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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20072U2211991-04-12012 April 1991 Forwards Response to NRC 901221 Request for Addl Info Re Ssar for Design Certification (CESSAR-DC) LD-91-014, Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per1991-03-26026 March 1991 Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per ML20029C1001991-03-15015 March 1991 Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC ML20029C0141991-03-15015 March 1991 Forwards Response to NRC 890119 Request for Addl Info to Enable NRC to Continue Review of Cessar - Design Certification (CESSAR-DC) LD-91-010, Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC1991-03-0404 March 1991 Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC ML20029B6491991-03-0404 March 1991 Forwards Amend 1 to Cessar - Design Certification (CESSAR-DC). LD-91-006, Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes1991-01-30030 January 1991 Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes LD-90-097, Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design1990-12-21021 December 1990 Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design LD-90-075, Forwards Amend H to CESSAR - Design Certification1990-10-0303 October 1990 Forwards Amend H to CESSAR - Design Certification LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per1990-08-28028 August 1990 Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per LD-90-046, Forwards Addl Copies of Amend G to CESSAR-DC1990-07-12012 July 1990 Forwards Addl Copies of Amend G to CESSAR-DC ML20044A5531990-06-18018 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 ML20042E9001990-04-30030 April 1990 Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document ML20011E2041990-01-25025 January 1990 Forwards Response to 881216 Request for Addl Info Re CESSAR-DC,Chapters 3,4,5 & 6 Re Turbine Missiles,Control Element Drive Structural Matls,Cleaning & Contamination Protection Procedures & Reactor Internals Matls ML20006A7201990-01-0505 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 ML20011D5151989-12-22022 December 1989 Forwards Amend F to C-E Std SAR - Design Certification (CESSAR-DC). ML19324B6811989-10-30030 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 71989-09-28028 September 1989 Forwards Addl Info Re CESSAR-DC Chapter 7 LD-89-092, Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification1989-08-17017 August 1989 Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification LD-89-091, Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys1989-08-16016 August 1989 Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys ML20246A2261989-04-28028 April 1989 Forwards Sser Re Steam Generator Tube Vibration for CESSAR Sys 80 Design.Concurs W/Licensee That Adequate Steam Generator Tube Integrity Can Be Assured at Each Plant Through Appropriate Program of Preventive Tube Plugging LD-89-035, Forwards Vols 1-17,consisting of Chapters 1-18,to CESSAR Design Certification, for Approval,Per 10CFR521989-03-30030 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 & Concurrence1989-03-30030 March 1989 Forwards Design Certification Licensing Review Basis, for Review & Concurrence 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 Request1989-03-17017 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 Encl1989-03-15015 March 1989 Forwards Amend E to C-E Std SAR Group E2 Re Design Certification.Summary of Revs Also Encl LD-88-132, Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review1988-11-11011 November 1988 Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review LD-88-128, Forwards QA Program in Response to NRC Request for Addl Info Re Chapter 17,CESSAR-DC QA1988-11-0404 November 1988 Forwards QA Program in Response to NRC Request for Addl Info Re Chapter 17,CESSAR-DC QA ML20195D2251988-11-0101 November 1988 Forwards Request for Addl Info Re Amend C of Chapters 5,6 & 10 of CESSAR-DC,Sys 80+.Info Requested within 90 Days of Ltr Receipt ML20205N4851988-10-28028 October 1988 Forwards Request for Addl Info Re Chapter 5,Amend C to CESSAR-DC,Sys 80+ on Steam Generators.Info Needed by 881230 ML20195B9011988-10-26026 October 1988 Forwards Request for Addl Info Re 880930 Submittal of Amend D to Chapters 4,5,6 & 10 of CESSAR-DC,Sys 80+.Info Requested within 90 Days from Receipt of Ltr 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-11988-10-21021 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 Fees1988-09-30030 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 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 Ignition1988-09-20020 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 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 Listed1988-09-14014 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 ML20154K0031988-09-12012 September 1988 Responds to Comments & Questions Re Regulatory Trends in Us & Republic of Korea.C-E Will Pursue Design Certification & Will Revise Sys 80 Std Design to Meet Requirements of NRC Severe Accident & Standardization Policy Statements ML20154K0211988-09-12012 September 1988 Submits Questions from South Korean Engineers Re Value of Design Certification Program for C-E Sys 80 & Sys 80 Plus Designs LD-88-089, Forwards Addl Info Re CESSAR-DC,Chapter 4,in Response to NRC 880628 Request1988-09-0909 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 Performance1988-09-0909 September 1988 Provides Proposed Resolution for Single Issue of Advanced Reactor Severe Accident Program Topic Paper Set 4, Essential Equipment Performance ML20151N3441988-08-0303 August 1988 Forwards Request for Addl Info Re Chapter 9, Auxiliary Sys, & Chapter 5, RCS, CESSAR-DC,Sys 80+ in Order to Continue Review of Amend B ML20151R0281988-08-0202 August 1988 Discusses QA for CESSAR-DC,Sys 80+ & Significant Points Made Listed ML20151Q8581988-08-0202 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 Map1988-08-0202 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,Per1988-08-0101 August 1988 Forwards Response to Request for Addl Info Re CESSAR-DC Chapters 1 & 5 Re Sabotage Protection,Per 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 Design1988-07-29029 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 LD-88-055, Forwards Revised Design Certification Licensing Review Bases1988-07-15015 July 1988 Forwards Revised Design Certification Licensing Review Bases ML20150E7261988-07-0101 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 Encl1988-06-30030 June 1988 Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl LD-88-046, Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch1988-06-30030 June 1988 Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch ML20153B1411988-06-28028 June 1988 Requests Addl Info Re Amend B of Chapters 5 & 9 of CESSAR-DC,Sys 80+ for Review Completion ML20153B1281988-06-28028 June 1988 Forwards Request for Addl Info Re Amend B of Chapters 4 & 5 of CESSAR-DC,Sys 80+,transmitted by .Receipt of Info within 90 Days of Ltr Date Requested 1991-04-12
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20072U2211991-04-12012 April 1991 Forwards Response to NRC 901221 Request for Addl Info Re Ssar for Design Certification (CESSAR-DC) LD-91-014, Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per1991-03-26026 March 1991 Forwards Response to NRC Request for Addl Info Re Design Certification,CESSAR-DC,per ML20029C1001991-03-15015 March 1991 Forwards Response to NRC 890626 Request for Addl Info Re C-E Std SAR - Design Certification (CESSAR-DC),including Revs to CESSAR-DC ML20029C0141991-03-15015 March 1991 Forwards Response to NRC 890119 Request for Addl Info to Enable NRC to Continue Review of Cessar - Design Certification (CESSAR-DC) LD-91-010, Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC1991-03-0404 March 1991 Responds to NRC 881223 Request for Addl Info Re CESSAR-DC. Forwards Proposed Revisions to CESSAR-DC ML20029B6491991-03-0404 March 1991 Forwards Amend 1 to Cessar - Design Certification (CESSAR-DC). LD-91-006, Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes1991-01-30030 January 1991 Forwards Summary of Amend I to Std SAR for Design Certification,For Info & Planning Purposes LD-90-097, Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design1990-12-21021 December 1990 Forwards Response to 901106 Request for Discussion of Differences Between Certain Provisions of EPRI Advanced LWR Util Requirements Document & Sys 80+ Std Design LD-90-075, Forwards Amend H to CESSAR - Design Certification1990-10-0303 October 1990 Forwards Amend H to CESSAR - Design Certification LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per1990-08-28028 August 1990 Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per LD-90-046, Forwards Addl Copies of Amend G to CESSAR-DC1990-07-12012 July 1990 Forwards Addl Copies of Amend G to CESSAR-DC ML20044A5531990-06-18018 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 ML20042E9001990-04-30030 April 1990 Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document ML20011E2041990-01-25025 January 1990 Forwards Response to 881216 Request for Addl Info Re CESSAR-DC,Chapters 3,4,5 & 6 Re Turbine Missiles,Control Element Drive Structural Matls,Cleaning & Contamination Protection Procedures & Reactor Internals Matls ML20006A7201990-01-0505 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 ML20011D5151989-12-22022 December 1989 Forwards Amend F to C-E Std SAR - Design Certification (CESSAR-DC). ML19324B6811989-10-30030 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 71989-09-28028 September 1989 Forwards Addl Info Re CESSAR-DC Chapter 7 LD-89-092, Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification1989-08-17017 August 1989 Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification LD-89-091, Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys1989-08-16016 August 1989 Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys LD-89-033, Forwards Design Certification Licensing Review Basis, for Review & Concurrence1989-03-30030 March 1989 Forwards Design Certification Licensing Review Basis, for Review & Concurrence LD-89-035, Forwards Vols 1-17,consisting of Chapters 1-18,to CESSAR Design Certification, for Approval,Per 10CFR521989-03-30030 March 1989 Forwards Vols 1-17,consisting of Chapters 1-18,to CESSAR Design Certification, for Approval,Per 10CFR52 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 Request1989-03-17017 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 Encl1989-03-15015 March 1989 Forwards Amend E to C-E Std SAR Group E2 Re Design Certification.Summary of Revs Also Encl LD-88-132, Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review1988-11-11011 November 1988 Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review LD-88-128, Forwards QA Program in Response to NRC Request for Addl Info Re Chapter 17,CESSAR-DC QA1988-11-0404 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-11988-10-21021 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 Fees1988-09-30030 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 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 Ignition1988-09-20020 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 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 Listed1988-09-14014 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 ML20154K0211988-09-12012 September 1988 Submits Questions from South Korean Engineers Re Value of Design Certification Program for C-E Sys 80 & Sys 80 Plus Designs LD-88-089, Forwards Addl Info Re CESSAR-DC,Chapter 4,in Response to NRC 880628 Request1988-09-0909 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 Performance1988-09-0909 September 1988 Provides Proposed Resolution for Single Issue of Advanced Reactor Severe Accident Program Topic Paper Set 4, Essential Equipment Performance ML20151Q8581988-08-0202 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 Map1988-08-0202 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,Per1988-08-0101 August 1988 Forwards Response to Request for Addl Info Re CESSAR-DC Chapters 1 & 5 Re Sabotage Protection,Per 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 Design1988-07-29029 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 LD-88-055, Forwards Revised Design Certification Licensing Review Bases1988-07-15015 July 1988 Forwards Revised Design Certification Licensing Review Bases ML20150E7261988-07-0101 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 Encl1988-06-30030 June 1988 Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl LD-88-046, Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch1988-06-30030 June 1988 Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch 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 Submitted1988-06-17017 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 LD-88-039, Forwards Addl Info Re Chapters 1 & 10 to CESSAR-DC,per NRC 880311 Request1988-06-0606 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 Days1988-06-0606 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 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 Limits1988-05-25025 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 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 Responses1988-05-25025 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 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,Requested1988-04-11011 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 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 Changes1988-03-22022 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 Encl1988-03-18018 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 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 Encl1988-03-18018 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 1991-04-12
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARLD-90-075, Forwards Amend H to CESSAR - Design Certification1990-10-0303 October 1990 Forwards Amend H to CESSAR - Design Certification LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per1990-08-28028 August 1990 Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per LD-90-046, Forwards Addl Copies of Amend G to CESSAR-DC1990-07-12012 July 1990 Forwards Addl Copies of Amend G to CESSAR-DC ML20044A5531990-06-18018 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 ML20042E9001990-04-30030 April 1990 Forwards Amend G to CESSAR-design Certification,Per Draft Licensing Review Basis Document ML20006A7201990-01-0505 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 ML20011D5151989-12-22022 December 1989 Forwards Amend F to C-E Std SAR - Design Certification (CESSAR-DC). ML19324B6811989-10-30030 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 71989-09-28028 September 1989 Forwards Addl Info Re CESSAR-DC Chapter 7 LD-89-092, Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification1989-08-17017 August 1989 Forwards Slides from 890616 Meeting Re CESSAR-DC Baseline PRA for Sys 80+ Std Design Described in SAR on Design Certification LD-89-091, Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys1989-08-16016 August 1989 Forwards Responses to 881020 Request for Addl Info Re CESSAR-DC,Chapter 10, Emergency Feedwater Sys LD-89-035, Forwards Vols 1-17,consisting of Chapters 1-18,to CESSAR Design Certification, for Approval,Per 10CFR521989-03-30030 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 & Concurrence1989-03-30030 March 1989 Forwards Design Certification Licensing Review Basis, for Review & Concurrence 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 Request1989-03-17017 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 Encl1989-03-15015 March 1989 Forwards Amend E to C-E Std SAR Group E2 Re Design Certification.Summary of Revs Also Encl LD-88-132, Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review1988-11-11011 November 1988 Forwards Advanced Reactor Severe Accident Program Topic Paper Set 6, Development of Severe Accident Mgt Program, for Review LD-88-128, Forwards QA Program in Response to NRC Request for Addl Info Re Chapter 17,CESSAR-DC QA1988-11-0404 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-11988-10-21021 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 Fees1988-09-30030 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 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 Ignition1988-09-20020 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 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 Listed1988-09-14014 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 Request1988-09-0909 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 Performance1988-09-0909 September 1988 Provides Proposed Resolution for Single Issue of Advanced Reactor Severe Accident Program Topic Paper Set 4, Essential Equipment Performance ML20151Q8581988-08-0202 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 Map1988-08-0202 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,Per1988-08-0101 August 1988 Forwards Response to Request for Addl Info Re CESSAR-DC Chapters 1 & 5 Re Sabotage Protection,Per 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 Design1988-07-29029 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 ML20150E7261988-07-0101 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 Encl1988-06-30030 June 1988 Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl LD-88-046, Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch1988-06-30030 June 1988 Forwards Response to NRC 880315 Request for Addl Info Re CESSAR-DC,Chapter 10, Plant Sys Branch 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 Submitted1988-06-17017 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 LD-88-039, Forwards Addl Info Re Chapters 1 & 10 to CESSAR-DC,per NRC 880311 Request1988-06-0606 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 Days1988-06-0606 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 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 Limits1988-05-25025 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 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 Responses1988-05-25025 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 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,Requested1988-04-11011 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 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 Changes1988-03-22022 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 Encl1988-03-18018 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 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 Encl1988-03-18018 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 ML20149M6171988-02-16016 February 1988 Forwards Proprietary & Nonproprietary Base Line Level 1 PRA for Sys 80R NSSS Design, Per NRC Request.Proprietary Rept Withheld (Ref 10CFR2.790) 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 Design1988-01-22022 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 ML20148D3241988-01-19019 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 Requested1987-11-30030 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 Purposes1987-09-18018 September 1987 Forwards Revised Steam Generator Tube Rupture Analysis for Fsar.Rev Incorporates Revised Analysis Using Reactor Coolant Gas Vent Sys for Depressurization Purposes LD-87-050, Requests NRC Adoption of Proposed Docketing Process for Forthcoming Revs to C-E Std SAR1987-09-18018 September 1987 Requests NRC Adoption of Proposed Docketing Process for Forthcoming Revs to C-E Std SAR 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+1987-09-18018 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 Encl1987-09-18018 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 Tm1987-09-18018 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 Revised1987-04-23023 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 Days1987-04-10010 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 1990-08-28
[Table view] |
Text
COMBUSTION ENGINEERING April 11,1988 LD-88-026 Docket No. STN 50-470F (Project No. 675)
Mr. Frank J. Miraglia Associate Director for Projects Office of Nuclear Reactor Regulation Attn: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Combustion Engineering Standard Safety Analysis Report -
Submittal Group B: Amendments to Chapters 1, 4, 5, and 9
Dear Mr. Miraglia:
This letter transmits the next in Combustion Engineering's series of modifications to the Combustion Engineering Standard Safety Analysis Report - FSAR (CESSAR-F). Since the purpose of our modifications is to upgrade our current Final Design Approval (FDA-2) to a Design Certification, we refer to the revised CESSAR-F as CESSAR-DC. As you are aware, the enhanced and expanded design described la CESSAR-DC will be called the System 80+m Standard Design.
The enclosure to this letter provides you with our draft revisions to Chapters 1, 4, 5, and 9. Attachment (1) to this letter provides a management overview of the enclosed revisions. A summary of our view of the significance of these revisions is provided in Attachment (2).
Revisions relative to CESSAR-F are identified by a bar in the right-hand margin. To distinguish the amendments to CESSAR-F which are intended to lead to Design Certification from the amendments made in the course of updating CESSAR-F, we are introducing a lettered amendment system for CESSAR-DC. Revisions to Chapter 1 which were submitted previously as Amendment 12 [ Reference ( A)] are now identified as Amendment A. New revisions to Chapter 1, 4, 5, and 9 are identified as Amendment B.
We hope to formally submit a set of printed CESSAR-DC volumes to you in the near future. With that submittal, we intend to formally request opening of a separate docket for CESSAR-DC, as described in References 9
@ j 8804200529 000411 0 g PDR ADOCK 0500 K
Power Systems 1000 Prospect H,Il Road (203) 68B-1911 Combustion Engineenng. Inc. Post Offce Box 500 Te!ex 99297 3 6. g$
Windsor, Connectcut 06091 0500 v
Mr. F. J. Miraglio LD-88-026 April 11,1988 Page 2 (B) and (C). The issue of the category and limit of the fees to which we will be liable (Reference (D)), however, continues to remain an impediment to our submittal. We request, therefore, that the issue be addressed in a timely manner or a means be found which will protect our rights and thus allow the technical review to proceed unencumbered.
As a result of recent feedback from your staff and our experience to date, we have initiated a review of the schedule and composition of the submit-tais in our draft Licensing Review Bases [ Reference (E)). The purpose of our review is to develop more realistic submittal dates and logical submittal groups which will facilitate an efficient review. As an initial result of our review, we have revised the submittal date for Group C to June 30, 1988.
In order to ensure that the results of the review meet our mutual objec-tives, we intend to review our proposed submittal groups and schedule with your staff before finalizing them. We believe that the most effective approach will be to have a meeting with your staff in the near future to resolve this as well as other issues delaying the Licensing Review Bases agreement.
If we can be of any additional assistance in this matter, please feel free to call me or Dr. Michael D. Green of my staff at (203) 285-5204.
Very truly yours, COMBUSTION ENGINEERING, INC.
Director Nuclear Licensing AES:ss Attachments: As Stated
Enclosure:
As Stated l
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Mr. F. J. Miraglia LD-88-026 April 11,1988 Page 3 !
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References:
(A) Letter, LD-87-054, A. E. Scherer (C-E) to F. J.
- Miraglia (NRC), dated September 18, 1987 l (B) Letter, LD-87-050, A. E. Scherer (C-E) to F. J.
Miraglia (NRC), dated September 18, 1987 (C) Letter, L. S. Rubenstein (NRC) to A. E. Scherer, I (C-E) dated October 13, 1987 (D) Letter, LD-88-009, A. E. Scherer (C-E) to L. W. ,
Zech, Jr. (NRC), dated February 1,1988 (E) Letter, LD-88-005, A. E. Scherer (C-E) to F. J.
Miraglia (NRC), dated January 19, 1988 l
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Att:chment (1) to LD-88-026 Page 1 of 2 l l
l' Summary of Significant Revisions for CESSAR-DC Amendment Il Chapter 1
- 1. Sections 1.1 and 1.2 were updated to reflect current terminology and design overview. Commitment to the NRC Standardization, Safety Goal, and Severe Accident Policies is stated.
- 2. Responses to NRC questions were incorporated (see C-E Letters LD-88-019 and LD-88-020 dated March 18, 1988).
- 3. The Instrumentation and Control Room design summaries in Section 1.2 were updated.
- 4. The list of C-E topical reports incorporated by reference (Section 1.6) was updated,
- 5. The list of Regulatory Guides in Table 1.8-1 was expanded to include those from CESSAR-F, Appendix A.
Chapter 4
- 1. The number of Control Element Assemblies (CEAs) was increased from 89 to 93. Eight four-element, full-strength CEAs and the thirteen part-length CEAs were replaced by 25 full-length part-strength CEAs.
- 2. Ifafnium was added as an absorber material in four-element CEAs.
- 3. Gadolinia was added as an option for burnable poison rods.
Combustion Engineering has submitted a Topical Report on this modification.
- 4. The description of fuel-related demonstration programs was updated.
- 5. The thermal-hydraulic methodology was updated to include statistical combination of uncertainties. This methodology has been accepted by the NRC for reload analyses.
- 6. The neutronics methodology was updated to reflect revised methods.
The corresponding Topical Report has been approved by the MRC.
- 7. The hot leg temperature was decreased to 615 F.
Chapter 5
- 1. The introduction was revised to correspond to the System 80+
Standard Design. (Additional data and information will be provided in Submittal Groups C and D.)
Attachment (1) to LD-88-026 i Page 2 of 2 !
- 2. The Pressurizer volume was increased. l
- 3. The Steam Generator heat transfer area and secondary-side water ;
volume were increased, f
- 4. Materials and ASME Code compliance information in Section 5.2 was updated. (Overpressure protection information and analysis will be provided in Submittal Groups C and D.)
1
- 5. Section 5.3 was updated to reflect a 60 year design life for the '
I reactor vessel. (Additional revisions will be provided in Submittal Groups C and D.)
- 6. The reactor coolant system description in Section 5.4 was updated to
, reflect System 80+ current information. (Additional information will 4
be provided in Submittal Groups C and D.)
Chapter 9
- 1. Standardized Functional Descriptions for the Demineralized Water Makeup and Condensate Storage Systems were added to Section 9.2.
- 2. A Standardized Functional Description for the Process Sampling l System was added to Section 9.3.
- 3. The Chemical and Volume Control System design was revised to reflect reliability improvements and to reflect the transfer of accident mitigation and safe shutdown functions to other, safety-grade systems. .
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Attachacnt (2) to LD-88-026 '
Page 1 of 13
SUMMARY
OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4, Sp, AND 9p)
ITEM DESCRIPTION SECTIONS Note: This Attachment addressus both editorial and technical changes judged to be of some significance. Minor '
3 changes such as revised figure numbers are not addressed.
1 1 The "Contents of Report" was revised to Contents of identify the CESSAR-DC appendices which Report will summarize compliance with the Severe Accident Policy Statement.
(These appendices are also identified in Section 1.1.3.4.)
l 2 CESSAR-DC's compliance with the NRC's 1.1, 1.1.1, Severe Accident, Safety Goal, and 1.1.3.4 i Standardization Policies was stated. l I
3 The summary of the System 80+TM Standard 1.1.1, 1.1.2, i i
Design was revised for clarity. (There 1.1.5, 1.2, were, however, no significant changes.) 1.2.1, 1.2.2, 1.2.3, 1.2.4, 1.2.5 4 The Chemical and Volume Control System 1.1.3.2, (CVCS) was removed from the description 1.2.11.2 of safety system functions in response '
to NRC Question 281-1 (C-E Letter LD-88-019, 3/18/88).
5 The description of interfaces was 1.1.3.3 replaced with the summary of Standardized Functional Descriptions from the draft Licensing Review Basis ,
document.
6 The reactor core design criterion on 1.2.3.1 departure from nucleate boiling was revised for consistency with Chapter 4.
(This change did not affect the safety 1 analysis.)
7 The Containment System description was 1.2.4.1, revised and the Containment Spray System 1.2.4.5, description was added as a result of NRC T:1.2-1 Question 281-4.
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AttcchOnt (2) to LD-88-026 Page 2 of 13
SUMMARY
OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4, 5p, AND 9p)
ITEM DESCRIPTION SECTIONS 8 The summaries of Instrumentation and 1.2.5, Control Systems and the Nuplex 80+TM 1.2.5.1.2, Control Complex were revised to more 1.2.5.1.4, completely summarize the current design. 1.2.5.1.6, 1.2.6, T:1.2-1, T:1.3-4, 1.7 9 In anticipation of a future submittal, 1.2.10.2 Section 1.2.10.2 states that Standardized Functional Descriptions for Fuel Storage are provided in Section 9.1. (Section 9.1 will be included in Submittal Group E.)
10 A reference to chapters on Physical 1.2.13 Plant Security was added in response to NRC Question 500.2 (C-E Letter LD-88-020, 3/18/88). ,
11 In anti":ipation of a future submittal, 1.2.13 '
Section 1.2.13 states that Standardized Functional Descriptions and design features for Physical Plant Security are provided in Chapters 2, 3, 8, 9 and 13.
(This material will be in Submittal .
Groups D and E.)
l 12 The Safety Depressurization System was T:1.2-2
-dded in response to NRC Question 281-2 (C-E Letter LD-88-019, 3/18/88). This system will be located in Section 6.7, however, not Section 5.4.12 as indicated ,
in the response to the question. I 13 Responses to NRC Questions 281-1 and T:1.2-2 281-2 idicated that the CVCS would be removed from Table 1.2-2, since the CVCS l is not required for accident l mitigation. The CVCS will have interfaces with other systems and, thus, remains in Table 1.2-2, 14 The comparison of reactor T:1.3-1 l characteristics was revised to reflect l the information in the revisions to l Chapters 4 and 5.
e Attcchm nt (2) i to LD-88-026 ;
- Page 3 of 13 i
SUMMARY
OF CESSAR-DC DESIGN CHANGES i
' FOR SUBMITTAL GROUP B '
(CHAPTERS 1, 4, Sp, AND 9p)
ITEM DESCRIPTION SECTIONS I l
< i 15 Topical Reports referenced in Chapters 4 1.6 ;
i and 5 were added. The material already l listed was also updated to reflect the '
current status. Report CENPD-132-P was '
added for consistency with Table 1.5-1.
16 The list of applicable Regulatory Guides 1.8, T:1.8-1 was revised to include information from r CESSAR-F, Appendix A and Regulatory f Guides referenced in Chapters 4 and 5. '
Regulatory Guides withdrawn by NRC were i also identified.
17 Section 1.9 of CESSAR-F (Anticipated 1.9 Transients Without Scram) was deleted in 1
Amendment A as a result of design :
revisions. Amendment B includes an i appropriately marked page in place of i the previous Section 1.9 to clearly indicate its deletion.
18 The total number of CEAs was increased 4.1, 4.2.2.4, I
from 89 to 93. Eight full-length, T 4.2-1, full-strength and 13 part-length, 4.3.2.2.1, L
full-strength CEAs were removed. 4.3.2.2.3, Twenty-five full-length, part-strength 4.3.2.2.5.3, j CEAs were added to improve power + 4.3.2.2.5, j maneuvering. 4.3.2.4.2, i
' 4.3.2.4.3.4,
- 4.3.2.7.3.3, 4.3.2.7.4, ,
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4.3.2.7.5.2, 4.4.4.3, 19
- Figure 4.2-1, Reactor Core Cross 4.1 Section, was added for consistency with l
1 the existing text. (This is a l 1
! description change only, not a design ;
change.)
20 The transients which were previously
- 4.2.1.1 I
included in the analysis of a fuel assembly's compliance with design basgs were explicitly listed in CESSAR-DC. .
) (This is an editorial change only.) i I
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y4 Attcchment (2) to LD-88-026" j Page 4 of 13' ,
SUMMANY OF CESSAR-DC DESIGN CHANGES '
! FOR SUBMITTAL GROUP B i (OHAPTERS 1, 4, Sp, AND 9p; !
r ITEM DESCRIPTION '
SECTIO S
-- -. a 21 In the manufacture of the CEA guide 4.2.1.1.3, tubes and Zircaloy strip stock, limits 4.2.1.1.5 were placed on mechanical properties. '
a (These changes enhance performance.) 1 1
22 The description of fuel assembly design 4.2.1.1.3, bases was expanded to list a limit on 4.2.1.1.4, carbon conte'nt in Zircoloy. 4.2.1.1.5, 4.2.1.2.2.4,'
4.2.1.2.3.1 t
23 Additional description of the 4.2.1.1.6 manufacturing process for stainless ,
steel castings was provided. (This ;
change did not affect the design or -j performance but was provided for i
- completeness.)
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24 Additional detail was provided'on the 4.2.1 '1.9 1
manufacture of Inconel spacer grid i
strips. (This change did not affect the .
design or analysis.) i
- 25 Material procurement and fa*tication 4. .1.1.4, standards were updated. aterial 4.2.1.1.6, performance and applica' so remained 4.2.1.1.7,
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unaffected.) 4.2.1.1.8, -
4.2.1.1.9, 4.2.1.2.2.3, >
4.2.1.2.3.2, 4.2.5 1
26 The description of fuel pellet chemical 4 . 2,.1. 2 . 4 .1 analysis was updated. (There were no changes in the analysis results.)
t 27 The method of evaluating the effects of 4.2.1.2.4.3, irradiation on fuel pellot density was 4.2.3.2.8 1
updated to reflect current practice.
j (This is consistent with NRC guidance
- and our approved model.) i I
28 Gadolinia-Urania was added as ani alternative option to the B4C-AUJ03 4.2.i.3, l 4.2.1.3.4, l
absorber in the burnable poison rods. 4.2.2.3, I
(This application of gadolinia is being 4.2.3.3.1, reviewed by the NRC in Combustion 4.2.3.3.2, i
Engineering's Topice.1 Report 4.2.4.3.1, CENPD-275-P.) 1.3.4.3.2 l l
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l Atttchm nt-(2) !
a ho LD-88-026 ;
j t Page'5 of 17
SUMMARY
OF CESSAR-DC DESIGN CHANGES
.; FOR SUBMITTAL GROUP B
- (CHAPTERS 1,' ,4, Sp, AND 9p)
l 3
i ITEM DESCRIPTION SECTIONS l "
9 ' i
! 29 The B4C absorbar in the 4-element, 4.2.1.4.1, ;
full-length CEAs is replaced with 4.2.1.4.2, a
' hafnium in order to extend the CEA 4.2.1.4.4, design life from 10 to 20 years. 4.2.2.4, ,
r c 4.2.3.4, L 4.2.4.4, '
Tt4.2-1 30 The fuel assembly hold-down spring 4.2.2.1 l
, diameter was changed from l'.656 in, to '
1.859 in. and the wire diameter was c increased from 0.316 in to 0.319 in.
(These reviulons did not affect the '
safety analysis.)
i i 31 The description of the contact between 4.2,2.1 j
the fuel assembly hold-down springs and the upper guide structure was revised to be more complate. (Fuel assembly performance was unaffected.)
32 Minor improvenants in the manufacture of 4.2.2.1, the lower and of the fuel assemblies 4.2.4.1.1 wore described. (Fuel assembly performance was unaf fected. )
I 33 Minor changes were made to the 4.2.2.1 j
description of fuel assembly guide tube stability. (Fuel assembly performance j was unaffected.)
! 34 Minor changes were.made to the 4.2.3.1.1, description of fuel'assenbly analyses. 4.2.3.1.2,
! (Fuel assembly performance was 4.2.3.1.3, unaffected.) 4.2.3.2.1, 4.2.3.2.4
) 35 For fuel design evaluation, a statement 4.2.3.1.2 that the OBE is equivalent to one-half i
SSE was deleted. (10 CFR 100, Appendix j A, provides this definition. The j
analysis was performed jn conformance j
with the regulatien.) '
i
i l
, '\ ' i
- ~/
Attachmrt) # \'
3 to LD ;GL -026 i
e Page '6 of 13 ..t
- i , , .c N10fARY of CESSAR-DC QESIGN CHANGEF, .( I 'E.1, '
/ FOR SUDMITTAL GROUP B I, (CHAPTERS 1, 4, Sp,' AND l'p) t< /
'(/ I '
ITEM DESCRIPTibN SECTIONS / '
V
/ a y
, y y[ / s
.. j <
36 ANO-2 (System-80R' fuel) was/ added to the 4.2.1.1.3 list of reactors which have not shown
'l significant bowing of fact-roda.
provides additional confidence in the (This 4
[ )' '
i o
fuel rod design.) "
N*'
~i Descriptions of fuel rod internal 4 . 2 . 3 . 2 . 3 ( C ) ',
s
, idriding and chemical reacticos we:{e - 4.2.3.2.3(E)' '
dsed to be more complete. (The A sign I anaIysis remained unchangt<.t{)
i .
h /j}*
description of the results if
,i 3G 4.2.3.2.4 exam 16ations forIfu l rod fretting was '
'\! (\
revised for compldteness. (The design i and analysis were ux:: hanged.) "
/\ )
/ '
39 The description of f'uel dimensional 4.2.3J2.8 4, stability was updated to reflect more #
recent results. (The conclusions ', <
remaine'.D the same.) '
1
)
40 The description of participation in tha 4.2.3.2.10(I)
)
/
Halden experimental; program was updated. '
, (There was no impitt on fuel design or .I <
ana7ysis.)
)
4
)
di Descriptions c.7 fuel-related inspection 4.2.1.5.1, programs and Eknerience were updated.
(Results have v Yri'f.ed acceptable fuel 4.2.3.2.10(C),/,
performance.) ,
h 2.3.2.10(D ,
4 . 2 . 3 . 2 .1o { 3 )(', ,ji
( 4 . 21. 3 . 2 .10 ( K) , <
',i
)
/ '>
v ,, ,1 1 h 1 42 Regulatory Guides 1.46, 1.48, and 1.51 1
4 . J /. 5 were deleted from the.*]/st ol'r'elevant Regulatory Guides for raz'ctol - '
't <
interfaces. (The.y'werekith6hawnbythe '
g'.'
NRC.) , t ,' ' '
43 l.
The requirement on maximu6' enrichment 4. 2. 5 ( D)
(
for new fuel storagrjraaks was increased ,
from 3.7 w/o U-235 yo 4. 3 'w/o. i s y 44 The description of' power distribution 4.3.2.2.1
!/
men,jtoring was, expanded t,Andicate the use of Core Prcf.ection Calculators. '
I (This is an editorial change only.) .
V:
'i
, g i
^T{ l, -
e, ,'
Attachment (2) j to LD-88-026 lg 3 Page 7 of 13 K O I '
. i' j , /
SUMMARY
OF CESSAR-DC DESIGN CHANGES
,i ,' '
i j FOR SUBMITTAL GROUP B
'i (CHAPTERS 1, 4, Sp, AND 9p)
(>.
8 j ' ITEM DESCRIPTION SECTIONS
'I
' 3 1 45 Appro'ed v methodology for the statistical T:1.3-1, N (- cambination of uncertainties was
'/
) '
vi described for reactor core thermal 4.3.2.2.4, margin unalysis. [This change resulted 4.4.1.1,
/ in % thermal margin estimate of 15% 4.4.2.2.1, (idereas'd from 10%).)
4.4.2.2.2,
' f' 4. 4. 2. 2. 2. 2 (D) ,
, , 4.4.2.8, 4.4.2.9.4,
)' 4.4.2.9.5, J 4.4.2.10, 4.4.4.1, s
,\
4.4.4.5.2, 1 e T:4.4-2 46, Tha methodology for analyzing load 4.3.2.2.3, following capabilities was revised. (The 4.3.3.1.1.4 ysafety analyses were unaffected.)
47 The hRC-approved DIT, ROCS and MC codes 4.3.2.3, were csed for calculation of neutron 4.3.2.3.3,
' cross sections, coarse-mesh, and 4.3.3.1, fine-mosh power distributions. (This 4.3.3.1.1, strearalined the analysis. 4.3.3.1.2.2.1, e'
. T:4.3-15 f
. 48 The average void fraction was decreased 4.3.2.3.6, as a result of a 60 F reduction in hot 4.4.2.4 leg temperature, from 6210 F to 615 F. ,
' - l 49 Conservative CEA shutdown worths were
' 4.3.2.4.3, I provided for the end of Cycle One,- 4.3.2.4.3.6 rather than for the end of an I, equilibrium cycle because for the fuel
' management presented, the end of Cycle I
,One has the lowest shutdown worth.
50 .CEA reactivity allowances were revised 4.3.2.4.3, slightly, reflecting design methociology 4.3.2.4.3.1, changes. 4.3.2.4.3.6 51 . The maximum neutron fluence predicted 4.3.2.8, for the reactor vessel was increased to 4.3.3.3, 6.0 X 10 (19) n/cm2. (This resulted 5.3.1.4 from increasing the design life of the
<L reactor vessel to 60 years and using a larger uncertainty factor in the fluence predictions.)
k
Atttchm nt (2) to LD-88-026 Page 8 of 13
SUMMARY
OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4, Sp, AND 9p)
ITEM DESCRIPTION SECTIONS 52 The reactor outlet full-power average T:1.3-1, coolant temperature was lowered 60 F to 4.3.3.1.1.4, 6150F to increase the reactor core T:4.4-1, thermal margin. The cold leg T:4.4-4, temperature was correspondingly reduced T:4.4-9, from 5650F to 558 F. 5.1.4(G.10),
5.1.4(0.7),
5.4.2.1, T:5.1.1-1, T:5.1.1-2, T:5.4.2-1 53 The heat flux augmentation factor was 4.4.2.2.2.1(E),
removed since modern manufacturing [4.3.3.4 was procedures have effectively precluded deleted) fuel pellet densification.
54 An explicit requirement to meet the 4.4.3.1.1 Safety Injection System net positive suction head criteria of Section 6.3 was added.
55 Appendix A of CESSAR-F (QUIX computer 1.5.2.3, code description) was deleted. In T:1.5-1, CESSAR-DC the QUIX Manual is Reference Appendices 4A 4.3(14). Appendices 4B and 4C were and 4B re-lettered to 4A and 4B in CESSAR-DC.
(These revisions are editorial.)
56 The pressurizer volume was increased to T:4.4-8, improve the response of the reactor T:4.4-9, 5.1.1, coolant system to transients. T:5.1.1-2, T:5.1.1-3, T:5.1.4-3, T:5.4.10-1 57 The steam ge'.:erator size was increased T:1.3-1, to accomodate a larger number of tubes, T:4.4-8, an increased water volume, lower T:4.4-9, 5.1.1, l
I pressure, and lower hot leg temperature. T:5.1.4-2, (These changes were made to improve the T:5.1.4-3, reactor coolant system's response to T:5.1.1-2, transients.) T:5.1.1-3, T:5.4.2-1, 5.1.4(0.7)
Attachm:nt (2) to LD-88-026 Page 9 of 13
SUMMARY
OF CESSAR-DC DESIGN LdANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4, Sp, AND 9p)
ITEM DESCRIPTION SECTIONS l
58 Discharge from the Reactor Coolant System safety valves and the new 5.1, 5.1.4(0.2) motor-operated Safety Depressurization System valves was routed to the in-containment refueling water storage tank. (This improves the quenching capability.)
59 The reference for definition of the 5.1.2, 5.2 reactor coolant pressure boundary was updated to ANSI 51.1 - 1983. (This revision did not materially affect the System 80+ Standard Design.)
60 The list of Regulatory Guides applicable 5.1.4 to the design of the reactor coolant system was updated.
61 The set of guidelines for implementing 5.1.4(F.6, F.7) interface criteria for the emergency feedwater system was updated to ANS 58.9
- 1981.
62 Interface requirements for main steam 5.1. 4 ( F) isolation valve bypass and atmospheric dump valve control circuits were deleted. (They are included in the scope of Chapter 7.)
63 The interface requirement on emergency 5.1. 4 ( F) ,
feedwater system unavailability was 5.1.4(G) deleted. (This system is included in the System 80+ design scope, Chapters 7 and 10.
64 The interface requirements for atmospheric dump valve control and 5.1.4(G) actuation were deleted. (Information is either included in Chapter 10 or is included in the scope of Chapter 7.)
65 The interface requirement on secondary side valve monitoring was deleted. (It 5.1. 4 (H) is included in the scope of Chapter 7.)
Atttchm nt (2) to LD-88-026 Page 10 of 13
SUMMARY
OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4, Sp, AND 9p)
ITEM DESCRIPTION SECTIONS !
L I
66 Interface requirements on valve controls were deleted. (They are included in the 5.1.4(I) !
l scope of Chapter 7.) t 67 The uncertainty on feedwater temperature 5.1.4(H.4) measurement was increased from 1 F to
- 5. 50 F . (This change does not affect the design or analysis.) 1 68 Additional detail on the pressurizer 5.1.4(M.1, M.2) surge line was provided to avoid water
{
traps. (This improved performance of !
the RCS and did not affect existing !
safety analysis conclusions.) j 69 The requirement on system arrangements 5.1.4(M.4) for avoidance of reactor vessel cavity flooding was revised to include the Safety Injection System.
70 Additional requirements on the pressurizer spray line were provided to 5.1.4(M.20/21) minimize the potential for waterhammer.
71 A requirement was added to disallow loop seals in the safety valve inlets. 5.1.4(M.22) 72 Heat loads from steam generator supports T:5.1.4-2 were updated. (Safety-related aspects of the design were unaffected.)
l 73 Regulatory Guide 1.147 was referenced 5.2.1.2 for determining ASME Code Cases in addition to the previously referenced Regulatory Guides 1.84 and 1.85.
74 Primary safety valve blowdown was 5.2.2.4, revised from 5% to 18.5%, consistent T:5.4.13-1 with previously approved experimental and safety analysis results (Appendix 5A).
75 The title was revised to include 5.2.2.10.1.4 standard IEEE-279. (This was an editorial change only.)
Attcchm nt (2) to LD-88-026 Page 11 of 13
SUMMARY
OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4, Sp, AND 9p)
ITEM DESCRIPTION SECTIONS 76 The reactor vessel material type was 5.2.3.1, changed from SA-533B (plate material) to T:5.2-2, SA-508 (forging material). (This will 5.2.3.3.2.1, eliminate longitudinal welds in the 5.3.1.6.1, active core region and help increase 5.3.1.6.4.1, reactor vessel design life to 60 years.) 5.3.2.1 77 A requirement was added to restrict the 5.2.3.2.2 use of material containing cobalt in reactor coolant pressure boundary materials. (This will reduce coolant contamination due to activated cobalt.)
78 The limitation on the extent of Reactor 5.2.3.2.3 Coolant Pressure Boundary insulation provided was removed.
79 The ASME Code was referenced, in place 5.2.3.4.2.1 of AWSA.S.4, for the current manufacturing process used to minimize hot cracking during welding.
80 The access to reactor vessel inlet 5.2.4.1 nozzles for inspections was described.
(This is an editorial change only.)
81 The reactor vessel head and beltline 5.2.3.1, region manufacturing method was changed 5.3.1.2 to a forging method. (This will eliminate longitudinal welds in the active core region and help extend the reactor vessel lifetime to 60 years.)
82 Regulatory Guide 1.99 was referenced for 5.3.1.4 predictions of reactor vessel irradiation. (This is consistent with NRC guidance.)
83 The ASTM Standard reference for reactor 5.3.1.6, vessel surveillance was updated to the 4.3.1.6.2.1, 1982 version. 5.3.3.7 84 Neptunium was added as a candidate 5.3.1.6.4.1, material for neutron threshold T:5.3-5 detectors.
Attachmsnt (2) to LD-88-026 Page 12 of 13
SUMMARY
OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4, Sp, AND 9p)
ITEM DESCRIPTION SECTIONS 85 The design basis of the Steam Generators 5.4.2.1 was revised to include an increased number of design transient cycles.
86 The description of reactor coolant pump 5.4.1.4 tests was revised. (Pump test program conclusions are unaffected.)
87 Main Steam Isolation Valve and Main 5.1.4(I.3,I.6),
Feedwater Isolation Valve closure times 5.4.5.3 were revised from 4.6 seconds to 5 seconds. (This change does rot affect the safety analysis conclusico.s. )
88 The design basis of the pressurizer was 5.4.10.1 modified to improve plant response during transients.
89 The thermal sleeves were removed from 5.4.10.2 the pressurizer surge and spray nozzles.
(This change was based on operating plant experience.)
90 Minor revisions were made to the 5.4.10.2 description of pressurizer level control.
91 Leak-Before-Dreak methodology was 5.1. 4 (C.1) ,
applied to reactor coolant system branch 5.4.14 lines, in accordance with recent revisions to General Design Criterion 4. i 92 A Standardized Functional Description 9.2.3 was provided for the Demineralized Water Makeup System. I 93 An editorial revision was made to 9.2.1, 9.2.2, indicate that Standardized Functional 9.2.4, 9.2.5 Descriptions would be provided later for the Station Service Water System, ;
Cooling System for Reactor Auxiliaries, Potable and Sanitary Water Systems and the Ultimate Heat Sink. l
Atte.chmtnt (2) to LD-88-026 Page 13 of 13 SUFMARY OF CESSAR-DC DESIGN CHANGES
OR SUBMITTAL GROUP B
"' ' 'FDS 1, 4, Sp, AND 9p)
ITEM DESCRIPTION SECTIONS 94 An editorial revision was made to 9.3.1, 9.3.3, indicate that Standardized Functional 9.4 Descriptions would be provided later for the Compressed Air Systems, Equipment and Floor Drainage System, and the Air Conditioning, Heating, Cooling, and Ventilation Systems.
95 A Standardized Functional Description 9.2.6 was provided for the Condensate Storage System.
96 A btandardized Functional Description 9.3.2 was provided for the Process Sampling System.
97 The Chemical and Volume Control System T:4.6-1, design w&s revised. (It is no longer 9.3.4.1.1, required to perform any accident 9.2.4.1.2, mitigation or safe shutdown functions.) 9.3.4.1.3, 9.3.4.2, 9.3.4.3, 9.3.4.3.7 98 The CVCS design was revised to include 9.3.4.1.2, two charging pumps, not three. (The 9.3.4.1.3, CVCS is no longer required to perform 9.3.4.3.1 any accident mitigation or safe shutdown functions.)
99 Modifications were made to the CVCS 9.3.4.1, which improve reliablity. 9.3.4.2, 9.3.4.3, 9.3.4.5 100 Makeup and chemistry control of the 9.3.4.1.1, water in the in-containment refueling 9.3.4.2.1, water storage tank were added to the 9.3.4.2.3 list of CVCS functions.