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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
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e CONIBUSTION ENGINEERING May 25,1968 LD-88-034 Docket No. STN 50-470F (Project No. 675)
Mr. Guy Vissing, Project Manager Standardization and Non-Power Reactor Project Directorate Office of Nuclear Regulation Attn: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Response to NRC Request for Additional Information on Chapter 10 CESSAR-DC, Secondary Water Chemistry
References:
(A) Letter, G. S. Vissing (NRC) to A. E. Scherer (C-E),
dated February 25, 1988 (B) Letter, LD-87-068, A. E. Scherer (C-E) to F. J.
Miraglia (NRC), dated November 30, 1987
Dear Mr. Vissing:
Reference (A) requested that Combustion Engineering provide tdditional information on CESSAR-DC Chapter 10. Enclosure (1) to this letter provides our .esponses and Enclosure (2) provides the corresponding revisions to our submittal of Reference (B).
Should you have any questions, please feel free to contact me or Dr. M D. Green of my staff at (203) 285-5204.
Very truly yours, COMBUSTION ENGINEERING, INC.
Director Nuclear Licensing AES:blr 0g
Enclosures:
As Stated cc: Frank Ross (DOE-Germantown)
Power Systems 1000 Prospect H.ll Road (203) 688 1911 Cornbust:on Engineenng. Inc. Post Off,ce Box 500 Telex: 99297 Windsor, Connecticut 06095-0500 g6gg4gg A DCD l
, Enclosure (1)
- to LD-88-034
. Page 1 of 10 Response to NRC Request for Additional Information Concerning Chapter 10 CESSAR-DC, Secondary Water Chemistry
References:
(1) Letter, G. S. Vissing (NRC) to A. E. Scherer (C-E) dated February 25, 1988 (2) "Safety Evaluation Report Related to the Fina'. Design of the Ste.idard Nuclear Steam Supply Reference System CESSAR System 80", NUREG-0852, dated November 1981 Reference (1) requested that Combustion Engineering provide additional information on CESSAR-DC, Chapter 10 This enclosure provides our responses.
, Enclosure (1) to LD-88-034
. Page 2 of 10 Question 281-8 The EPRI ALWR Requirements Document, Chapter 3, Paragraph 4.2.7, requires a plant design which provides system features which facilitate compliance with EPRI NP-5056-SR, PWR Secondary Water Chemistry Guidelines. Section 10.3.5 does not reference the EPRI Secondary Water Chemistry Guidelines. A generic secondary water chemistry program that conforms with SRP Section 5.4.2.1, Branch Technical Position MTEB 5.3 should be provided.
Response 281-8 The System 80+D design complies with the EPRI ALWR Requirements Document, Chapter 3, Paragraph 4.2.7. The System 80+ design provides system features which facilitate compliance with the secondary water chemistry requirements described in EPRI Report NP-5056-SR, dated June 1984, "PWR Secondary Water Chemistry Guidelines." Specifically, the secondary water system, the makeup water system, and the process sampling system, as described in CESSAR-DC Sections 9.2.3, 9.3.2, 10.3.5,10.3.6,10.4.6,10.4.7, and 10.4.8, have been designed to be consistent with the referenced EPRI guidelines.
To demonstrate the consistency of CESSAR-DC, Chapter 10, with the above-referenced EPRI "PWR Secondary Water Chemistry Guidelines",
Combustion Engineering (C-E) has performed a comparison between the CESSAR-DC proposed operating chemistry limits and the EPRI Guidelines.
This comparison revealed six (6) differences. C-E has reviewed these six differences and has elected to conform with the EPRI Guidelines in each
! instance. Tables 10.3.5-1 and 10.3.5-2 will be revised to reflect C-E's concurrence with the EPRI Guidelines.
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In addition to the above chemistry limits, Section 10.3.5 of CESSAR-DC I stipulates general provisions for a secondary water chemistry program.
These provisions were presented in CESSAR-F and were judged by the NRC staff to meet the acceptance criteria for the non-plant specific details of water chemistry programs as specified in Branch Technical Position MTEB 5-3 [see section 10.3.1 of Reference (2)).
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Encicoure (1) to LD-88-034
. Page 3 of 10 Since the water chemistry limits are consistent with the current EPRI guidelines and since other general provisions have not been changed relative to CESSAR-F, C-E believes that the previous NRC conclusion remains valid.
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Enclosure (1) to LD-88-034
. Page 4 of 10 Question 281-9 Section 10.3.5 provides operating chemistry limits for secondary steam generator water, feedwater and condensate. Normal and Abnormal limits are provided for secondary water. However, the three action levels and corrective actions to be considered (as recommended by the EPRI PWR Secondary Water Chemistry Guidelines) are not provided.
Response 281-9 Section 10.3.5 of CESSAR-DC provides normal, abnormal, and immediate shutdown limits for secondary water and discusses the corrective actions to be performed when these limits are exceeded. This information is presented in the last six (6) paragraphs of Section 10.3.5.1, and in Tables 10.3.5-1 and 10.3.5-2. A detailed comparison of the CESSAR-DC normal, abnormal, and immediate shutdown limits with the EPRI "PWR Secondary Water Chemistry Guidelines" (see Table 1) was performed. Tids comparison showed that C-E's chemistry limits and recommended Corrective Actions are consistent with the EPRI Action Levels and their recommended corrective actions. CESSAR-DC Section 10.3.5.1 will be revised to make it clear that C-E's secondary water chemistry program includes normal, abnormal, and immediate shutdown limits.
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Enclosure (1) to LD-88-034 Page 5 of 10 Table i EPRI PWR Secondary Water Chemistry Guidelines for Corrective Actions Action Levels Status Corrective Actions Status Normal Value Range None Action Level 1 (1) Return parameter to within (Normal Range Exceeded) Normal Value Range within one week following confirmation of excursion.
(2) If parameter is not within Normal Value Range within one week following confirmation of excursion, then go to Action Level 2 for parameters having Action Level 2 values.
Action Level 2 (1) Reduce power to appropriate level (typically 30% or less) within four hours of initiation of Action Level 2.
(2) Return parameter to within Normal Value Range within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> or go to Action Level 3 for those parameters having Action Level 3 values.
Action Level 3 (1) Shutdown within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and clean up by feed and bleed or drain and refill as appropriate until normal values are reached.
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7 Enclosuro (1) to LD-88-034 Page 6 of 10 Question 281-10 Section 10.3.5 does not provide guideline parameters and corresponding normal and action values for:
- a. cold shutdowngwet layup steam generator sample,
- b. heat-up (>200 F to <5 percent power) steam generator blowdown sample ,
- c. feedwater - during fill,
- d. heat-up feedwater sample, and e, power operation condensate sample, as recommended in the EPRI PWR Secondary Water Chemistry Guidelines.
Response 281-10 As stated in the response to Question 281-8, Section 10.3.5 stipulates requirements which set forth general provisions for a secondary water chemistry program. The requirements set forth in Section 10.3.5 (primarily Tables 10.3.5-1 and 10.3.5-2) define, for plant power operation
(>5% power), the secondary water chemistry parameters, their limits, and the allowable time span that these chemistry parameters may be out of l their operational limits. In order to more fully distinguish condensate and feedwater chemistry requirements, Table 10.3.5-2 will be revised to be feedwater specific, and a new Table 10.3.5-3, Operatinst Chemistry Limits for Condensate, will be added to CESSAR-DC. Detailed f operating guidelines for cold shutdown / wet layup, system fill, and system heat-up are implemented into plant-specific water chemistry programs l
which, past experienca has shown, are developed based on input from both I Combustion Engineering and EPRI.
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Enclosure (1) to LD-88-034 Page 7 of 10 Question 281-11 Section 10.3.6.2 does not include materials selection recommendations in EPRI ALWR Requirements Document (Chapter 1, Section 5.3.B) regarding ,
prohibition of copper alloys e d design considerations identified in EPRI NP-2294, "Guide to the Desigo of Secondary Systems and Their Components to Minimize Oxygen-Induced Corrosion" for the steam and feedwater system.
Response 281-11 The following will be added to Section 10.3.6.2 to address material selection for minimizing erosion-corrosion of components in the steam and power conversion system, in accordance with EPRI's ALWR Requirements Document:
I o No copper alloys are used for components that are in contact with feedwater, steam, er condensate.
t o Oxygen induced corrosion is minimized by providing the following component materials:
Moisture separator reneater tubes are ferritic stainless steel.
d - Low pressure feedwater heater tubes are type 304L stainless steel with 304L-clad carbon steel tube sheets, t High pressure feedwater heater tubes are type 316L stainless 1
i steel with 316L-clad carbon steel tube sheets.
- The condenser tube material is type 304L stainless steel for l fresh water applications with chloride levels below 200 ppm. For i
chloride levels up to 500 ppm, type 316L stainless steel tubing is J
j - used. A higher grade of stainless steel (such as 904L or
.; AL-6X) is used for chloride levels between 500 and 800 ppm. !
For brackish or salt water applications with high chlorides (greater than 800 ppm), or water contaminated by sewage 1
discharges, titanium tubing is used. !
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Enclosure (1) ;
to LD-88-034 i l- Page 8 of 10
- The condenser tube sheets are specified as follows:
-- For 304L stainless steel tubes, 304L stainless-clad carbon !
steel tube sheets are used, t
-- For 316L stainless steel tubes, 316L stainless-clad carbon steel tube sheets are used.
For titanium tubing, titanium-clad carbon steel tube sheets ;
are used.
1 1 - The main steam piping, hot reheat piping, condensate piping, feedwater piping, and heater drain piping upstream of the drain control valve are carbon steel. Extraction steam piping, heater drain piping downstream of the drain control valves, pd other ,
piping exposed to wet steam or flashing liquid flow r..e either ,
chrome-moly or stainless steel. The degree of corrosion / erosion 7 resistance of the piping material is consistent with the ;
temperature, moisture content, and velocity of the steam to j which the piping is exposed. :
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Enclosure (1) ,
to LD-88-034 '
. Page 9 of 10 Question 281-12 Section 10.4.6.2, item 4, the purpose of the resin traps should be included (i.e., to remove resin fines). Item 5 should include the requirement that the minimum flow rate of the condensate polisher should be specified by the manufacturer to prevent channeling.
Response 281-12 C-E agrees with these recommendations. Item 4 of Section 10.4.6.2 will be revised to state, "Resin traps are installed down stream of each lon !
exchanger to remove resin fines." The sentence, "In addition, a minimum i flow rate is specified by the manufacturer to prevent channeling," shall be inserted after the first sentence of Section 10.4.6.2, Item 5.
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Enclosure (1) to LD-88-034 Page 10 of 10 Question 281-13 Section 10.4.6.2 does not meet the EPRI ALWR Requirements Document regarding utilization of a side stream condensate polisher system which contains deep bed mixed bed ion exchangers.
Response 281-13 The first paragraph of Section 10.4.6.2 will be revised as follows to indicate compliance with the EPRI ALWR Requirements Document:
"The condensate cleanup system utilizes a side stream, full condensate flow polisher, located downstream of the condensate pumps. Deep bed, mixed resin ion exchangers are utilized to obtain the advantage of their larger capacity in the event of the inleakage of impurities, to reduce the probability of resin discharge to the feed system due to feilure of resin retention elements, and to simplify system operation."
Enclo ure (2) to LD 034 Page 1 of 10 PROPOSED REVISIONS TO TIIE COMBUSTION ENGINEERING STANDARD SAFETY ANALYSIS REPORT 1
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h 2,6\Cl Enclosure (2) to LO-83-034 Page 2 of 10 b.
Centinuous effects of theblowdown of the steam generator to reduce the concentrating steam generator.
c.
Chemicalsystem minimizes addition to establish and maintain an environment which corrosion.
- d. Preoperational cleaning of the feedwater system.
- e. Minimizing feedwater oxygen content prior to entry into the steam generator.
Secondary water chemistry is based on the zero solids treatment method. This method employs the use of volatile additives to maintain system pH and to scavenge dissolved oxygen which may be present in the feedwater.
A neutralizing amine is added to establish and maintain alkaline conditions in the feedtrain. Neutralizing amines which can be used for pH control are ammonia, morpholine, and cyclohexylamine. Amonia should be used in plants employing condensate polishing to avoid resin fouling. Although the amines are volatile and will not concentrate in the steam generator, they will reach an equilibrium level which will establish an alkaline condition in the steam generator.
Hydrazine is added to scavenge dissolved oxygen which may be present in the feedwater. Hydrazine also tends to promote the formation of a protective oxide layer on metal surfaces by keeping these layers in a reduced chemical state.
Both the pH agent and hydrazine can be injected continuously at the discharge headers of the condensate pumps or condensate demineralizer, if installed.
These chemicals are added as necessary for chemistry centrol, and can also be added to the upper steam generator feed line when necessary.
Operating chemistry limits for secondary steam generator water and feedwater and condersate are given in Tables 10.3.5-gae+ 10.3.5-2x ad lo& M The limits stated are divided into groups: normalY andy abnomal, The
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limits provide high quality chemistry control and yet permit operating flexibility.
The normal chemistry conditions can be maintained by any plant to operating with little or no condenser leakage. The abnormal steam generator limits are suggested to permit operations with minor system f3 ult conditions hesh p cken*g to4b% ak h cockmehuntil the affected component can be isolated and/or rep The following procedures are re:cmmended 9@oMm(cwc\k h6eJere.skow yiec@ecrco roS% b@
system and steam generator corrosion:
or protection against secondary 12 ed When the nomal range is exceeded, immediate investigation of the pr:,olem should be initiated, sampling frequency increased to the abnormal level (at least twice per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shift) and blowdown increased to one (1) percent of the main steaming rate. to The problem should be corrected and the parameter (s) returned to the nomal range within one week. If this cannot be done, and the parameter has a listed abnormal range, power should be reduced -+e-GM-as if the abnomal range had been exceeded.
Amendment No. 12 10.3-13 September 11, 1987 L
i Enclosure (2)
-Q h 28\-9 to LD-83-034 Page 3 of 10
$d When the abnomal ran is exceeded, power should be reduced to the lowest value (:=M M 25% consistent with automatic operation of the feed system.
Continued plant operation is then possible while corrective action is taken.
Power reduction should be initiated within four hours of exceeding the 10 abr.omal range. The problem should be corrected and the parameter (s) returned to the nomal range within one hundred (100) hours. If this cannot be done the u it should be shu down, dem M@e. ShAhom bk is eureM h04Y m, sT be s bW% b to (Muk $ $b peraNor cono5 ion Draining or flushing of the steam generators will be necessary to reduce the impurity concentration. 5 10.3.5.2 Corrosion Control Effectiveness Alkaline conditions in the feed train and the steam generator reduce general corrosion at elevated temperatures and tend to decrease the release of soluble corrosion products from metal surfaces. These conditions promote the formation of a protective metal oxide film and thus reduce the corrosion products released into the steam generator.
Hydrazine also prcmotes the formation of a metal oxide film by the reduction of ferric oxide to magnetite. Ferric oxide may be loosened from the metal surfaces and be transported by the feedwater. Magnetite, however, provides an adherent protective layer on carbon steel surfaces.
The removal of oxygen from the secondary water is also essential in reducing corrosion. Oxygen dissolved in water causes general corrosion that can result in pitting of ferrous metals, particularly carbon steel. Oxygen is removed from the steam cycle condensate in the main condenser deaerating section and by the full flow feedwater deaerator which is a portion of the low pressure 12 feedwater heaters. Additional oxygen protection is obtained by chemical injection of hydrazine into the condensate stream. Maintaining a residual level of hydrazine in the feedwater ensures that any dissolved oxygen not removed by the main condenser is scavenged before it can enter the steam generator.
The presence of free hydroxide (CH ) can cause rapid corrosion (caustic stress corrosion) if it is allowed to concentrate in a loce.1 area. Free hydroxide is avoided by maintaining proper pH control, and by minimizing impurity ingress in the steam generator.
Zero solids treatment is a control technique whereby both soluble and insoluble solids are excluded from the steam generator. This is accomplished by maintaining strict surveillance over the possible sources of feed train contamination (e.g: Main Condenser cooling water leakage, air inleakage and subsequent corrosion product generation in the Low Pressure Orain System, etc.). Solids are also excluded, as discussed above, by injecting only volatile chemicals to establish conditions which reduce corrosion and, therefore, reduce the transport of corrosion products into the steam generator. Reduction of solids in the steam generator can also be accomplished through the use of full flow condensate demineralization.
In addition to minimizing the sources of contaminants entering the steam generator, continuous blowdown is employed to minimize their concentration.
Amendment No. 12 10.3-14 September 11, 1987
. 1 Enclosure (2) g g., gg to LD-88-034 Page 4 of 10 i These systems are discussed in Section 10.4.6. With the low solid levels which result from employing the above procedures, the accumulation of corrosion deposits on steam generator heat transfer surfaces and internals is limited. Corrosion product formation can al ter the thermal hydraulic 12 performance in local regions to such an extent that deposits create a mechanism which allows impurities to concentrate to high levels, and thus could possibly cause corrosion. Therefore, by limiting the ingress of solids into the steam generator, the effect of this type of corrosion is reduced.
Because they are volatile, the chemical additives will not concentrate in the steam generator, and do not represent chemical impurities which can themselves tause corrosion.
10.3.6 STEAN AND FEE 0 WATER SYSTEM MATERIALS 10.3.6.1 Fracture Touchness Materials are in compliance with Sections II and III of the ASME Boiler and Pressure Vessel Code with respect to fracture toughness and meet the requirements of ASME Section III, articles NB-2300, NC-2300, and ND-2300.
10.3.6.2 Materials Selection and Fabrication
- 1) Materials used are included in Appendix I of Section III of the ASME 12 Code.
- 2) No austenitic stainless steel piping material is used in these systems.
- 3) Cleaning and acceptance criteria are based on the requirements of ANSI N45.2.1-73 and the recomendations of NRC Regulatory Guide 1.37.
- 4) Low-alloy steels are not used in the systems for piping materials.
- 5) The degree of compliance with NRC Regulatory Guide 1.71, "Welder Qualification for Areas of Limited Accessibility", is discussed in Section 1.8.
- 6) Noncestructive examina. tion procedures for tubular products conform t the requirements of the ASME Code,Section III, NC-2000 for Class 2 materials.
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Mendment No.12 10.3-15 September 11, 1987 l
' Enclosure (2) to LD-88-034 Page 5 of 10 INSERT A (Q/R 281-11)
- 7) No copper alloys are used for components that are in contact with feedwater, steam or condensate.
- 8) Oxygen induced corrosion is minimized by providing the following component materials:
a) Moisture separator reheater tubes are ferritic stainless steel, b) Low pressure feedwater heater tubes are type 304L stainless steel with 304L-clad carbon steel tube sheets.
c) High pressure feedwater heater tubes are type 316L stainless steel with 310L-clad carbon steel tube sheets.
d) The condenser tube material is type 304L stainless steel for fresh water applications with chloride levels below 200 ppm. For chloride levels up to 500 ppm, type 316L stainless steel tubing is used. A higher grade of stainless steel (such as 904L or AL-6X) is used for chloride levels between 500 and 800 ppm.
For brackish or salt water applications with high chlorides (greater than 800 ppm), or water contaminated by sewage discharges, titanium tubing is used.
e) The condenser tube sheets are specified as follows:
o For 304L stainless steel tubes, 304L stainless-clad carbon steel tube sheets are used.
o For 316L stainless steel tubes, 316L stainless-clad carbon steel tube sheets are used.
o For titanium tubing, titanium-clad carbon steel tube sheets are used. ,
f) The main steam piping, hot reheat piping, condensate piping, feedwater piping, and heater drain piping upstream of the drain control valve are carbon steel. Extraction steam piping, heater drain piping downstream of the drain control valves, and other piping exposed to wet steam or flashing liquid flow are either chrome-moly or stainless steel. The degree of corrosion / erosion resistance of the piping material is consistent with the temperature, moisture content, and velocity of the steam to which the piping is exposed.
G Enclosure (2)
Q[$ ?Jb\ B to LD-88-034 ;
Page 6 of 10 i TABLE 10.3.5-1 OPERATING CHEMISTRY LIMITS FOR SECONDARY STEAM GENERATOR WATER Normal (1) Abnormal Variable Specifications Limits pH (mixed system)( ) 8.5 - 9.0 (copper free) 9.0 - 9.5(5)
Cation Conductivity (3) s 0.8 pmhos/cm 0.8-2.0 pmhos/cm Silica s 300 ppb Chloride 1 20 ppb 20-100 ppb Sodium (4) s 20 pob 20-100 ppb Sulfate 630g(>t
- 15 ;; 15 1^,0 pp; 10 NOTES:
(1) Normal specifications are those which should be maintained by continuous steam generator blowdown durir.g proper operation of secondary systems.
(2) A mixed system is any secondary system containing copper alloy components.
(3) If the imediate shutdown limit of 7.0 pmhos/cm is exceeded, the unit should be shut down within four hours.
l (4) If the imediate shutdown limit of 500 ppb is exceeded, the unit should be shut down within four hours.
I (5) In plants where condensate polishers are in operation, the pH of a i copper-free system can be controlled to a value of 18.8, with action required at < 8.8. 12 l
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l Amendment No. 12 September 11, 1987 l
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" Enclosure (2) g g,g to LD-80-034 Page 7 of 10 TABLE 10.3.5-2 OPERATING CHEMISTRY LIMITS FOR FEE 0 WATER 'MO COMDCM ?T G k m .go Nonnal(1)
Variable Soecifications pH
- a. Mixed system 8.8 - 9.2
- b. Copper-free system 9.3 - 9.6 Conductivity (Intensiftad cation)(F :d :ter) s 0.2 pmhos/cm tto Hydrazine (Feedwater) 10 50 ppb Dissolved Oxygen 6 6 pb P
(F::d) : 3 pub (Cenden::te) 9 : 10 ppt Sodium ) s 3 ppb Iron ff::f ;ted- s 20 ppb to u ce,,t 91 asa4+4 99 4 Copper (F::i:tcr)-(k s 2 ppb NOTES:
(1) Normal specifications are those which should be maintained during proper operation of secondary systems.
-(2) The ::..d:n:::: bno; ;;el li..;; is 10 00 ppt, but the requir; ;at for -
i;; diet; :hutd:un d::: :t :pp!y ever if th: probl= i: n:t corrected
-witM - 100 hr3.-
42; For the cor,dcasate, ::dia: i: ;;niterd at 02 h tenden: r 50t w:ll.-
2 (A) Analysis not required for copper-free systems.
(5) Li-it is depsadeia wgvi. gu.
In plants where condensate polishers are in operation, the pH 'of a 12 copper-free system can be centrolled to a value of a 9.0, with action required at < 9.0.
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. d'9s<u @^uh we**ew- 4 "Igb ut Tm 4 nd bw Mh% ex w &.Uws,aw w a % dn Euotweyck 44 "1s nL % w %y 9 ' VPR- Anendment No.12 September 11, 1987
Enclosure (2) to LD-88-034 OkZ&6 ' Page 8 of 10 3
TA8LE10.3.5-f OPERATING CHEMISTRY LIMITS FOR I:"~2T ' 00 CONDENSATE Q$ZtHO Nomal(1) yariable Soecifications 9H-
.- u . a. . . , .. .. ... ._._ _
,e . ,. ,, ,
-b C^"? r-fr:: :ysts -9.; 9.,4
...........,s........,.,.- .
- t 4^a) (C^^S:ter)- 0. 2 ;; .h::/:-
.u.,s. . , 4. . . r 3e .. . ..&.. ....s_ .a av en sv ypw
__m P
r Dissolved Oxygen f&eedt ' 3 ppb-(C:nd:n:::)Q -
5 10 ppd e-,. 4. . J. 3t , , ,u_
__m
- f. , u. . .
. f, A.
c . . . . u -...-..-L
.- , .A,rgw to p" C0-tr:1 Additive g
- r. --..
. ., , . . r, e a. . m.
..sM yya NOTES:
(1) Normal specifications are those which should be maintained during proper operation of secondary systems x at M7. PW.
(2) The condensate abnomal limit i s 10-30 ppb, but the requirement for imediate shutdown does not apply even if the problem is not corrected within 100 hrs.
res ,. ___n___2 _ _ _ _ < . _ , .
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Amendment No. 12 September 11, 1987 e.
c Enclosure (2)
.. to LD-88-034
, Page 9 of 10 s
This safetysystem is not required for the safe shutdown of the reactor and has no function.
12 10.4.4.4 Insoection and Testino Reouirements This system is non safety-related.
10.4.4.5 Instrumentation Aeolication The control system for the Turbine Bypass System is described in Section 7.7.1.1.5 (Steam Bypass Control System).
10.4.5 CIRCULATING WATER SYSTEM i ### 6*
b cbA h skhe d b rtyrAj (later - pending completion of EPRI Chapter 8) iA b ekA d h Nelkge4 kes, 12 10.4.6 CONDENSATE CLEANUP SYSTEM do teLx.e b paw d MA te. b hS hh4 h 4 (A rc\%
10.4.6.1 Desion Basis M ^b M *
- b 6 h OfM-The Condensate Cleanup System (CCS) is an integral part of the Condensate System. The CCS is designed to remove dissolved and suspended impurities which can cause corrosion damage to secondary system equipment. The CCS also removes to radioisotopes which might enter the system in the event of a primary secondary steam generator tube leak. The condensate polishing demineralizers (CPD) will also be used to remove impurities which could enter the system due to a condenser circulating water tube leak.
10.4.6.2 S_Ystem Oescriotion O h 2M-Yb The condensate cleanup system utilizes a side streagfull condensate flow polisher, located downstream of the condensate pumps. k 12 The final design and layout of the condensate cleanup system are described in the site-specific SAR. The following functional requirements are to be met to ensure a reliable system.
- 1. The polishing system ,is sized to meet the chemistry requirements for continuous operation specified in Section 10.3.5 while operating with a condenser leak of 0.001 gpm and to maintain water quality during an orderly unit shutdown (not longer than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) with a leak of 0.1 gpm irregardless of the type of cooling water.
- 2. The number and sizing of the ion exchangers are such that the functional requirements can be met while permitting the replacement of resin in one ion exchanger at a time.
- 3. Plant features are provided to facilitate replacement of ion exchange resin. No ion exchange resin regeneration system is provided.
- 4. Resin traps are installed down stream of each ion exchangerA cerote (wsWkim4.
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Amendment No. 12 10.4-8 September 11, 1987
[ .c
' Enclosure (2) to LD-88-034 Qh gS(-l2. Page 10 of 10
- 5. Design flow rates through the _ damina"li2eM are :1.(L._qpm/f t or less3 Minimum bed height is 3 ft.
C (4 M%McMo^ b rak.4
- 6. The demineralizer outlet lines vdukone bkreseA are fitted withhum .
individual fl)p%A p valves. w regulating
- 7. The system design pemits full flow recirculation through each ion exchanger for cleanup and verification of resin bed performance after resin replacement and prior to alignment within the system.
- 8. Ion exchanger isolation valve and recirculation valves are designed to permit slow, controlled opening to minimize hydraulic surges on the resin bed.
12 10.4.6.3 Safety Evaluation This system is non safety-related.
10.4.6.4 Inscection and Testino Recuirements This system is non safety-related.
10.4.6.5 Instrumentation Aeolications This system is non safety-related.
10.4.7 CONDENSATE AND FEE 0 WATER SYSTEMS 10.4.7.1 Desion Basis The Condensate and Feedwater Systems are designed to return condensate from the condenser hotwells to the steam generators. In addition, the systems include a number of stages of regenerative feed and condensate heating and provisions for maintaining feedwater quality.
The entire Condensate System is non safety-related. The portions of the Feedwater System that are required to mitigate the consequences of an accident and allow safe shutdown of the reactor are safety-related. The safety-related portions of the system are designed in accordance with the following design 12 bases:
- 1) The system is designed such that failure of a feedwater supply line coincident with a single active failure will not prevent safe shutdown of the reactor.
- 2) The system components are designed to withstand the effects of and perform their safety functions during a safe shutdoan earthquake.
- 3) Components and piping are designed, protected from, or located to protect against the effects of high and moderate energy pipe rupture, whip, and jet impingement which are not eliminated by leak-before-break analysis.
Amendment No. 12 10.4-9 September 11, 1987