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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
[Table view] |
Text
w .
April 26, 1994
' LD-94-027 Docket No. 52.-002 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington. D.C. 20555
Subject:
System 80+" Exemptions From Regulations
Dear Sirs:
In response to a request fror;: the NRC Project Directorate, ABB-CE is submitting the attached summary of System 80+ design and operational features which involve deviations from current regulations. These features have been reviewed by NRC staff and the exemptions summarized in the attachment are consistent with those in the advance copy of the System 80+ Final Safety Evaluation Report.
The attachment summarizes the basis for each of the exemptions, consistent with the requirements of 10 CFR 50.12. It is ABB-CE's understanding that the acceptability of the exemptions and corresponding System 80+ features will be datumented in the Final Safety Evaluation Report (NUREG-i;$2) and will be codified during the System 80+ Design Certification rulemaking.
If you have any questions, please call me or Mr. Stan Ritterbusch at (203) 285-5206.
Very truly yours, COMBUSTION ENGINEERING, INC.
C. B. Brinkman Director Nuclear Systems Licensing CBB/ser cc: 1. Trotter (EPRI)
T. Wambach (NRC)
P. Lang (DOE) p p n r, r
_ - - u - m t u o ~ _..
ABB Combustion Engineering Nuclear Power d
y Conte,tum Dymero Irc f O E x N.o Tek
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9405060298 940426 wirca ci wse l PDR ADOCK 05200002 A PDR
i .
. ATTACHMENT 1 Summary of System 80+ Deviations From NRC Reaulations The following paragraphs summarize System 80+ deviations from NRC regulations, it is ABB-CE's understanding that NRC staff agrees with the deviations, as documented in the advance copy of the System 80+
Final Safety Evaluation Report.
10 CFR 50.34[f) - Compliance with the " TID 14844" Radioloaical Source l Termt i
Paragraph 2(xxviii) of this regulation requires the evaluation of pathways that may lead to control room habitability problems "under accident conditions resulting in a TID 14844 source term release".
Similar wording appears in subparagraphs vii, viii, and xvi. ABB-CE has implemented the new source term technology summarized in Draft NUREG-1465 and Appendix 15A of'the Combustion Engineering Standard Safety Analysis Report for Design Certification (CESSAR-DC). NRC staff has encouraged the development and implementation of the new source term technology (re: letter to ABB-CE, dated October 19, 1992).
Our understanding of the NRC staff position is that the new source term must be used consistently and that the old TID source term could not be used for equipment qualification if the new source term were implemented in the accident analysis of CESSAR-DC, Chapters 6,15, and 19. We have, therefore, implemented the new source term for equipment qualification (Section 3.11 of CESSAR-DC) as well as for the accident analysis. The NRC staff's concurrence is documented in the advance copy of the Final '
Safety Evaluation Report (FSER), Section 3.11.3.2 and Appendix 15A.
l This approach and its inherent conservatism meets exemption criteria !
(a)(1), (a)(2)(ii), and (a)(2)(iii) of 10 CFR 50.12.
l L0 CFR 100 - Elimination of the Operatina Basis Earthauake Subsection IV, paragraph (a)(2) of 10 CFR 100, Appendix A, requires that structures, systems and components be designed to remain functional when subjected to an Operating Basis Earthquake (0BE). The NRC staff and industry groups have analyzed in detail the problems associated with including the OBE in the design of plant piping and equipment support systems (e.g., see SECY-93-087). ,
i System 80+ is designed for Safe Shutdown Earthquake of 0.39 and it has been shown that all design basis safety criteria are met. Removal of i
~ w , -- --m w- m -
.the OBE decreases the number of analyses required and.results in '
" improved (and simplified) piping and equipment support systems.
llowever, plant safety has not been decreased. NRC staff concurrence is documented in the advance copy of the System 80+ FSER, Section 3.1.1.
i The System 80+ design analysis performed using the Safe Shutdown Earthquake complies with exemption criteria (a)(1), (a)(2)(ii), and (a)(2)(iii) of 10 CFR 50.12.
10 CFR 50.34(f) - Dedicated Vent for Severe Accident Mitiaation Paragraph (3)(iv) of 10 CFR 50.34(f) states that designs should provide "one or more dedicated containment penetrations, equivalent in size'to a single 3-foot diameter opening, in order to not preclude future installation or systems to prevent containment failure". System 80+
advanced design features address all severe accident issues, including containment integrity, overpressurization, and the need for venting; however, a dedicated vent and/or its penetration are not included in the design.
Based on the System 80+ Probabilistic Risk Assessment, the containment failure probability given a severely damaged core is only 4% (i.e., the probability of maintaining containment integrity, given a severely damaged core, is 96%), as documented in Section 19.12.2.3 of CESSAR-DC.
Due to the robustness of the System 80+ containment design, a dedicated filtered containment vent is approximately seven orders of magnitude from being cost effective (see CESSAR-DC, Appendix 19A, Table 19A.2-1).
This evaluation of System 80+ containment integrity meets exemption criteria (a)(1), (a)(2)(ii), and (a)(2)(iii) of 10 CFR 50.12.
10 CFR 50. Anp_endix J - Assumptions for leak Rate Testing Strict application of Appendix J would not allow isolation, repair, or adjustment to a leakage barrier during a " Type A" test. However, consistent with common practice, isolation or repair of certain leaks are allowed for the System 80+ design (see CESSAR-DC, Section 6.2.6 for details).
Based on a proposed revision to Appendix J and specific conditions identified in Section 6.2.6 of the System 80+ FSER, the NRC staff has concurred with this exemption. This evaluation meets exemption criteria (a)(1), (a)(2)(ii), and (a)(2)(iii) of 10 CFR 50.12.
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l 10 CFR 50.34(f) - Post-Accidgnt Samolina System (PASS) Desian i
Paragraph (2)(viii) of 10 CFR 50.34(f) requires the capability to obtain l and analyze samples of reactor coolant for certain materials, including l chloride. The System 80+ post-accident sampling design, Section 9.3.2
, of CESSAR-DC, does not require the capability for chloride analysis.
In its response to NRC staff's policy paper SECY-03-087, the Commission deleted the requirement for post-accident sampling for chlorides (see the Commission's staff requirements memorandum dated July 21,1993).
The staff documented its recognition that chloride sampling was not a requirement in the advance copy of the System 80+ FSER, Section 9.3.2, Based on the documentation in SECY-93-087 and the Commission's response, I the System 80t PASS meets exemption criteria (a)(1), (a)(2)(ii), and j (a)(2)(iii) of 10 CFR 50.12.
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