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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20249C1601998-06-24024 June 1998 Transmits Revised Fda for Sys 80+ Design,Per App O of 10CFR52.Duration of Fda Conforms W/Duration of Design Certification Rule for Sys 80+ Std Design LD-98-009, Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. All CESSAR-DC Pages Designated Except for Listed Info1998-03-13013 March 1998 Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. All CESSAR-DC Pages Designated Except for Listed Info ML20203J3231997-12-17017 December 1997 First Partial Response to FOIA Request for Documents.Records in App a & B Encl & Will Be Available in PDR ML20149J7101997-07-23023 July 1997 Requests That R Simard Be Removed from Service Lists & R Bell Be Added to Svc Lists,Due to Recent NEI Reorganization LD-97-020, Requests That Errata Be Corrected in Errata Amend to Sys 80+ Design Certification Rule.Memo from Egan & Assoc to C Brinkman Which Lists Errata,Basis for Correction & Suggested Corrections Encl1997-06-13013 June 1997 Requests That Errata Be Corrected in Errata Amend to Sys 80+ Design Certification Rule.Memo from Egan & Assoc to C Brinkman Which Lists Errata,Basis for Correction & Suggested Corrections Encl LD-97-015, Informs That ABB-CE Has Completed Review of Effective Page Listing & Sys 80+ Design Control Document Revs Dtd Jan 19971997-05-0707 May 1997 Informs That ABB-CE Has Completed Review of Effective Page Listing & Sys 80+ Design Control Document Revs Dtd Jan 1997 LD-97-014, Transmits Final Version of Sys 80+ Design Control Document (DCD)1997-04-30030 April 1997 Transmits Final Version of Sys 80+ Design Control Document (DCD) ML20138E0301997-04-25025 April 1997 Informs That Portion of Info in Encl 1 of Vendor 960416 Submittal of Presentation Matl on ABB-C-E Licensing Plan for Full Batch Implementation of Abb Advanced Fuel for Meeting Held on 960416 W/Nrc Will Be Withheld,Per 10CFR2.790 ML20147C0881997-01-23023 January 1997 Responds to Requesting Opportunity to Review Design Certification Rule for Abb Combustion Engineering Sys 80+ Before Sending to Office of Fr for Publication ML20133A9791996-12-18018 December 1996 Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor ML20133A9811996-12-18018 December 1996 Informs That NRC Has Approved Rules Certifying Two Evolutionary Reactor Designs:Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energy ABWR ML20133A9871996-12-18018 December 1996 Informs of NRC Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-CE Sys 80+ & GE Nuclear Energy ABWR ML20133A9901996-12-18018 December 1996 Informs That NRC Has Approved Asea Brown Boveri CE Sys 80+ & GE Nuclear Energy ABWR as Evolutionary Reactor Designs ML20133B0191996-12-18018 December 1996 Informs of Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energys Advanced BWR LD-96-062, Requests Authorization to Conduct Narrowly,Focused Review of Design Certification Rule for Sys 80+ Before Sending of Office of Fr for Publication1996-12-18018 December 1996 Requests Authorization to Conduct Narrowly,Focused Review of Design Certification Rule for Sys 80+ Before Sending of Office of Fr for Publication LD-96-060, Forwards Rev to Sys 80+ Std Plant Design Control Document1996-12-13013 December 1996 Forwards Rev to Sys 80+ Std Plant Design Control Document ML20149M3091996-12-10010 December 1996 Responds to Which Requested Status of CESSAR-DC Relative to Fda for Sys 80+ Design ML20129E7111996-10-0101 October 1996 Forward RAI Re CENPD-137,Suppl 2-P, Calculative Methods for Abb CE Small Break LOCA Evaluation Model. Submittal Being Withheld from Public Disclosure Pending Staff Final Determination,Per 960523 Request LD-96-042, Submits Misleading Statement by BNL on C-E Reactor Coolant Pump Seals.Statement Correction Listed1996-09-26026 September 1996 Submits Misleading Statement by BNL on C-E Reactor Coolant Pump Seals.Statement Correction Listed ML20128P4981996-09-23023 September 1996 Forwards Proposed Rule Language for 3 Design Certifications Discussed at 960827 NRC Briefing ML20128N6001996-09-16016 September 1996 Provides Addl Info in Response to Several Questions Raised by Commission During 960827 Briefing on Design Certification Rulemaking LD-96-029, Forwards Finalized Package of Six Draft Changes to Sys 80+ Std Plant Design Control Document.Changes Will Be Formally Incorporated Into Sys 80+ Design Control Document at Conclusion of Design Certification Rulemaking1996-07-25025 July 1996 Forwards Finalized Package of Six Draft Changes to Sys 80+ Std Plant Design Control Document.Changes Will Be Formally Incorporated Into Sys 80+ Design Control Document at Conclusion of Design Certification Rulemaking LD-96-028, Submits Addl Draft Changes for Staff Review & Approval. Changes Listed on Attached Table W/Details Shown on Encl Design Control Document Pages1996-07-17017 July 1996 Submits Addl Draft Changes for Staff Review & Approval. Changes Listed on Attached Table W/Details Shown on Encl Design Control Document Pages LD-96-024, Transmits Finalized Package of Changes to Sys 80+ Std Plant Design Control Document1996-06-27027 June 1996 Transmits Finalized Package of Changes to Sys 80+ Std Plant Design Control Document LD-96-021, Submits Changes to Sys 80+ Std Plant Design Control Document as Requested by for Staff Review & Approval1996-06-11011 June 1996 Submits Changes to Sys 80+ Std Plant Design Control Document as Requested by for Staff Review & Approval ML20107G1451996-04-17017 April 1996 Transmits CEOG Task 931 Survey Questionnaire-CEA Insertion Experience W/High Burnup Fuel Mgt ML20101P1231996-03-15015 March 1996 Expresses Appreciation for Opportunity on 960308 to Brief Commission on Views on Design Certification Rules, Particularly W/Respect to Issue of Applicable Regulations LD-95-026, Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER1995-10-0606 October 1995 Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER LD-95-040, Forwards ABB-CE Proposed Statement of Considerations to Accompany ABB-CE Proposed Rule,Presented in Form of Complete Rulemaking Package1995-09-0505 September 1995 Forwards ABB-CE Proposed Statement of Considerations to Accompany ABB-CE Proposed Rule,Presented in Form of Complete Rulemaking Package ML20092D2561995-08-23023 August 1995 Forwards Correction to Comment 20 Re Proposed Design Certification Rules for Standardized Advancement Reactors. Last Line of Text May Have Been Lost Due to Word Processing Error ML20092D2871995-08-23023 August 1995 Forwards Correction to Comment 19 Re Proposed Design Certification Rules for Standardized Advanced Reactors. Last Line on First Page May Have Been Lost Due to Word Processing Error ML20085G2711995-06-14014 June 1995 Proposes to Respond to RAIs on GE TR NEDE-32177P, Tracg Computer Code Qualification, Dtd Jan 1993 in Three Groups as Indicated in Attachment ML20082G5511995-04-10010 April 1995 Provides Documents & Info Requested in NRC Audit (950407- 950410) Re Rv Fabrication ML20203J4371995-04-0404 April 1995 Forwards Fr Notice Re Proposed Amends to Commission Regulations for Commercial Npps,Adding New App a to 10CFR52 Which Will When Promulgated Certify Sys 80+ Std Design of ABWR LD-95-015, Transmits Corrected Page for Incorporation Into Sys 80+ DCD Revs1995-03-27027 March 1995 Transmits Corrected Page for Incorporation Into Sys 80+ DCD Revs LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE1995-03-24024 March 1995 Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE LD-95-011, Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page1995-03-17017 March 1995 Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page LD-95-003, Provides Addl Info on Removal of Auxiliary Throttle Seal Coolers from Reactor Coolant Pumps,In Response to NRC Questions from Review of Sys 80+ Design Control Document1995-03-0303 March 1995 Provides Addl Info on Removal of Auxiliary Throttle Seal Coolers from Reactor Coolant Pumps,In Response to NRC Questions from Review of Sys 80+ Design Control Document LD-95-007, Forwards Revised Sys 80+ Design Control Document1995-02-22022 February 1995 Forwards Revised Sys 80+ Design Control Document LD-95-006, Forwards mark-up Pages Identifying Revs Incorporated Into Sys 80+ Design Control Document. Revs Provided in Response to Comments Provided by NRC & as Result of Changes Identified by ABB-CE & Discussed W/Nrc1995-02-16016 February 1995 Forwards mark-up Pages Identifying Revs Incorporated Into Sys 80+ Design Control Document. Revs Provided in Response to Comments Provided by NRC & as Result of Changes Identified by ABB-CE & Discussed W/Nrc LD-95-001, Forwards Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accident Under NEPA for Plants of Sys 80+ Design1995-01-0606 January 1995 Forwards Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accident Under NEPA for Plants of Sys 80+ Design NRC-94-4383, Comments on Review of Draft NUREG-1512 for Proprietary Info1994-12-27027 December 1994 Comments on Review of Draft NUREG-1512 for Proprietary Info LD-94-072, Provides Justification for Tier 2 Seismic & Valve Testing Expirations1994-12-16016 December 1994 Provides Justification for Tier 2 Seismic & Valve Testing Expirations LD-94-073, Forwards Sys 80+ Design Control Document, Vols 1-241994-12-16016 December 1994 Forwards Sys 80+ Design Control Document, Vols 1-24 LD-94-071, Transmits Addl Input to System 80+ Design Control Document1994-12-15015 December 1994 Transmits Addl Input to System 80+ Design Control Document LD-94-069, Forwards marked-up CESSAR-DC Figure 5.1.2-2 Re Proposed Design Change to Remove RCP Seal Coolers1994-12-0808 December 1994 Forwards marked-up CESSAR-DC Figure 5.1.2-2 Re Proposed Design Change to Remove RCP Seal Coolers ML20078N8961994-12-0101 December 1994 Forwards Copy of Ltr NFBWR-94-033 ML20149H1941994-11-14014 November 1994 Responds to Indicating Concern Re Application of Set of Interrelated Elements That Defines Technical & Regulatory Aspects of design-basic Accident Source Term for Licensing of Passive Plants LD-94-065, Submits Proposed Language Related to Tier 2 for Sys 80+ Design Certification Rule1994-10-28028 October 1994 Submits Proposed Language Related to Tier 2 for Sys 80+ Design Certification Rule LD-94-063, Forwards Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design1994-10-10010 October 1994 Forwards Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design 1998-06-24
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARLD-98-009, Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. All CESSAR-DC Pages Designated Except for Listed Info1998-03-13013 March 1998 Forwards 3 Copies of Amend X to CESSAR-Design Certification (DC) Sys 80+ Std Plant Ssar Which Is Reprint of CESSAR-DC That Incorporates Revs Made to Approved Design Matl in Dcd. All CESSAR-DC Pages Designated Except for Listed Info ML20149J7101997-07-23023 July 1997 Requests That R Simard Be Removed from Service Lists & R Bell Be Added to Svc Lists,Due to Recent NEI Reorganization LD-97-020, Requests That Errata Be Corrected in Errata Amend to Sys 80+ Design Certification Rule.Memo from Egan & Assoc to C Brinkman Which Lists Errata,Basis for Correction & Suggested Corrections Encl1997-06-13013 June 1997 Requests That Errata Be Corrected in Errata Amend to Sys 80+ Design Certification Rule.Memo from Egan & Assoc to C Brinkman Which Lists Errata,Basis for Correction & Suggested Corrections Encl LD-97-015, Informs That ABB-CE Has Completed Review of Effective Page Listing & Sys 80+ Design Control Document Revs Dtd Jan 19971997-05-0707 May 1997 Informs That ABB-CE Has Completed Review of Effective Page Listing & Sys 80+ Design Control Document Revs Dtd Jan 1997 LD-97-014, Transmits Final Version of Sys 80+ Design Control Document (DCD)1997-04-30030 April 1997 Transmits Final Version of Sys 80+ Design Control Document (DCD) LD-96-062, Requests Authorization to Conduct Narrowly,Focused Review of Design Certification Rule for Sys 80+ Before Sending of Office of Fr for Publication1996-12-18018 December 1996 Requests Authorization to Conduct Narrowly,Focused Review of Design Certification Rule for Sys 80+ Before Sending of Office of Fr for Publication LD-96-060, Forwards Rev to Sys 80+ Std Plant Design Control Document1996-12-13013 December 1996 Forwards Rev to Sys 80+ Std Plant Design Control Document LD-96-042, Submits Misleading Statement by BNL on C-E Reactor Coolant Pump Seals.Statement Correction Listed1996-09-26026 September 1996 Submits Misleading Statement by BNL on C-E Reactor Coolant Pump Seals.Statement Correction Listed ML20128P4981996-09-23023 September 1996 Forwards Proposed Rule Language for 3 Design Certifications Discussed at 960827 NRC Briefing ML20128N6001996-09-16016 September 1996 Provides Addl Info in Response to Several Questions Raised by Commission During 960827 Briefing on Design Certification Rulemaking LD-96-029, Forwards Finalized Package of Six Draft Changes to Sys 80+ Std Plant Design Control Document.Changes Will Be Formally Incorporated Into Sys 80+ Design Control Document at Conclusion of Design Certification Rulemaking1996-07-25025 July 1996 Forwards Finalized Package of Six Draft Changes to Sys 80+ Std Plant Design Control Document.Changes Will Be Formally Incorporated Into Sys 80+ Design Control Document at Conclusion of Design Certification Rulemaking LD-96-028, Submits Addl Draft Changes for Staff Review & Approval. Changes Listed on Attached Table W/Details Shown on Encl Design Control Document Pages1996-07-17017 July 1996 Submits Addl Draft Changes for Staff Review & Approval. Changes Listed on Attached Table W/Details Shown on Encl Design Control Document Pages LD-96-024, Transmits Finalized Package of Changes to Sys 80+ Std Plant Design Control Document1996-06-27027 June 1996 Transmits Finalized Package of Changes to Sys 80+ Std Plant Design Control Document LD-96-021, Submits Changes to Sys 80+ Std Plant Design Control Document as Requested by for Staff Review & Approval1996-06-11011 June 1996 Submits Changes to Sys 80+ Std Plant Design Control Document as Requested by for Staff Review & Approval ML20107G1451996-04-17017 April 1996 Transmits CEOG Task 931 Survey Questionnaire-CEA Insertion Experience W/High Burnup Fuel Mgt ML20101P1231996-03-15015 March 1996 Expresses Appreciation for Opportunity on 960308 to Brief Commission on Views on Design Certification Rules, Particularly W/Respect to Issue of Applicable Regulations LD-95-026, Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER1995-10-0606 October 1995 Requests Addl Explanation of Probablistic Risk Assessment. Request for Clarification & Does Not Impact Conclusions of Evaluation Already Reported in FSER LD-95-040, Forwards ABB-CE Proposed Statement of Considerations to Accompany ABB-CE Proposed Rule,Presented in Form of Complete Rulemaking Package1995-09-0505 September 1995 Forwards ABB-CE Proposed Statement of Considerations to Accompany ABB-CE Proposed Rule,Presented in Form of Complete Rulemaking Package ML20092D2561995-08-23023 August 1995 Forwards Correction to Comment 20 Re Proposed Design Certification Rules for Standardized Advancement Reactors. Last Line of Text May Have Been Lost Due to Word Processing Error ML20092D2871995-08-23023 August 1995 Forwards Correction to Comment 19 Re Proposed Design Certification Rules for Standardized Advanced Reactors. Last Line on First Page May Have Been Lost Due to Word Processing Error ML20085G2711995-06-14014 June 1995 Proposes to Respond to RAIs on GE TR NEDE-32177P, Tracg Computer Code Qualification, Dtd Jan 1993 in Three Groups as Indicated in Attachment ML20082G5511995-04-10010 April 1995 Provides Documents & Info Requested in NRC Audit (950407- 950410) Re Rv Fabrication LD-95-015, Transmits Corrected Page for Incorporation Into Sys 80+ DCD Revs1995-03-27027 March 1995 Transmits Corrected Page for Incorporation Into Sys 80+ DCD Revs LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE1995-03-24024 March 1995 Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE LD-95-011, Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page1995-03-17017 March 1995 Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page LD-95-003, Provides Addl Info on Removal of Auxiliary Throttle Seal Coolers from Reactor Coolant Pumps,In Response to NRC Questions from Review of Sys 80+ Design Control Document1995-03-0303 March 1995 Provides Addl Info on Removal of Auxiliary Throttle Seal Coolers from Reactor Coolant Pumps,In Response to NRC Questions from Review of Sys 80+ Design Control Document LD-95-007, Forwards Revised Sys 80+ Design Control Document1995-02-22022 February 1995 Forwards Revised Sys 80+ Design Control Document LD-95-006, Forwards mark-up Pages Identifying Revs Incorporated Into Sys 80+ Design Control Document. Revs Provided in Response to Comments Provided by NRC & as Result of Changes Identified by ABB-CE & Discussed W/Nrc1995-02-16016 February 1995 Forwards mark-up Pages Identifying Revs Incorporated Into Sys 80+ Design Control Document. Revs Provided in Response to Comments Provided by NRC & as Result of Changes Identified by ABB-CE & Discussed W/Nrc LD-95-001, Forwards Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accident Under NEPA for Plants of Sys 80+ Design1995-01-0606 January 1995 Forwards Rev 2 to Technical Support Document for Amend to 10CFR51 Considering Severe Accident Under NEPA for Plants of Sys 80+ Design NRC-94-4383, Comments on Review of Draft NUREG-1512 for Proprietary Info1994-12-27027 December 1994 Comments on Review of Draft NUREG-1512 for Proprietary Info LD-94-072, Provides Justification for Tier 2 Seismic & Valve Testing Expirations1994-12-16016 December 1994 Provides Justification for Tier 2 Seismic & Valve Testing Expirations LD-94-073, Forwards Sys 80+ Design Control Document, Vols 1-241994-12-16016 December 1994 Forwards Sys 80+ Design Control Document, Vols 1-24 LD-94-071, Transmits Addl Input to System 80+ Design Control Document1994-12-15015 December 1994 Transmits Addl Input to System 80+ Design Control Document LD-94-069, Forwards marked-up CESSAR-DC Figure 5.1.2-2 Re Proposed Design Change to Remove RCP Seal Coolers1994-12-0808 December 1994 Forwards marked-up CESSAR-DC Figure 5.1.2-2 Re Proposed Design Change to Remove RCP Seal Coolers ML20078N8961994-12-0101 December 1994 Forwards Copy of Ltr NFBWR-94-033 LD-94-065, Submits Proposed Language Related to Tier 2 for Sys 80+ Design Certification Rule1994-10-28028 October 1994 Submits Proposed Language Related to Tier 2 for Sys 80+ Design Certification Rule LD-94-063, Forwards Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design1994-10-10010 October 1994 Forwards Rev 1 of Technical Support Document for Amends to 10CFR51 Considering Severe Accidents Under NEPA for Plants of Sys 80+ Design ML20072T2691994-08-30030 August 1994 Advises That Industry Intends to Comment in Opposition to Applicable Regulations Approach & Proposed Text of Applicable Regulations in Design Certification Rulemaking Proceeding for Both ABWR & Sys 80+ LD-94-059, Forwards Draft Notice of Issuance of EA & Draft Fonsi, Together W/Supporting Draft Proposed EA for Consideration,W/ Respect to Draft EA NRC Producing for Proposed Sys 80+ Design Process1994-08-22022 August 1994 Forwards Draft Notice of Issuance of EA & Draft Fonsi, Together W/Supporting Draft Proposed EA for Consideration,W/ Respect to Draft EA NRC Producing for Proposed Sys 80+ Design Process ML20072B9641994-08-12012 August 1994 Requests That Author Name Be Added to Sys 80+ Service List. Author Counsel to Westinghouse in AP600 Design Certification ML20072E3561994-08-0909 August 1994 Requests Addition of Author Name to Sys 80+ Svc List ML20073E1721994-07-25025 July 1994 Forwards Rept Entitled, Analysis of Ex-Vessel Steam Explosions for Combustion Engineering Sys 80+ Using Gtsf Computer Code. Provides Comments on Central,Outer & Multiple Instrument Tube Failures LD-94-054, Forwards Errata to Sys 80+ Certified Design Matl,In Response to Editorial & Word Processing Errors1994-07-21021 July 1994 Forwards Errata to Sys 80+ Certified Design Matl,In Response to Editorial & Word Processing Errors LD-94-052, Requests That Service List for Docket 52-002 Be Updated in Accordance W/Encl Listing,Due to Changes in Position Titles, Affiliations & Organizations.Correspondence on Docket 52-002 Should Be Addressed to Listed Address1994-07-20020 July 1994 Requests That Service List for Docket 52-002 Be Updated in Accordance W/Encl Listing,Due to Changes in Position Titles, Affiliations & Organizations.Correspondence on Docket 52-002 Should Be Addressed to Listed Address LD-94-053, Seeks Confirmation of Vendor Understanding of NRC Fee Regulations in 10CFR170 as Pertaining to Sys 80+ Design Certification Rulemaking as Set Forth in Encl1994-07-20020 July 1994 Seeks Confirmation of Vendor Understanding of NRC Fee Regulations in 10CFR170 as Pertaining to Sys 80+ Design Certification Rulemaking as Set Forth in Encl LD-94-048, Forwards Certified Design Matl Related to Design Reliability Assurance Program & Corresponding Errata Pages for CESSAR-DC (Section 1.0,17.3 & 19.15) Amend W,To Resolve NRC Comments Received by Telcon Over Past Two Wks1994-07-12012 July 1994 Forwards Certified Design Matl Related to Design Reliability Assurance Program & Corresponding Errata Pages for CESSAR-DC (Section 1.0,17.3 & 19.15) Amend W,To Resolve NRC Comments Received by Telcon Over Past Two Wks ML20077F4111994-07-0808 July 1994 Forwards Technical Evaluation Rept Entitled, an Analysis of Core Meltdown Accidents in CE Sys 80+ Plant Using Melcor LD-94-047, Forwards Replacement Page for System 80+ Emergency Operations Guidelines1994-06-28028 June 1994 Forwards Replacement Page for System 80+ Emergency Operations Guidelines LD-94-046, Submits Sys 80+ Design & Operational Features Re Deviations from Regulations1994-06-27027 June 1994 Submits Sys 80+ Design & Operational Features Re Deviations from Regulations LD-94-044, Forwards Revised Combustion Engineering Standard Safety Analysis Rept - Design Certification,Amend W & Affidavit1994-06-20020 June 1994 Forwards Revised Combustion Engineering Standard Safety Analysis Rept - Design Certification,Amend W & Affidavit 1998-03-13
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A RD EB LFARH99 ASEA BROWN DOVERf June 29, 1993 LD-93-104 Mr. Dennis M. Crutchfield Associate Director for Advanced Reactors & License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Special ITAAC Submittal Reference- Letter, R. A. Matzie (ABB-CE) to S. J. Chilk (NRC),
dated May 27, 1993
Dear Mr. Crutchfield:
We have submitted, by separate correspondence, the set of Design Descriptions and Inspections, and Acceptance Criteria (DD/ITAAC) for System Tesg 80+ , hichAnalyses w ABB-CE believes are needed to meet 10 CFR Part 52 requirements.
The NRC staff has requested three additional DDs and two additional ITAAC covering the Initial Test Program (ITP), the Design Reliability Assurance Program (D-RAP), and Plant Operating Procedures (POPS). ABB-CE objects to the inclusion of these DDs and ITAAC because we regard them as programmatic and, therefore, unnecessary and not readily amenable to unambiguous and meaningful acceptance criteria.
In the reference letter, we recited in detail our objections to elevating the D-RAP to DD/ITAAC status. We acknowledge your response saying our arguments did not change the staff's opinion.
We continue to await the Commission's decision on this issue. In the meantime, so as to avoid impacting the System 80+ review schedule, we are forwarding a proposed D-RAP DD which can be used during the ITAAC reviews with the understanding it will be retracted if the Commission agrees with our request.
The ITP DD/ITAAC is submitted on the same basis and we ask the staff to reconsider its necessity when the Commission rules on the D-RAP issue.
ABB Combustion Engineering Nuclear Power
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l Mr. Dennie M. Crutchfield LD-93-104 June 29, 1993 Page 2 We believe the POP issue should be a COL action item and not be elevated to DD/ITAAC status as a programmatic ITAAC. We are deferring submittal of a POP DD/ITAAC pending the outcome of further discussions on this issue.
We hope this submittal will facilitate the System 80+ review whila preserving ADB-CE's right to request reconsideration of staff positions we believe not to be in the best interest of the ultimate COL holder.
Thank you for your cooperation in this matter.
Very truly yours, b kbn A~
C. B. Brinkman Acting Director Nuclear Systems Licensing GDH/ak cc: P. Lang (DOE)
J. Trotter (EPRI)
K. Karr (INPO)
R. Mcdonald (ARC)
T. Wambach (NRC)
A. Heymer (NUMARC) w . ,
y - - . - -_ ._. _
0 4
l 1
SYSTF.M 80+" !
2.11 INITIAL TEST PROGRAM l
An Initial Test Program (ITP) is performed following completion of construction ;
activities and construction-related inspections and tests and extends to a declaration of commercial operation. The ITP has preoperational and startup test phases.
The preoperational test phase of the ITP consists of those test activities conducted prior to fuel loading. Preoperational testing is conducted to demonstrate that structures, systems, components, and design features of the as-built plant meet the performance requirements of the design. Equipment functional tests, system operational tests, and system vibration and expansion measurements are conducted during preoperational testing.
The startup test phase of the ITP begins with fuel loading and extends to a declaration of commercial operation. Startup testing is conducted to demonstrate that the integrated plant with the nuclear fuel in the reactor pressure vessel meets the
- performance requirements of the design. Startup testing is performed with the plant operating at power levels ranging from zero power to full rated power. Startup testing is conduct ed at five test conditions: open vessel (fuel load), heatup, low power, mid-power, and high power. Startup testing includes testing of:
nuclear fuel system performance, steady-state plant performance, control system performance, and transient performance.
The ITP is performed using detailed preoperational and startup procedures to control the conduct of testing. Detailed test procedures delineate the test methods to be used and the applicable acceptance criteria against which performance is evaluated.
Test procedures are developed from preoperational and startup test specifications.
Administrative procedures are used to control the conduct of the test program; the review, evaluation and approval of test results; and test record retention.
The tests specified in Section 2.0 are a subset of the ITP.
2.11 . . -
.. _ ~ - ..
SYSTEM 80+"
3.3 DESIGN-RELIABILITY ASSURANCE PROGRAM A Design-Reliability Assurance Program (D-RAP) is conducted during the detailed design and through the equipment selection phase. 'Ihe D-RAP provides a means to factor into the detailed design, important reliability aspects from risk assessment.
The D-RAP identifies those systems, structures, and components (SSCs) whose reliability is significant to plant safety based on risk assessment. Relevant experience with significant SSCs can also be factored into the D-RAP.
The D-RAP factors the relative safety importance of SSCs into the detailed design and procurement processes, such that the reliability of SSCs of the certified design maintains the bases for the risk assessment.
The D-RAP provides risk significant information as input to the COL applicant for ;
use in developing operating and maintenance programs for the plant.
33 -- ,-, _