Similar Documents at Cook |
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Category:OPERATOR TRAINING/REQUALIFICATION PROGRAM
MONTHYEARML17334A3831980-02-0303 February 1980
to Operator Replacement Training Program
1980-02-03
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
[Table view] |
Text
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c A>A'cd/4 zKA.AP 9 RG~f c3~~?lane'terna~r 8~08040789'P0ygg PDR ADOCK 05000315 PDR R2/3/80
- 32.Power Distribution.
33..Peaking Factors.34.Radial Nuclear Factor.35.Axial Nuclear Factor.36.Local Nuclear Factor.37.Total Nuclear Factor.38.Neutron Production.
39.Prompt Neutrons.40.Delayed Neutrons.41.Delayed Neutron Emissions.
42.The Delayed Neutron Fraction.43.The Delayed Neutron Fraction Change Over Core Life.44.The Effective Delayed Neutron Fraction.45.Neutron Lifetime and Generation Time.46.Delayed Neutron Effects.47.Reactivity.
48.Reactor Period.49.The Power Law.50.Startup Rate.51.Doubling Time.52.The Inhour Equation.53.Reactor Control System Effects.a.Short-Term.
b.Intermediate-Term.
c.Long-Term.
Page 4 of ll Rev 1 2/3/00
~54.Typical Absorber Hater ial s.-----55.Effect of Control Poisons on the Effective Hultiplication Factor.56.Control Poison Forms.57.Black and Gray Poisons.58.Effects of Control Systems on Flux Shape.a..Control Rods.b.Soluble Poison.c.Burnable Poisons.59.Differential.Rod North.60.Integral Rod!lorth.61.Differential Boron Worth.62.The Doppler Coefficient.
63.The Hoderator Temperature Corefficient.
64.Undermoderation...
65.Overmoderation.
66.The Pressure Coefficient.
67.The Void Coefficient.
68.The Isothermal Hoderator Temperature Coefficient.
69.The Power Coefficient.
70.Calculations of Reactivity Changes.'71.Variations in the Doppler Coefficient.
72.Variations in the Hoderator Temperatur Coefficient a.Effect of Fuel Temperature Changes.b.Effect of Changes in Hoderator Density.c.Effect of Poison Density.d.Effect of Core Age.Page 5 of ll Rev I 2/3/80 73.Reactivity Defects.74.The Power.Defect.75.Neutron Competition and Shadowing.
76.Conditions Affecting Control Rod Morth.77..Coefficients and Control in a Pressurized Mater Reactor.78.Fission Product Formation.
79.'Xenon Production and Removal.80.Equilibrium Xenon..81.Startup Xenon Transients.
82.Shutdown Xenon Transients.
83.Restart Xenon Transients.
84.Power Change Xenon Transients.
85.Xenon Oscillations.
86.Equilibrium Samarium.87.Samarium Transients.
88.Core Reactivity Requirements
-Excess Reactivity.
89.Core Nuclear Reactions.
90.Fuel Depletion Effects on Reactivity.
a.U-235 Burnout.b.Fission Product Poison Buildup.c.Pu-239 Buildup.d.Burnable Poisons Depletion.
e.Total Core Life Effect.f.Refueling.
91.Other Fuel Depletion Effects.Page 6 of 11 Rev 1 2/3/80
~o~a~b.Effects on Flux.Effects on the Six Factors.c.Effects on the Effective Oelayed Neutron Fraction.d.Effects on the Reactivity Coefficients.
92.Neutron Sources.94.1/H Plots.95.Fuel Loading.96.The Approach to the Critical Condition.
97.Predictions of Criticality.
98.Physics Testing.a.Rod>lorth Measurement.
b.Coefficient Horth Measurement.
c.Reactivity Follow.99.Power Changes.100.End of Core Life.101.Reactor Coastdown.
102.Turbine Runback.103.Planned Shutdown.104.Reactor Trip.105.Shutdown Cooling Requirements.
106.Fuel Management.
107.Pefueling.
To enhance the theory phase of instruction, the trainees will participate in a training program at a research reactor.Ouring this Page 7 of 11 Rev 1 2/3/80 program they will perform experiments to exhibit and measure reactivity effects.The trainees will gain hands-on experience by performing startups arid shutdowns of the reactor.Plant systems will be taught in depth through formal classroom instruction and in-plant study.Normal, Abnormal, and Emergency Operating Procedures will be emphasized.
Controls, instrumentation, setpoints, auto-matic actions, differences between the units, system interfaces, and Technical Specifications limitations will be stressed.The systems covered are: 1.'eactor Core.2.Reactor Coolant System.3.4.Pressurizer and Pressure Relief System.I Rod Control System.5.'hemical and Volume Control System.6.Residual Heat Removal System.7~8.Excore Nuclear Instrumentation System.Incore Huclear Instrumentation System.9.Reactor Protection System.10.Emergency Core Cooling System.ll.Containment System.12.Ice Condenser System.13.Containment Spray and Hydrogen Recombiner System.14.Fuel Handling System.15.Primary Sampling System.16.Component Cooling Water System.ll.Essential Service Mater System.Page 8 of 11 Rev>2/3/80 18.19.20., t(on-Essential Service Mater System.Demineralized Mater System.Spent Fuel Pit Systems.21.Maste Disposal Vent and Drain System.22.Liquid Maste Disposal System.I~/~~23.Gaseous Maste Disposal System.24.Solid Maste Disposal System.25.Containment Ventilation System.26.Auxiliary Building Ventilation System.27.Control Room Ventilation System.28.Emergency Diesel Generator Systems.29.Auxiliary Feedwater System.30.Compressed Air System.31.Lube Oil Cleanup System.32.Secondary Sampling System.33.Secondary Chemical Feed Systems.34.Primary Mater System.35.Primary Gas System.36.Mater Fire Protection System.37.Carbon Dioxide and Halon Fire Protection System.38.Hiscellaneous Fire Protection Systems.39.Plant Computer.40.Radiation thoni toring System.41.Portable Radiation Instruments.
42.Steam Generator and Steam Generator Slowdown System.43.Main Steam System.Paqe 9 of 11 Rev~2/3/80 45.Auxiliary Steam System..46.Plant Heating Boiler.47.Main Turbine and Control System.48.Steam Seal Supply and Exhaust System.49.Main Turbine Lube Oil System.50.Bleed Steam System.51.Moisture Separator/Reheater and Feedwater Heater Drains.52.Circulating Water System.53.Chlorination System.54.Miscellaneous Sealing and Cooling Water System.55.Vacuum Priming System.56.Condensate System.57.Feedwater System.58.Steam Generator Level Control System.59.Steam Dump System.60.Main Generator and Auxiliary Systems.61.4160 KY Electrical Distribution.
62.600Y AC Electrical Distribution.
63.120Y AC Electrical Distribution.
64.250V DC Electrical Distribution.
The trainees vIill be instructed in the Plant Technical Specif-cations Safety Limits, Limiting Safety System Settings, Limiting Conditions for Operation and Bases for these limits.They will be held responsible for knowing all Action Statements of one hour or less.Page 10 of 11 Rev>2/3/80 Further intensive training in Instrumentation and Control systems C and in Radiation Control and Protection will be given.Periodic written and oral examinations will be given throughout the program to evaluate trainee performance and to prepare them for taking the NRC written and oral examinations.
Plant operating characteristics and responses to transients will be taught.Accident diagnosis and corrective actions will be emphasized.
The trainees will attend a simulator training program where they will perform plant evolutions and casualties.
An NRC approved simulator certification program will be utilized for the demonstration portion of the Reactor Operator licensing examination at this time.Simulated NRC written and oral examinations will'e administered to the license candidates to audit their preparation for the NRC Reactor 0)er ator licensing examinations.
This audit will be an input in determining which candidates will be recommended for the NRC examination and will be used to identify weak areas needing further study.After the audit examination, a'minimum two week review series, will be conducted in final preparation for the NRC examination.
Meak areas and overall plant operation will be stressed, Page ll of 11 Rey I 2/3/80~~'ve'%A-~%N~'Ll*Sly,"'>>++~i".~~~~A'.i~~"<<~ir~>>*-
~~r-2070 Attachment
- -5 No.of Hours to the nearest l/10 hour Date Shift REACTI~I iT.'lAHLPULATIGH Control Board Time To be comoleted by Hot License candidates (Replacement Reac.or Operator Students}working under instruction in the Control Roam, or by any individual Auxiliary equipment operator that is working under instruction in the Control Room.Name-Prin.Signature Control lhnipulations, Oral"-xams (Mai kthrough}, etc.Be Spe"ific
- ~Iame-Print (RG,SRO)Slgnatul e'"-r~ard im.diately to the Training Depar=..ent acn and every ime a student wor4s in he Control Room.page l of l Rev 1 2/3/80>>
