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 Issue dateTitleTopic
ML20059J28310 September 1990Forwards Updated Operator Licensing Exam Schedule for FY91, FY92,FY93 & FY94,per Generic Ltrs 90-07 & 89-12
ML20059D98328 August 1990Forwards fitness-for-duty Program Performance Data for 900103-0630,per 10CFR26.71.NRC Review of Data Will Provide Realization That Positive Testing Rate Extremely Low & Limited to pre-access Testing PopulationFitness for Duty
BVY-90-087, Forwards Addl Info on Use of RELAP5YA Program for LOCA Analyses.Proprietary Encl Withheld28 August 1990Forwards Addl Info on Use of RELAP5YA Program for LOCA Analyses.Proprietary Encl Withheld
BVY-90-086, Responds to NRC Re Violations Noted in Insp Rept 50-271/90-06.Corrective Actions:Incident Rept Initiated & All Required Locking Devices in Place by 90070624 August 1990Responds to NRC Re Violations Noted in Insp Rept 50-271/90-06.Corrective Actions:Incident Rept Initiated & All Required Locking Devices in Place by 900706
ML20059F66822 August 1990Comments on Review of Amend 115 to License DPR-28,including Safety Evaluation.Requests Explanation of Statement in NRC Re How NRC Considers Comments & What Resolution Could Be for Each Util Comment in
BVY-90-085, Informs That Sys Testing & Operator Training Successfully Completed & SPDS Declared Operable on 900813.Util Intends to Operate SPDS in Parallel W/Original Honeywell Gepac Plant Computer Until mid-Nov 199015 August 1990Informs That Sys Testing & Operator Training Successfully Completed & SPDS Declared Operable on 900813.Util Intends to Operate SPDS in Parallel W/Original Honeywell Gepac Plant Computer Until mid-Nov 1990
BVY-90-084, Notifies NRC of Intentions to Install Test Fuel Assemblies & Test Control Blades During Cycle 15 Refueling Outage in Sept 199024 July 1990Notifies NRC of Intentions to Install Test Fuel Assemblies & Test Control Blades During Cycle 15 Refueling Outage in Sept 1990Shutdown Margin
BVY-90-082, Informs That Effective 900723 Facility Implemented Rev 4 of Procedure Generating Package & Corresponding Revs to Eops. Revs Developed Per Rev 4 of BWR Owners Group Emergency Procedure Guidelines24 July 1990Informs That Effective 900723 Facility Implemented Rev 4 of Procedure Generating Package & Corresponding Revs to Eops. Revs Developed Per Rev 4 of BWR Owners Group Emergency Procedure Guidelines
BVY-90-071, Forwards Rev 2 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)20 July 1990Forwards Rev 2 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21)
BVY-90-078, Forwards List of Refs for Proposed Change 161 to Facility OL & Tech Specs17 July 1990Forwards List of Refs for Proposed Change 161 to Facility OL & Tech Specs
BVY-90-072, Forwards Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989,Including Annual Radiological Impact on Man for 198927 June 1990Forwards Supplemental Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters 1989,Including Annual Radiological Impact on Man for 1989
ML20043G43515 June 1990Requests Temporary Waiver of Compliance from Tech Spec Requirements for Limiting Conditions for Operation for Certain post-accident Monitoring Instrumentation Listed in Tech Spec Table 3.2.6.Parameters Listed
ML20043E4018 June 1990Responds to Second Request for Addl Info on Use of RELAP5YA. Explanation Re Why More Accurate View Factor Calculation Not Included in Huxy Code Addressed
ML20043C6131 June 1990Forwards YAEC-1659-A, Simulate-3 Validation & Verification.
ML20043C5991 June 1990Forwards Accepted Version of YAEC-1683-A, MICBURN-3/ CASMO-3/TABLES-3/SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 Through 13.
ML20043C48230 May 1990Informs of Three Organizational Changes That Will Become Effective on 900601.WP Murphy,Jp Pelletier & DA Reid Will Be Senior Vice President of Operations,Newly Created Vice President of Engineering & Plant Manager,Respectively
ML20043B75623 May 1990Informs That Util Intends to Utilize Relationship Between Frosstey & FROSSTEY-2 to Support Cycle 15 Calculations.Nrc Approval of FROSSTEY-2 Needed by Aug 1990 for LOCA Analysis Program
ML20043B64817 May 1990Forwards Rev 19 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)
BVY-90-058, Forwards Public Version of Vermont Yankee Nuclear Power Station Emergency Response Preparedness Exercise 1990. Exercise Scenario Package Includes All Info Pertinent to Performance of Exercise Scheduled for 90071817 May 1990Forwards Public Version of Vermont Yankee Nuclear Power Station Emergency Response Preparedness Exercise 1990. Exercise Scenario Package Includes All Info Pertinent to Performance of Exercise Scheduled for 900718
ML20042G90610 May 1990Forwards Proprietary Supplemental Info to 900419 Response to NRC 900309 Ltr Re FROSSTEY-2 Fuel Performance Code.Info Withheld
ML20042F6474 May 1990Ack That NRC Will Issue Supplementary Info to NRC 900307 Request for Installation of Neutron Flux Monitoring Instrumentation That Conforms to Requirements of Reg Guide 1.97 & 10CFR50.49 at Plant
ML20042E72923 April 1990Forwards Pages Omitted from 900314 Revs 16-18 to Physical Security Plan.Revs Withheld
ML20012F35130 March 1990Provides Supplemental Response to Station Blackout Rule (10CFR50.63).Util Will Use Alternate Ac Power Source Available within 10 Minutes of Onset of Station Blackout to Meet Requirements of Station Blackout RuleSafe Shutdown
ML20012D03019 March 1990Forwards Response to Generic Ltr 89-19 Re Resolution of USI A-47.Feedwater Sys Trip Relays,Interfacing W/Feedwater Pump Control Circuitry,Powered from Supplies Originating from safety-related Dc Sources
ML20012D02416 March 1990Forwards Supplemental Info Re Feedwater Check Valve V28B Flaws Evaluation,Per NRC Request.Util Remains Committed to Replacement of Subj Valve During Upcoming 1990 Refueling OutageLiquid penetrant
ML20012C63815 March 1990Forwards Vermont Yankee Nuclear Power Corp Financial Statements 891231,1988 & 1987.
ML20012C60715 March 1990Forwards Method for Generation of One-Dimensional Kinetics Data for RETRAN-02, Per NUREG-0393 & 891211 Request
ML20012B8319 March 1990Forwards Proprietary Vermont Yankee Evaluation Model Sample Problem 0.7 Ft(2) Break in Recirculation Discharge Loop, in Response to 900208 Telcon.Rept Withheld (Ref 10CFR2.790)
ML20012B6139 March 1990Informs of Schedular Changes Made W/Regard to Plant Licensed Operator Requalification Training Program
ML20006E88715 February 1990Provides NRC W/Results of Licensee Review of Design Bases & Operability Status of torus-to-reactor Bldg Vacuum Breakers
ML20011E6795 February 1990Responds to Weaknesses Noted in SALP Rept 50-271/88-99 for Jul 1988 to Sept 1989.Implementation of Emergency Response Facility Info Sys Nearing Completion & Remaining Safety Class Vendor Manuals Will Be Completed During 1990Systematic Assessment of Licensee Performance
Fire Protection Program
ML20006D1572 February 1990Responds to 891226 Request for Addl Info Re YAEC-1683 on MICBURN-3/CASMO-3/TABLES-3/SIMULATE-3 Benchmarking.Hot Eigenvalue Std Deviation on Table 5.7 of YAEC-1683 Reduced to 0.00098 w/SIMULATE-3Shutdown Margin
ML20006B13522 January 1990Forwards Responses to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Establishment of Program Revs Prior to Startup from Next Refueling Outage, Scheduled for Fall 1990,plannedUltimate heat sink
Coatings
Zebra Mussel
Biofouling
ML20006A44416 January 1990Forwards Revised Page 127 of Tech Specs to Clarify Proposed Change 134, Rev of Pressure Suppression - Reactor Bldg Vacuum Breaker Sys Operability Requirements. Change Involves Adoption of Language Consistent W/Bwr STS
ML19354E80016 January 1990Forwards Addl Info Re Testing of Cable Vault C02 Suppression Sys During 891031-1102,per NRC 890518 & 0821 Requests.Encl Final Test Rept Demonstrates That Carbon Dioxide Sys Will Satisfy Design Bases for Greater than 10 Minutes in RoomFire Watch
ML20005G08410 January 1990Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of high-hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar DesignAnchor Darling
ML20005E8202 January 1990Forwards Minutes of NRC 890907 Meeting W/Util in Rockville,Md Re Util LOCA Analysis Program.List of Attendees Also Encl
ML20005F0552 January 1990Informs That Util Has Implemented Fitness for Duty Program, in Compliance w/10CFR26Fitness for Duty
ML20005E35328 December 1989Forwards Response to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & Surveillance.Util Intends to Extend Existing IE Bulletin 85-003 Program to Cover motor- Operated Valves within Scope of Ltr
ML20005E31928 December 1989Responds to Violations Noted in Insp Rept 50-271/89-17 on 890906-1016.Corrective Actions:Plant Procedures Revised & Addl Meetings Between Plant Manager,Dept Supervisors & Personnel to Take Place
ML19332G17912 December 1989Forwards Rev 0 to Vermont Yankee Nuclear Power Station Cycle 14 Core Operating Limits Rept.
ML19332F27830 November 1989Forwards Rev 1 to YAEC-1693, Application of One-Dimensional Kenetics to BWR Transient Analysis Methods, Per 891106 Ltr.Rept Presents Methodology,Verification & Justification for Application of RETRAN-02 One Dimensional Option
ML19332E35129 November 1989Forwards Annual Cashflow Statements for 1989 as Evidence of Util Maint of Approved Guarantee,Per Requirements of 10CFR140.21 Re Licensee Guarantees of Payment of Deferred Premiums
ML19332E52828 November 1989Requests Removal of Change B to Proposed Change 148 Re Rev to Pages 5b & 6a Correcting Administrative Error in Tech Spec 2.1
ML19332D38022 November 1989Responds to NRC Generic Ltr 89-21 Re Request for Info Re Status of Implementation of USI Requirements.Encl Table Details Implementation Status for USIs for Which Final Technical Resolution Achieved
ML19324C15010 November 1989Responds to NRC Bulletin 88-010,Suppl 1 Re Molded Case Circuit Breakers.Program Initiated to Ensure That Breakers Can Perform Safety Functions
ML19324C2206 November 1989Requests Change in Review & Approval Basis from Facility Specific to Generic Because Methods Described in YAEC-1693 & YAEC-1694 Applicable to All BWRs
ML19325F0266 November 1989Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Util Has Evaluated Listed Considerations,Including Safe Standoff Distances for Vital Equipment
ML19324B74330 October 1989Responds to Generic Ltr 89-16 Re Installation of Hardened Wetwell Vent.Util Expects to Establish Specific Design Criteria to Install Enhanced Containment Overpressure Protection Capability by End of 1992 Refueling Outage
ML19324B84830 October 1989Provides NRC W/Test Acceptance Criteria for Alternate Test of CO2 Suppression Sys,Per 891025 Meeting.Ability to Contain CO2 at Appropriate Concentration for Required Duration,As Well as Ability to Withstand Dynamics of Discharge,Verified