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| Issue date | Title | Topic | |
|---|---|---|---|
| LD-90-075, Forwards Amend H to CESSAR - Design Certification | 3 October 1990 | Forwards Amend H to CESSAR - Design Certification | Probabilistic Risk Assessment |
| LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per | 28 August 1990 | Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per | |
| LD-90-046, Forwards Addl Copies of Amend G to CESSAR-DC | 12 July 1990 | Forwards Addl Copies of Amend G to CESSAR-DC | |
| ML20044A553 | 18 June 1990 | Advises That Licensee Will Submit Application for Final Design Approval & Design Certification of Process Inherent Ultimate Safety Reactor in FY92 & That Safe Integral Reactor Anticipated in FY93,in Addition to Sys 80+ Under Review | |
| ML20042E900 | 30 April 1990 | Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document | |
| ML20006A720 | 5 January 1990 | Requests That Consolidated Financial Statements Submitted to NRC by 891121 Ltr Re Indirect Transfer of C-E Licenses Be Treated as Confidential,Per 10CFR2.790.Supporting Affidavit Encl | |
| ML20011D515 | 22 December 1989 | Forwards Amend F to C-E Std SAR - Design Certification (CESSAR-DC). | Probabilistic Risk Assessment |
| ML19324B681 | 30 October 1989 | Forwards Response to Request for Addl Info Re C-E QA Program & CESSAR-DC,Chapter 17,proposed Rev to CESSAR-DC & Rev 5 to CENPD-210, QA Program:Description of Nuclear Power Businesses QA Program. | |
| LD-89-107, Forwards Addl Info Re CESSAR-DC Chapter 7 | 28 September 1989 | Forwards Addl Info Re CESSAR-DC Chapter 7 | Safe Shutdown Fire Barrier |
| LD-89-092, Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification | 17 August 1989 | Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification | Probabilistic Risk Assessment |
| LD-89-091, Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys | 16 August 1989 | Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys | Internal Flooding Earthquake |
| LD-89-035, Forwards Vols 1-17,consisting of Chapters 1-18,to CESSAR Design Certification, for Approval,Per 10CFR52 | 30 March 1989 | Forwards Vols 1-17,consisting of Chapters 1-18,to CESSAR Design Certification, for Approval,Per 10CFR52 | |
| LD-89-033, Forwards Design Certification Licensing Review Basis, for Review & Concurrence | 30 March 1989 | Forwards Design Certification Licensing Review Basis, for Review & Concurrence | Earthquake |
| LD-89-029, Forwards Vol Viii to DOE/ID-10216, Mods for Development of MAAP-DOE Code:Vol Viii:Resolution of Outstanding Nuclear Fission Product Aerosol Transport & Deposition Issues Wbs 3.4.2, Per 881011 Request | 17 March 1989 | Forwards Vol Viii to DOE/ID-10216, Mods for Development of MAAP-DOE Code:Vol Viii:Resolution of Outstanding Nuclear Fission Product Aerosol Transport & Deposition Issues Wbs 3.4.2, Per 881011 Request | |
| LD-89-028, Forwards Amend E to C-E Std SAR Group E2 Re Design Certification.Summary of Revs Also Encl | 15 March 1989 | Forwards Amend E to C-E Std SAR Group E2 Re Design Certification.Summary of Revs Also Encl | Safe Shutdown Boric Acid Shutdown Margin High Radiation Area Ultimate heat sink Non-Destructive Examination Anticipated operational occurrence Safe Shutdown Earthquake Hydrostatic Probabilistic Risk Assessment Coatings Operating Basis Earthquake Nondestructive Examination Emergency Lighting Incorporated by reference Finite Element Analysis Earthquake Power Operated Valves Turbine Missile Pressure Boundary Leakage Accidental discharge Power change Flow Induced Vibration Unidentified leakage Unidentified leak |
| LD-88-132, Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review | 11 November 1988 | Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review | Ultimate heat sink Probabilistic Risk Assessment Chernobyl Backfit |
| LD-88-128, Forwards QA Program in Response to NRC Request for Addl Info Re Chapter 17,CESSAR-DC QA | 4 November 1988 | Forwards QA Program in Response to NRC Request for Addl Info Re Chapter 17,CESSAR-DC QA | |
| LD-88-119, Responds to NRC Request for Addl Info on Chapter 17 of CESSAR-DC.NRC Question 260.2 Incorporated in CENPD-210,Rev 5 as Part of Sections III.1,III.3 & Table III-1 | 21 October 1988 | Responds to NRC Request for Addl Info on Chapter 17 of CESSAR-DC.NRC Question 260.2 Incorporated in CENPD-210,Rev 5 as Part of Sections III.1,III.3 & Table III-1 | |
| LD-88-106, Forwards Amend D to CESSAR Fsar,Including Revs to Chapters 2-7 & 18.Technical Review Should Be Allowed to Proceed Unencumbered Pending Settlement of Dispute Re Fees | 30 September 1988 | Forwards Amend D to CESSAR Fsar,Including Revs to Chapters 2-7 & 18.Technical Review Should Be Allowed to Proceed Unencumbered Pending Settlement of Dispute Re Fees | Safe Shutdown |
| LD-88-099, Responds to NRC Request for Addl Info Re Chapters 5 & 9 of CESSAR-DC Re Steam Generator Secondary Water Chemistry, Reactor Coolant Water Chemistry,Fire Protection Sys,Letdown Purification Line & Hydrogen Ignition | 20 September 1988 | Responds to NRC Request for Addl Info Re Chapters 5 & 9 of CESSAR-DC Re Steam Generator Secondary Water Chemistry, Reactor Coolant Water Chemistry,Fire Protection Sys,Letdown Purification Line & Hydrogen Ignition | Coatings |
| LD-88-091, Forwards Summary of Sabotage Protection Considerations & Draft Requirements for Sabotage Design from EPRI Advanced LWR Requirements Document,Per NRC .Basis for Program Listed | 14 September 1988 | Forwards Summary of Sabotage Protection Considerations & Draft Requirements for Sabotage Design from EPRI Advanced LWR Requirements Document,Per NRC .Basis for Program Listed | |
| LD-88-089, Forwards Addl Info Re CESSAR-DC,Chapter 4,in Response to NRC 880628 Request | 9 September 1988 | Forwards Addl Info Re CESSAR-DC,Chapter 4,in Response to NRC 880628 Request | |
| LD-88-088, Provides Proposed Resolution for Single Issue of Advanced Reactor Severe Accident Program Topic Paper Set 4, Essential Equipment Performance | 9 September 1988 | Provides Proposed Resolution for Single Issue of Advanced Reactor Severe Accident Program Topic Paper Set 4, Essential Equipment Performance | Probabilistic Risk Assessment |
| ML20151Q858 | 2 August 1988 | Informs That Vendor Finalizing Review & Anticipates That Rev 5 to CENPD-210 Will Be Transmitted by Sept 1988.Road Map Will Also Be Submitted to Identify Remaining QA Questions | |
| LD-88-069, Informs of Finalizing Review of QA Program Description of Rev 5 to CESSAR Topical Rept CENPD-210 & Anticipates Transmitting Review to NRC by Third Quarter 1988.Submittal Will Address Remaining QA Questions in Road Map | 2 August 1988 | Informs of Finalizing Review of QA Program Description of Rev 5 to CESSAR Topical Rept CENPD-210 & Anticipates Transmitting Review to NRC by Third Quarter 1988.Submittal Will Address Remaining QA Questions in Road Map | |
| LD-88-068, Forwards Response to Request for Addl Info Re CESSAR-DC Chapters 1 & 5 Re Sabotage Protection,Per | 1 August 1988 | Forwards Response to Request for Addl Info Re CESSAR-DC Chapters 1 & 5 Re Sabotage Protection,Per | Safe Shutdown |
| LD-88-066, Forwards DOE Advanced Reactor Severe Accident Program Proposed Resolutions for Severe Accident Issues,Topic Set 3. Resolutions to Listed Items Will Be Adopted in Development of Sys 80+ Std Design | 29 July 1988 | Forwards DOE Advanced Reactor Severe Accident Program Proposed Resolutions for Severe Accident Issues,Topic Set 3. Resolutions to Listed Items Will Be Adopted in Development of Sys 80+ Std Design | Safe Shutdown High winds Mission time Tornado Missile Internal Flooding Probabilistic Risk Assessment Design basis earthquake Earthquake Turbine Missile Backfit |
| ML20150E726 | 1 July 1988 | Forwards Flow Distribution & Tube Vibration:Evaluation of Sys 80 Steam Generator Tube Lane/Economizer Corner Region, in Support of C-E 870918 Request That Steam Generator Tube Vibration Issue Be Closed | |
| LD-88-047, Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl | 30 June 1988 | Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl | Safe Shutdown |
| LD-88-046, Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch | 30 June 1988 | Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch | Safe Shutdown Probabilistic Risk Assessment Power Operated Valves |
| LD-88-042, Provides Proposed Resolutions to Remaining Two Issues Committed to in Re Direct Containment Heating (Idcor Issue 8) & Debris Coolability (Idcor Issue 10).C-E Plans to Adopt 14 Resolutions Previously Submitted | 17 June 1988 | Provides Proposed Resolutions to Remaining Two Issues Committed to in Re Direct Containment Heating (Idcor Issue 8) & Debris Coolability (Idcor Issue 10).C-E Plans to Adopt 14 Resolutions Previously Submitted | Ultimate heat sink |
| LD-88-039, Forwards Addl Info Re Chapters 1 & 10 to CESSAR-DC,per NRC 880311 Request | 6 June 1988 | Forwards Addl Info Re Chapters 1 & 10 to CESSAR-DC,per NRC 880311 Request | |
| LD-88-038, Provides Proposed Resolutions for Four of Six Issues Which Make Up Topic Paper Set 2,including in-vessel Hydrogen Generation,Core Melt Progression & Vessel Failure & Hydrogen Ignition & Burning.Remaining Issues Submitted in 30 Days | 6 June 1988 | Provides Proposed Resolutions for Four of Six Issues Which Make Up Topic Paper Set 2,including in-vessel Hydrogen Generation,Core Melt Progression & Vessel Failure & Hydrogen Ignition & Burning.Remaining Issues Submitted in 30 Days | Probabilistic Risk Assessment |
| LD-88-034, Provides Addl Info on CESSAR-DC Chapter 10 Re Secondary Water Chemistry,Per NRC 880225 request.CESSAR-DC Section 10.3.5.1 Revised to Make Clear That C-E Secondary Water Chemistry Program Includes Immediate Shutdown Limits | 25 May 1988 | Provides Addl Info on CESSAR-DC Chapter 10 Re Secondary Water Chemistry,Per NRC 880225 request.CESSAR-DC Section 10.3.5.1 Revised to Make Clear That C-E Secondary Water Chemistry Program Includes Immediate Shutdown Limits | Safe Shutdown Earthquake |
| LD-88-033, Forwards Response to NRC 880226 Request for Addl Info on Chapter 17 to Rev 4 to Topical Rept CENPD-210A, QA Program, Including Revs to C-E 871130 & 880411 Responses | 25 May 1988 | Forwards Response to NRC 880226 Request for Addl Info on Chapter 17 to Rev 4 to Topical Rept CENPD-210A, QA Program, Including Revs to C-E 871130 & 880411 Responses | Ultimate heat sink |
| LD-88-026, Forwards Draft Revs to C-E Chapters 1,4,5 & 9 to C-E Std Sar.Meeting to Resolve Issues Re Schedule & Composition of Submittals as Part of Draft Licensing Review Bases & Related Issues,Requested | 11 April 1988 | Forwards Draft Revs to C-E Chapters 1,4,5 & 9 to C-E Std Sar.Meeting to Resolve Issues Re Schedule & Composition of Submittals as Part of Draft Licensing Review Bases & Related Issues,Requested | Safe Shutdown Loop seal Ultimate heat sink Incorporated by reference |
| LD-88-021, Forwards Response to NRC 871208 Request for Addl Info Re Reg Guides That Appear in CESSAR-DC,QA.Suggest That Meeting W/Nrc Staff Be Scheduled to Allow Overview Program Changes | 22 March 1988 | Forwards Response to NRC 871208 Request for Addl Info Re Reg Guides That Appear in CESSAR-DC,QA.Suggest That Meeting W/Nrc Staff Be Scheduled to Allow Overview Program Changes | |
| LD-88-019, Forwards Addl Info Re Chemical & Vol Control Sys for Sys 80+TM Std Design,Per 871217 Request.Proposed Rev to C-E Std SAR, Design Certification Also Encl | 18 March 1988 | Forwards Addl Info Re Chemical & Vol Control Sys for Sys 80+TM Std Design,Per 871217 Request.Proposed Rev to C-E Std SAR, Design Certification Also Encl | Safe Shutdown Shutdown Margin Fuel cladding |
| LD-88-020, Responds to NRC Request for Addl Info Re Chapter 1 Concerning Safeguards.Proposed Revision to C-E Engineering Std SAR & Responses to Specific Questions Also Encl | 18 March 1988 | Responds to NRC Request for Addl Info Re Chapter 1 Concerning Safeguards.Proposed Revision to C-E Engineering Std SAR & Responses to Specific Questions Also Encl | Probabilistic Risk Assessment |
| ML20149M617 | 16 February 1988 | Forwards Proprietary & Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design, Per NRC Request.Proprietary Rept Withheld (Ref 10CFR2.790) | Probabilistic Risk Assessment |
| LD-88-008, Forwards Proprietary Base Line Level 1 PRA for Sys 80r NSSS Design. Rept Presents Methodology & Results of Sys 80 PRA to Be Used for Evaluation of Design trade-offs for Sys 80+ Std Design | 22 January 1988 | Forwards Proprietary Base Line Level 1 PRA for Sys 80r NSSS Design. Rept Presents Methodology & Results of Sys 80 PRA to Be Used for Evaluation of Design trade-offs for Sys 80+ Std Design | Probabilistic Risk Assessment |
| ML20148D324 | 19 January 1988 | Forwards Input to Licensing Review Bases Document Being Developed for CESSAR - Design Certification Originally Transmitted on 870702.Encl C-E Sys 80+TM Std Design Design Certification Bases Addresses NRC 871207 Comments | |
| LD-87-068, Forwards Proposed Amend to CESSAR FSAR Describing Sys 80 Plus Design.Mods Comply W/Standardization & Severe Accident Policy Statements & Results in Upgrading of Final Design Approval FDA-2.Clarification of NRC Fees Requested | 30 November 1987 | Forwards Proposed Amend to CESSAR FSAR Describing Sys 80 Plus Design.Mods Comply W/Standardization & Severe Accident Policy Statements & Results in Upgrading of Final Design Approval FDA-2.Clarification of NRC Fees Requested | |
| LD-87-053, Forwards Revised Steam Generator Tube Rupture Analysis for Fsar.Rev Incorporates Revised Analysis Using Reactor Coolant Gas Vent Sys for Depressurization Purposes | 18 September 1987 | Forwards Revised Steam Generator Tube Rupture Analysis for Fsar.Rev Incorporates Revised Analysis Using Reactor Coolant Gas Vent Sys for Depressurization Purposes | Shutdown Margin |
| LD-87-050, Requests NRC Adoption of Proposed Docketing Process for Forthcoming Revs to C-E Std SAR | 18 September 1987 | Requests NRC Adoption of Proposed Docketing Process for Forthcoming Revs to C-E Std SAR | Backfit |
| LD-87-052, Requests That Steam Generator Tube Vibration Issue Be Closed on C-E Std SAR - FSAR (CESSAR-F) Docket.Any Potential Design Improvements for Future Steam Generators Can Be Reviewed as Part of Review of Improved Design Sys 80+ | 18 September 1987 | Requests That Steam Generator Tube Vibration Issue Be Closed on C-E Std SAR - FSAR (CESSAR-F) Docket.Any Potential Design Improvements for Future Steam Generators Can Be Reviewed as Part of Review of Improved Design Sys 80+ | |
| LD-87-051, Provides Design Info to Support Conclusion That Sys 80R in Compliance W/Atws Rule.Requests Closure of Issuance on CESSAR - F Docket.Response to NRC Evaluation of CEN-315,Sys 80R Encl | 18 September 1987 | Provides Design Info to Support Conclusion That Sys 80R in Compliance W/Atws Rule.Requests Closure of Issuance on CESSAR - F Docket.Response to NRC Evaluation of CEN-315,Sys 80R Encl | |
| LD-87-054, Forwards Amend 12 to CESSAR Fsar,Modifying Sys 80R Design. Enhanced & Expanded Sys 80 Design Will Be Called Sys 80 Tm | 18 September 1987 | Forwards Amend 12 to CESSAR Fsar,Modifying Sys 80R Design. Enhanced & Expanded Sys 80 Design Will Be Called Sys 80 Tm | |
| LD-87-021, Provides Formal Description of C-E Efforts to Advance Sys 80R PWR Design & Advises That Sys 80 Design Including Consideration of EPRI Advanced LWR Design Requirements Document Revised | 23 April 1987 | Provides Formal Description of C-E Efforts to Advance Sys 80R PWR Design & Advises That Sys 80 Design Including Consideration of EPRI Advanced LWR Design Requirements Document Revised | |
| 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 |