.2 100 Ability to coordinate personnel activities outside the control room. 3.4 66 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, " no-solo" operation, maintenance of active license status, etc. 3.3 67 Subtotal 2 2 2. Equipment Control to Mode of Operation.

4.5 95 Knowledge of pre and 4.1 99 2.2.1 3 Knowledge of tagging and clearance procedures 4.1 68 Ability to apply technical specifications for a system. 3.4 69 Ability to determine operability availability of safety related 3.6 75 Subtotal 3 2 3. Radiation Control 2.3.1 1 to control releases.

4.3 96 2.3.1 2 Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling access to locked radiation areas, aligning filters, etc. 3.2 70 Knowledge of radiation exposure limits under normal or emergency conditions.

3.2 71 Subtotal 2 1 peration ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 of system components WA's / 1 / ES-401 Record of Rejected Form ES-401-4 Topic does not apply to VY. Randomly selected EA1.03, correct, control, or mitigate the consequences of those abnormal conditions or operations:

D.C. distribution failure: Plant-Specific Topic does not lend itself to a discriminating question (system function)

Randomly selected A2.08, Ability to (a) PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Failure to actuate when required 204000 2.4.3 256000 K3.07 multi unit license. Randomly selected 2.2.1 3, 201 006 K1.08 ECIFIC) and the following:

Steam WA's 1 Form ES-401-4 Record of Rejected VY has electric feed pumps could not write a specific 295023 AK3.05 not apply to VY, randomly selected AK3.03 Low LOD for a discriminating SRO level question for this I I N09-1 I I I Typecode*

1 1 I N, S 1 N, S Offgas ERFlS Drywell ProceduresIPlan I SROs. to~ics, I I D, S (C)ontrol (S)imulator (3), Class(R)oom (D)irect (5 ROs; 5 (N)ew (M)odified (2 (P)revious (5 ; JPM: I ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Vermont Yankee Date of Examination:

2/09 I Examination Level: RO Operating Test Number: Administrative Topic Describe activity to be performed (see Note) Equipment Control JPM: Perform the RHR System Valve Lineup 2.1.29 (4.1) Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. 2.3.1 1 (3.8) Ability to control radiation releases I JPM: Determine Release Rate without 2.2.1 2 (3.7) Knowledge of Surveillance Procedures JPM: Perform a Temperature Profile Emergency 2.4.43 (3.2) Knowledge of Emergency Communications Systems and techniques Perform Control Room Emergency Communications Checks NOTE: All items (5 total) are required for RO applicants require only 4 items unless they are retaking onlv the administrative when 5 are required.

  • Type Codes & Criteria:

room (0), or (1) from bank 3 for 4 for SROs & RO retakes) (1) or from bank 1) (3) 2 exams 1 randomly selected)

(0) NUREG-1021, Revision 9 N09-1 I I 1 JPM: 1 N, S 1 I I JPM: I - - JPM: Offgas ERFlS ProceduresIPlan - SROs. & (C)ontrol (S)imulator, Class(R)oom (D)irect (5 ROs; 2 & (N)ew (M)odified (2 (P)revious (5 1 ES-Administrative Topics Outline Form ES-301-1 Facility:

Vermont Yankee Date of Examination:

2/09 Examination Level: SRO Operating Test Number: Administrative Topic (see Note) Conduct of Operations Type Code* Perform the RHR System Valve Lineup Describe activity to be performed 2.1.29 (4.0) Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc. 2.1.7 Ability to evaluate plant performance and Conduct of make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation Perform a Core Thermal Hydraulic Limits Evaluation Equipment Control Radiation Control Emergency 2.2.1 2 (4.1) Knowledge of Surveillance Procedures JPM: Review a Surveillance 2.3.1 1 Ability to control radiation releases Determine Release Rate without 2.4.44 Knowledge of Emergency Plan Protective Action Recommendations Off-Site Protective Action Recommendations (evacuate)

NOTE: All items (5 total) are required for RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes Criteria:

room, (0) (3) or (2) from bank 3 for 4 for SROs RO retakes) (1) or from bank 1) (4) 2 exams ; randomly selected)

(1) NUREG-1 021, Revision 9 Room/ln-Plant WA: 3.713.9 ES-301 Control Systems Outline Form ES-301-2 Transformer APE 295037 Scram Condition Present and Reactor Power Above APRM Downscale or Unknown EA1.10 NUREG-1021, Revision

/ 1 I I I I I 5 I I I I ' 1 I I/ i I - 6. kW f kVAR v~brations surve~llance 3.10.8.1 INHIBIT w~th powerllevel unt~l and/or I I l -1 requlres Type* 3 mfRR-11B sec I SRO NIA m~~-03~ sec. mfAN08G5 P N - ,,, - SRO R RO R - SRO - C SRO I Appendix D Scenario Outline Form ES-D-1 Facility:

VERMONT YANKEE Scenario No.: 1 Op Test No.: 2009 NRC Examiners:

Operators:

SRO RO -BOP -Initial Conditions:

At 100% power DG " A has been operating for 30 minutes for Monthly Diesel Generator Slow Start Operability Test (Tech Spec) per OP 4126, Sect The test is being performed following a-diesel lube oil change. The test must be run for at least two hours at 2700 to 2750 and 1600 50 OUT. RHR Pump B is OOS for severe vibrations that occurred during surveillance testing and is tagged out for Maintenance investigation.

Turnover:

RHR Pump B is OOS for severe that occurred during testing and is tagged out for Maintenance investigation.

DG " A is in operation for the Monthly Diesel Generator Slow Start Operability Test per OP 4126, Sect B. This requires DG A being declared inop IAW T.S. You are requested to bring voltage to 358 KV by VELCO Critical Tasks: 1. With a reactor scram required and the reactor not shutdown, ADS to prevent an uncontrolled RPV depressurization to prevent causing a significant power excursion.

2. During an ATWS conditions met to perform control TERMINATE AND PREVENT INJECTION into the RPV using appendix GG, conditions are met to re-establish injection.
3. With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron inserting control rods, to prevent exceeding the primary containment design limits. Event No. Malf. No. " B" Recirc speed controller will fail and will begin to run away requiring the RO to take manual control and rebalance flows. 4 Raise Main Generator output to heavy load schedule and maximum Lagging (OUT) VAR Load IAW OP 2140, Sect. H. Turbine Vibration respond per ARS 7-F-2 (lower power stop test) Lower power OP 0105, Reactor Operations (vibrations stop after lowering generator load) DG A -Jacket Water Leak removing DG from service Event 1 2 Event Description 100% over 600 I -RO -60% over 300 SPURIOUS BOP --I I D I I MCC-9A (AC-6B MSlV 88 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor - R0 - Sflo - Sflo M- RO - Sflo 5 7 mfED-05Da rnf~~05~b mfRP-02A mfSL-02A Appendix Scenario Outline Form ES-D-1 Loss of with a failure of the Group 3 Isolation will not auto close) Consult Tech Specs 480V MCC-8B will trip causing a half scram (if RPS B was transferred to its alternate supply) also the loss of the bus will challenge DW pressure by the loss of power to RRUs 1 A and 1 B, alternate RRUs must be started. (This power lost will affect ATWS recovery by preventing the use of cooling water flow to insert the control rods.) The SRO will address TS Loss of RPS MG Set A, Hydraulic ATWS with closure SLC Squib Valve " A failure (the loss of takes away SLC Pump B) Candidate must recognize that the Squib Valves must be fired locally using the battery.
  • TS -SRO C-BOP TS -SRO ALL C -6 8 mf RD-I 2A mf RD-1 2B (20120%)

I I Indefinite LC0 LC0 "C" MSlV % "B 1 I 110. I Type* N'A I: mfNM-03C I-RO - 1 ;:%I switch continuethe MfRD-15 mf~p-03 C-BOP HPCl P-04 C-SRO T~-~R~ HPCl HPCl 3.5.E 1 rnfED-02A 1 M - ALL 1 mfDG-OsA - DGs mfDG-08B C-SRO 1 Appendix Scenario Outline Form ES-D-1 Facility:

VERMONT YANKEE Scenario No.: 2 Op Test No.: 2009 NRC Examiners:

SRO -RO -BOP -Initial Conditions:

At -1 power, Startup in progress.

OP 01 05, Phase 2.D Step 10 " A" IRM failed upscale during the startup and is bypassed.

RHR Pump " C" is OOS Turnover:

due to IRM " A" OOS (TS Table 3.1.1 and TRM 3.2.5) RHR Pump " C" is OOS for severe vibrations during surveillance testing. Tagged out on previous shift; estimated return to service is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 7-day due to RHR Pump OOS (TS 3.5.A.3) Isolation Testing is NOT required Critical Task: 1. Following a Loss of Normal Power diagnoses DG failed to auto-start and manually starts " B DG and places on 4KV Bus 4. With the reactor shutdown and reactor pressure greater than the shutoff head of the low pressure systems, initiate RPV-ED BEFORE RPV level reaches -1 9 inches Restore and maintain RPV level above TAF (+6 inches) I I Event Malf. No. Event Event Description Withdraw control rods to continue the startup 2 IRM " C lnop Failure, results in half scam. (1 00%) I-SRO TS SRO Transfer Reactor Mode to RUN and startup. I-RO Failure of CRD Flow Controller Automatic Output Signal I-SRO 5 inadvertently injects to the vessel with a controller failure mf H (low -to prevent a reactor scram). The crew will confirm that the injection is spurious and trip the turbine. Requires T.S. entry Loss of the startup transformers which will result in a LNP and reactor scram. 7 mf ED-02B C Both fail to auto start, DG " A cannot be started, DG " B can be manually started.

I I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor mf~~-~l~ mfRC-03 RClC mfRC C "B" Drywell RClC Appendix D Scenario Outline Form ES-D-1 8 9 OVRD ANN -flow controller failure -RClC inadvertent Isolation M ALL -BOP C-SRO

  • Core spray line break in the between the RPV and injection check valve resulting in a LOCA and loss of the remaining Core Spray system. Controller Fails in AUTO, then isolates I ES-D-1 I LC0 Oncemeek drywell 280QF, (andlor SRVs AND/OR 3 N/A mfFW-28A 50% over 60 sec mf~~-01 B (if Type* N - RO - SRO R - - - SRO SRO - TS OnceNVeek Appendix Scenario Outline Form Facility:

VERMONT YANKEE Scenario No.: 3 Op Test No.: 2009 NRC Examiners:

SRO -RO -BOP -Initial 85% power IC-807 " A" RHR OOS for severe vibration, maintenance is investigating.

RHR Pump " A" is OOS while maintenance investigates high vibration.

It was tagged out on the previous shift; estimated return to service is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 7-day due to RHR Pump " A" OOS (TS 3.5.A.3) Perform OP 4160 Pump Performance Test Section 1 .a and b. Critical 1. When temperature cannot be restored and maintained below initiate RPV-ED anticipate ED and use bypass valves). IF Reactor water level cannot be determined, Enters EOP-6, RPV Flooding, opens all and commences injection using Shutdown RPV Flooding Systems until the Main Steam lines are flooded. OR 3. Restores RPV water level and containment parameters with Condensate injecting directly into the RPV aligns alternate injection systems such as RHR. 1 2 Malf. No. necessary)

Event SRO I RO , Event Description Perform OP 4160 Pump Performance Test Section 1 .a and b. Feedwater flow transmitter slow failure upscale, causing the crew to take manual control of feedwater in order to recover and stabilize RPV level. Call from the Southeast RHR Corner Room that RHR Pump " B" lower motor bearing oil indicating sight glass is empty. Tech Specs Sections 3.5 and determine that a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO, requiring a plant shutdown, has been entered.

/ 1 IOR RRlo042AS7B IOR RRdi042AS7B IOR RRlo042AS7B rfRR-12 mfEDO6A -SRO "B "B runback 1 TS - SRO - - - - - SSISRO Drywell mfFW-08A FW-086 mfFW-08C mfCS-03A 8 Appendix D Scenario Outline Form ES-D-1 C -BOP C R-RO R-SRO IRF Recirc Pump discharge valve full open indication fails causing the Recirc Pump to to minimum flow. Insert control rods to get below MELLA C-RO C-SRO I Trip of CRD Pump B with a loss of 125 VDC Bus 1 (Inops 4 KV Bus 3 ECCS equipment).

The crew will implement ON 3159, Loss of Bus DC 1. The will review Tech Specs Sections 3.10 and 3.5 and determine that a second 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO, requiring a plant shutdown, has been entered. (STG 04) EPR Oscillations OT 31 15, Reactor Pressure Transients

-Place MPR in service. M -CREW Main Steam Line Break in the Failure of the Reactor Feedwater Pumps and Core Spray Pump A Injection Valve require lining up Condensate Pumps to restore RPV water

Retrieved from "https://kanterella.com/w/index.php?title=ML090790241&oldid=1803411"