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Issue date | Title | Topic | |
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LD-84-039, Informs of Planned Mod to C-E Control Element Assembly Guide Tube Wear Sleeve.Mod Includes Relocation of Sleeve Flare,Sleeve Expansion Over Full Length of Sleeve & Relocation of Crimp,Providing Resistance to Axial Motion | 27 July 1984 | Informs of Planned Mod to C-E Control Element Assembly Guide Tube Wear Sleeve.Mod Includes Relocation of Sleeve Flare,Sleeve Expansion Over Full Length of Sleeve & Relocation of Crimp,Providing Resistance to Axial Motion | |
LD-84-049, Forwards Response to Mechanical Engineering Branch 840424 Request for Addl Info Re Operability of Shutdown Cooling Sys Relief Valves Used on Sys 80 Std Plant.Valves in Question Will Function Under Anticipated Design Conditions | 7 September 1984 | Forwards Response to Mechanical Engineering Branch 840424 Request for Addl Info Re Operability of Shutdown Cooling Sys Relief Valves Used on Sys 80 Std Plant.Valves in Question Will Function Under Anticipated Design Conditions | |
LD-84-074, Forwards Summary Rept on Design Basis of Shutdown Cooling Sys Relief Valves for CESSAR Sys 80 & Summary Rept on Operability of Shutdown Cooling Sys Relief Valves for Palo Verde Units 1,2 & 3, Per 841109 Meeting | 13 December 1984 | Forwards Summary Rept on Design Basis of Shutdown Cooling Sys Relief Valves for CESSAR Sys 80 & Summary Rept on Operability of Shutdown Cooling Sys Relief Valves for Palo Verde Units 1,2 & 3, Per 841109 Meeting | |
LD-85-004, Forwards Palo Verde Technical Audit of Safety Analysis & Applicable CESSAR-F Analyses,Per .No Serious Technical Errors,Safety Concerns or Systematic Error Patterns found.C-E Design Process Adequate | 11 January 1985 | Forwards Palo Verde Technical Audit of Safety Analysis & Applicable CESSAR-F Analyses,Per .No Serious Technical Errors,Safety Concerns or Systematic Error Patterns found.C-E Design Process Adequate | |
LD-85-009, Forwards Proprietary & Nonproprietary Comprehensive Vibration Assessment Program for Palo Verde Nuclear Generating Station Unit 1 (Sys 80 Prototype),Evaluation of Predictions.... Proprietary Rept Withheld (Ref 10CFR2.790) | 7 March 1985 | Forwards Proprietary & Nonproprietary Comprehensive Vibration Assessment Program for Palo Verde Nuclear Generating Station Unit 1 (Sys 80 Prototype),Evaluation of Predictions.... Proprietary Rept Withheld (Ref 10CFR2.790) | |
LD-85-033, Forwards Comments on Proof & Review Tech Specs,Per 850703 Request.Concurs W/Proposed Tech Specs.Ltr from Northeast Utils to NRC & marked-up Tech Specs Encl.Responses to Questions Per Being Prepared | 18 July 1985 | Forwards Comments on Proof & Review Tech Specs,Per 850703 Request.Concurs W/Proposed Tech Specs.Ltr from Northeast Utils to NRC & marked-up Tech Specs Encl.Responses to Questions Per Being Prepared | Safe Shutdown Reactor Vessel Water Level |
LD-85-043, Forwards Nonproprietary Revs 00 to CEN-304-NP & CEN-305-NP & Proprietary Revs 00 to CEN-304-P & CEN-305-P,per NRC Request for Generic Design Specs.Proprietary Repts Withheld (Ref 10CFR2.790) | 30 August 1985 | Forwards Nonproprietary Revs 00 to CEN-304-NP & CEN-305-NP & Proprietary Revs 00 to CEN-304-P & CEN-305-P,per NRC Request for Generic Design Specs.Proprietary Repts Withheld (Ref 10CFR2.790) | |
LD-85-044, Forwards Proprietary & Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program. Proprietary Rept Withheld (Ref 10CFR2.790) | 30 August 1985 | Forwards Proprietary & Nonproprietary Rev 0 to Cpc/Ceac Software Mods for CPC Improvement Program. Proprietary Rept Withheld (Ref 10CFR2.790) | |
LD-86-012, Forwards Revs 0 to Proprietary CEN-323-P & Nonproprietary CEN-323-NP, Reload Data Block... & Revs 3 to Proprietary CEN-39(A)-P & Nonproprietary CEN-39(A)-NP, CPC Protection Algorithm.... Proprietary Repts Withheld (Ref 10CFR2.790) | 10 February 1986 | Forwards Revs 0 to Proprietary CEN-323-P & Nonproprietary CEN-323-NP, Reload Data Block... & Revs 3 to Proprietary CEN-39(A)-P & Nonproprietary CEN-39(A)-NP, CPC Protection Algorithm.... Proprietary Repts Withheld (Ref 10CFR2.790) | |
LD-86-013, Requests Clarification That NRC Review of Ref Portion of Plant Application Closed to Extent That Util Commits to CESSAR as Approved Through Final Design Approval & Amend 1 | 12 February 1986 | Requests Clarification That NRC Review of Ref Portion of Plant Application Closed to Extent That Util Commits to CESSAR as Approved Through Final Design Approval & Amend 1 | |
LD-86-024, Forwards Proprietary & Nonproprietary Rev 0 to CEN-330,Rev 01 to CEN-304 & Rev 01 to CEN-305 Re Improvement Program. Proprietary Repts Withheld (Ref 10CFR2.790).Affidavit for Withholding Repts Encl.Fee Paid | 21 May 1986 | Forwards Proprietary & Nonproprietary Rev 0 to CEN-330,Rev 01 to CEN-304 & Rev 01 to CEN-305 Re Improvement Program. Proprietary Repts Withheld (Ref 10CFR2.790).Affidavit for Withholding Repts Encl.Fee Paid | |
LD-86-034, Forwards Performance Info for C-E Supplied Nuclear Fuel for CY85 on plant-by-plant Basis,Per NRC 860618 Request.Info Includes Number of Fuel Assemblies & Fuel Rods Irradiated &/Or Discharged & Batch Average Burnups | 1 August 1986 | Forwards Performance Info for C-E Supplied Nuclear Fuel for CY85 on plant-by-plant Basis,Per NRC 860618 Request.Info Includes Number of Fuel Assemblies & Fuel Rods Irradiated &/Or Discharged & Batch Average Burnups | |
LD-86-038, Provides Info for Reactor Coolant Pump Data Bases on C-E Designed NSSS 80 for facilities.WPPSS-3 Should Be Added to Data Base | 5 September 1986 | Provides Info for Reactor Coolant Pump Data Bases on C-E Designed NSSS 80 for facilities.WPPSS-3 Should Be Added to Data Base | |
LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days | 10 April 1987 | Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days | |
LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request | 18 September 1987 | Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request | |
ML17194B730 | 30 September 1983 | Forwards Proprietary Dresden 2/3 Nuclear Generating Plant Suppression Pool Temp Response, Ei Hatch Nuclear Power Station Units 1 & 2 Suppression Pool Temp Response & Mark I 830825 Meeting Viewgraphs.Repts Withheld (Ref 10CFR2.790) | |
ML17296B286 | 11 March 1981 | Requests That Instrumentation & Control Independent Design Review Be Rescheduled at First Available Opportunity.Delays Will Have Significant Impact on Sar,Fsar & CESSAR-F Review | |
ML17297B605 | 2 July 1982 | Forwards Proprietary & Nonproprietary Comprehensive Vibration Assessment Program for Prototype Sys 80 Reactor Internals,Palo Verde Nuclear Generating Station,Unit 1. Proprietary Version Withheld (Ref 10CFR2.790) | |
ML17300A974 | 16 June 1987 | Discusses Actions Taken in Investigation of Bechtel Deficiency Rept DER 86-29 Re Cracked Reactor Coolant Inlet Nozzle on Letdown Hx.Utils Should Be Notitified to Perform Visual Exam of Inlet & Outlet Nozzles.Part 21 Related | |
ML17303A485 | 13 July 1987 | Forwards Steam Generator Tube Vibration Evaluation Program Progress Rept,Per Gw Knighton 870327 Ltr & Author 870410 Commitment.Rept Provides General Description of Program, Results to Date & Anticipated Direction of Future Efforts | Flow Induced Vibration |
ML17304B051 | 23 February 1989 | Requests That Sending of NRR Correspondence W/Util Re Plant to Recipient Continue,In Response to 890216 Ltr | |
ML17321A900 | 30 September 1985 | Notifies of Error in 10CFR50.46 LOCA Analyses Performed for Facilities.Input Error in TOODEE2 Code Used to Calculate Fuel Rod Heatup Resulted in Rod Decay Heat Power Too Low & Subsequent Underpredicted Cladding Temp.Part 21 Related | |
ML18142A048 | 7 August 1984 | Requests Proprietary Comparison to Alternate Code Calculations Be Withheld (Ref 10CFR2.790).Affidavit Encl | |
ML19324C315 | 20 February 1989 | Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies | |
ML19325E900 | 19 October 1989 | Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response | Loop seal |
ML19327A844 | 11 October 1989 | Forwards Pleadings,Motions & Orders Filed in Alchemie Reorganization Action.Alchemie Currently Preparing Reorganization Plan Which Will Serve as Framework for Future Company Business Activities | |
ML19327A851 | 5 October 1989 | Forwards Wh Arowood 890907 Ltr & Other Supplemental Info to Replace Info Previously Filed | |
ML19327B249 | 6 October 1989 | Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept. | |
ML20009G475 | 27 July 1981 | Advises That 16-cylinder PC-2.5 Engine for Marine Contract Suffered Burned Exhaust Valve Cage During Factory Tests. Specified Cages Will Be Inspected for Adequate Torquing of Holdowns Prior to Startup of Facilities | |
ML20024F099 | 24 August 1983 | Forwards Proprietary Thermocouple/Core Cooling Monitor,Vols 1 & 2. Repts Withheld (Ref 10CFR2.790) | |
ML20027B402 | 24 April 1978 | Forwards GE Program for Reactor Internals Vibration Measurement & Insp of BWR/6 Class Plants In,Response to NRC Request for Info in Item 2 of Table 1-3 of 251 & 238 NSSS Gessar Sers.Affidavit Encl | |
ML20028E148 | 14 January 1983 | Part 21 Rept Re Possible Adverse Effects of Cross Flow on Control Rod Assemblies for Facilities.Concern Not Substantial Safety Hazard.Design Change Will Be Implemented | |
ML20040H414 | 10 February 1982 | Notifies That Facilities Ref CENPD-210,Revision 3 Per 820202 Request.Info Based on Review of PSARs | |
ML20052F090 | 4 May 1982 | Informs That Addl Action Will Be Required in Order to Fully Comply W/Asme Code Requirements for Radiography of safe-end Welds.Discrepancy Will Be Resolved by re-radiographing Affected Welds | |
ML20052F519 | 6 April 1982 | Forwards Proprietary & Nonproprietary Versions of Response to NRC Questions on Improved Thermal Design Procedures. Authorizes Use of Proprietary Info by Comm Ed.Proprietary Info Withheld (Ref 10CFR2.790).Affidavit (AW-76-60) Encl | |
ML20063N435 | 16 December 1981 | Discusses Overpressure Events in Reactor Primary Sys.Impact of Transients on Structural Integrity of Reactor Vessel Evaluated.Related Info Encl | Hydrostatic |
ML20065B882 | 27 January 1983 | Part 21 Rept Re 170 Wire Tendon post-tensioning Sys.Problem Lies W/Poor Const Techniques Not Nonconforming Threads. Nonconforming Threads Not Responsible for Failures Exhibited at Job Sites.Qa Procedure Encl | |
ML20070C763 | 10 December 1982 | Part 21 Rept Re Problem W/Brown Boveri Electric,Inc Low Voltage Circuit Breakers W/Solid State Trip Devices.Units from San Onofre 2 & 3 Failed Due to long-term Degradation of Filter Capacitor C205.Suspect Trip Units Should Be Tested | |
ML20072K719 | 7 March 1983 | Forwards Evaluation of Small Break LOCA Operating Procedures & Effectiveness of Emergency Feedwater Spray for B&W-Designed Operating Nsss | |
ML20077G666 | 27 July 1983 | Part 21 Rept Re Circuit Breakers Mfg Between Nov 1981 & Feb 1982.Breakers Should Be Inspected for Broken Puffer Linkage Studs.Stud Identified as Part Number 192247A.List of Circuit Breakers for Nuclear Plants Encl | |
ML20077S179 | 1 July 1983 | FOIA Request for Structural Integrity Test Rept for Facilities | |
ML20078P485 | 28 March 1983 | Submits Further Followup Re Enchancement of Penetrameter Images on Radiographic Films.Film Reviews Completed to Date Confirm Weld Quality.Training Progress Initiated & Audits Performed | |
ML20080D963 | 20 January 1984 | Application for Withholding Rept, Snupps Steam Generator Tube Plugging Margin Evaluation (Ref 10CFR2.790) | |
ML20082S873 | 6 July 1982 | Responds to IE Bulletin 82-01 Re Associated Piping & Engineering Furnished Radiographs for Piping Welds 1/2 Inch & Less in Thickness.Smud Will Be Contacted to Return Radiographs for Review.Info Deleted | |
ML20083M844 | 11 April 1984 | Application for Withholding Proprietary Westinghouse Interconnecting Wiring Diagrams & Process Control Block Diagrams Associated W/Pressurizer Pressure Input (Ref 10CFR2.790).W/affidavit | |
ML20084N247 | 12 January 1972 | Expresses Concern Re Way Names of Vendor & Us Steel Corp, Pipe Were Used in Recent Telegrams to Util Concerning Main Steam Ejection at facility.Follow-up Telegram Showing That Failure Was Not Due to Faulty Matl Requested | |
ML20084N251 | 27 December 1971 | Expresses Concern Re Use of Name in Correspondence Concerning 711010 Main Steam Ejection at Facility.List of Recipients of Telegram Re Occurrence Requested to Complete Followup | |
ML20084V115 | 29 September 1969 | Submits Results of Investigation of RCPB Valves | |
ML20087N618 | 22 March 1984 | Application for Withholding Proprietary Response to NRC Questions on Setpoint Methodology | |
ML20088A272 | 3 April 1984 | Authorizes Use of Encl 761201 Affidavit Re Withholding Proprietary Westinghouse Info from Public Disclosure |