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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20247P807 | 4 April 1989 | Forwards Ltr in Which Concerns for Potential Significant Deficiency Under 10CFR21 Expressed | |
| ML17304B051 | 23 February 1989 | Requests That Sending of NRR Correspondence W/Util Re Plant to Recipient Continue,In Response to 890216 Ltr | |
| 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 | |
| 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 |
| 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 | |
| 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-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-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-86-024, 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-86-012, 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-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-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-85-033, 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-85-009, 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-85-004, 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 | |
| ML20111C328 | 4 January 1985 | Requests Author Addition to Correspondence List for Listed Facilities | |
| 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-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 | |
| 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) | |
| 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 | |
| ML20106B969 | 14 April 1982 | Provides Info Re Company QA Field Tests & Insps of Nuclear Code Pumps,In Response to NRC 820325 Request for Info.Encl Re QA Program Allegations Sent to Nuclear Code Customers | |
| ML20040H414 | 10 February 1982 | Notifies That Facilities Ref CENPD-210,Revision 3 Per 820202 Request.Info Based on Review of PSARs | |
| 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 | |
| ML20126B934 | 12 February 1980 | Confirms 800207 Telcon Re Failure of Valves.Forwards Part 21 Rept |