|
---|
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
..
7 Sandia National Laboratories Albuquerque, New Mexico 87185 December 13, 1993 Asimios Malliakos, Ph.D.
Research/ Accident Evaluation Branch Of6ce of Nuclear Regulatory Research MS: NLN-344 U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Cundensation Test Procedures and Results
Dear Dr. Malliakos:
A series of tests to be conducted in the Surtsey Test Facility will determine igniter effectiveness in rapidly condensing steam environments. These tests will be performed by the Severe Accident Phenomenology Department, 6422, as part of the U. S. Nuclear Regulatory Commission's effort on severe accident research. Experiments with both well-mixed and stratified hydrogen will be performed. The three objectives of the experiments are to determine: (1) if energetic forms of combustion are possible when originally non-flammable hydrogen / air / steam mixtures are ignited while the mixture is de-inerted by water sprays, (2) the effectiveness of water sprays in mixing hydrogen, and (3) the effect of hydrogen strat!Gcation on the maximum combustion pressure.
For the combustion tests, the Surtsey vessel is first heated internally with steam and externally with a liquid propane gas burner to ensure steam pressurization and ta minimize
:c.m condensation while setting the initial atmosphere conditions. After heatup, the general procedure of the experiments is to initially inert the Surtsey vessel with saturated steam.
After inerting the vessel, the vessel will be pressurized with saturated steam (413 K) to about l 0.36 MPa. Hot air (413 K) is then added to increase vessel pressure by about 0.12 MPa.
l The air concentration will be =24 mol.%. The gases are mixed using three 1000 cfm '
pneumatica!!y operated fans installed inside the Surtsey vessel. In the well-mixed experiment, heated hydrogen (413 K) is added with the fans operating until its final concentration is =4 mol.%. The final vessel temperature and pressure prior to operation of the sprays will be approximately 413 K and 0.50 MPa. After verifying the glow plug igniters are operating nominally, the water spray will be initiated. The target spray nozzle j flow rate and the temperature of the spray water are 23.3 gpm and 323 K. The spray is '
upected to operate up to and after the combustion event. Enough water is available to provide 21 minutes of spray at the nominal spray flow rate.
The procedure for the stratified experiments is nearly identical to the procedure for the well mixed tests. The main difference is that the hydrogen injection point is located l
,- s l
/ t
'NN d Enclosure 3
]
{ .,
approximately in the middle of the Surtsey vessel and the mixing fans are turned off prior to the addition of hydrogen. The target conditions are to have stoichiometric mixtures above l the injection point and no hydrogen below. This would result in mixtures with 78 mol.% !
hydrogen above the injection point before the operation of the sprays.
A well mixed condensation test was performed on November 19, 1993 after the Surtsey venel had been instrumented, sealed, and pressure tested. This test was a prerequisite for the igniter effectiveness combustion tests. Figures 1-3 give isometric views of the Surtsey vessel. Figure I shows the floor subdividing the vessel to provide a freeboard volume of 2
59.1 m . Figures 2 and 3 show instrumentation and instrument locations. The vessel heatup commenced at 1600 on November 18. The portable steam boiler provided a low-pressure, saturated steam heat source to Surtsey. Initially, the steam that entered Surtsey condensed and provided latent heat to the vessel walls and atmosphere. A steam trap allowed removal of the condensate without removing gases. As the vessel heated, the steam condensation rate decreased and the vessel began to pressurize. The liquid propane gas burner mounted under the dividing Soor was controlled to match gas temperatures above and below the floor during the heatup to minimize structural stress and heat loss. The heatup was completed at 0700 on November 19; the vessel pressure and temperature was 0.54 MPa and =424 K.
% vessel has a small, known leak rate, about 0.0046 MPa/hr. As the vessel is pressurized with steam, small amounts of air and steam leak out. Prior to the test, the vessel was inerted completely with steam to ensure a known initial atmosphere condition. A series of vessel fill and vents was performed. The vessel was vented to near atmospheric pressure and then refilled with steam to a pressure of about 0.25 MPa. This was performed five times and the entire procedure lasted about two hours.
Air (1665 g moles) and helium (266 g moles) was then added to the vessel. Standard compressed gas cylinder are used. The gases pass through a heat exchanger, where they were heated to 403 K prior to entering the vessel. Since this was about 10 K below the saturation temperature, some steam condensed and it was necessary to add a small amount of mam ..ner the noncondensible gases were added.
The initial test pressure in the Surtsey vessel was 0.4750 MPa and the gas temperature was 419 K. The initial vessel atmosphere concentrations were 76.05 mol.% steam,20.65 mol.%
air,4.32 mol.% oxygen, and 3.30 mol.% helium. Disregard the preliminary gas concentrations reported on December 1. They were estimated based on nominal compressed gas cylinder information reported by the gas supplier. The new concentrations are based on the actual amounts of gas (from pressure and temperature measurements) from the cylinders that were used during the test.
There was a small amount of water on the floor prior to initiating the spray. The use of the steam trap to remove the floor condensate was discontinued during the test due to a non-test related discharge permit problem. The water could be seen with the camera mounted on a level 4 port penetration and it is estimated that the water level was about 3-5 cm. After spray initiation, the camera view showed what appeared to be a ' light rain' inside the vessel.
Figures 4 and 5 showed that the vessel pressure and bulk gas temperature steadily decreased o - ~
1 during the spray down. The average bulk gas temperature was calculated by averaging the temperature data obtained from the five vertical thermocouple arrays, shown in Figures 6-10.
The bottom thermocouple on each array showed water reaching the 15 cm level at about 9-10 minutes after spray initiation. (Thermocouple 41 on array A is not shown on Figure 6 since its amplifier was used for another purpose during this test.)
Figure 1i shows the vessel floor, wall, and dome temperatures. The three floor thermocouples showed good agreement, irdicative of water on the floor. The two ' wetted-wall' thermocouples (Ch38 and Ch88) showed lower and more erratic temperatures due to "emer s: reaming down the walls as compared to the upper wall thermocouples (Ch37 and Ch87). These thermocouples were mounted near the upper head flange and were located just above the sprayed-unsprayed transition boundary. The upper wall thermocouples and the dome thermocouple showed good temperature agreement.
Figures 12 and 13 give the spray nozzle flow rate and water temperature. The spray flow rate was 30.5 gpm. This slightly exceeded the target value of 23.3 gpm. The vessel was sprayed with hot (321 K) water for 16.3 minutes, until the spray tank emptied. The total amount of . vater that was sprayed was 497 gallons. Air (driving the water spray) flowed into the vessel for about one minute after the water spray tank emptied. This caused Surtsey sessel pressure to increase about 0.04 Mpa.
Figures 14 and 15 give the time-dependent vessel steam, oxygen, and helium fractions. The fractions were calculated using the measured pressure and calculated average gas temperature data along with P,V,T ideal-gas law relationships. It was assumed that the air and helium noncondensible gas amounts remained constant at the initial values throughout the test.
The Onal (t= 16.3 min) vessel pressure and temperature was 0.1827 MPa and 367 K. The final atmosphere concentrations were 45.42 mol.% steam,47.06 mol.% air,9.84 mol.%
oxygen, and 7.72 mol.% helium. Table 1 summarizes the initial and f' mal conditions for the HIT-1 well-mixed condensation experiment.
..e ntacondeasible gas heat exchanger will be modified to ensure that the hot gas entering Surtsey will not condense steam. Also, the pressure regulator that controls the water spray flow rate will be adjusted under nominal, prototypic test conditions to meet the 23.3 gpm targe Row rate. Permits have already been obtained that allow the discharge of condensate water and boiler cooling water.
If you have questions or need any further assistance, do not hesitate to call me at (505) 845-3048 or FAX (505) 845-3435.
Sincerely, Thomas Blanchat Severe Accident Phenomenology Department 6422 s:
I i
Table 1 '
Initial and Final Conditions for the HIT-1 Well Mixed Condensation Experiment j i
j Initial Final (t=0 min) (t = 16.3 min)
Absolute pressure in Surtsey (MPa) 0.4750 0.1827 Gas temperature in Surtsey (K) 419 367 Total gas moles in Surtsey (g moles) 8061 3537 Gas composition in Surtsey Steam 76.05 45.42 (mol. %) Air 20.65 47.06
- 0 2 4.32 9.84 L
H 2 3.30 7.52 l Surtsey floor temperature (K) 414 383 Surtsey wall temperature (K) 414 390 Surtsey dome temperature (K) 413 397 Spray nozz!e water flowrate (gpm) 30.5 l Spray nozzle water temperature (K) 321 l Freeboard volume inside Surtsey 59.1 m' Copies:
NRC C. Tinkler 6429 D. Stamps 6422 M. Allen 6422 R. Nichols
{
_ . _ _ - _ -- __ m - -
I SURTSEY I l
VESSEL # '
TC E UPPER
i i k
C tlg
^
TC A y
Y jI TC D s ,,
TC B g ;p;;
te .
gj;
~
, j TC C%
! ,, Ml ': FLOOR
, ' bi; . ,,.[
b f'J. *?w
] tm A
..!l '
- ~ ja!.a - )1 1
g E *@
3 Ni
&:. tz s "
LOWER l _
N~
CATWALK 4 4 Figure 1. Location of the igniter effectiveness test in the Surtsey vessel. . _ _ .__
SPRAY NOZZLE FAN 3X H2 DOWN FAN IGNITOR ,
it TO A
'~
.jj l e :jI U!
O b
a vn fk!!!
g i inf6
- g1
l
? :., _
$p, '
i ~
- . flj[ 3X H2 l INJECTOI
! .$f s.
!RL 5?B$
TC B 10X H2 TC C TC E FLOOR SENSOR TO D FAN Figure 2. Igniter test instrumentation, mixing fans, hydrogen injectors, and spray nozzle.
.l
~~.5:.'.'000CPLE E m
- p fan, s
N Nl 8 OWN FAN
~
,,, s SENSOR EL 4.877 M N '
"F
, s .L 5.029 M f.7
+-
-- N I" '; - - IGNITER EL 4.524 M N
in %
%' CE' I-A E. 4 -ID Um.k h )1/ (' ,w
,- .L 4.420 M LF j by SENSOR EL 3.962 M
- . TE: :._ !.7:2 *.' w I l
f- y-EL 3.8:0 M
. . . . . . . . _ . . , ,- M
-. ..:....- : : . ::. Ms , i e t' -H2 SENSOR EL 3.048 M
,:= u.s.:: J N ~
_ N.L - ' * "
~
[)-EL 2.59
.2
"EC708 E' 2'7CI" Y a' lg y it..s0R I . fat M l =d= -H 2 SENSOR EL 2.134 M
%# g-~ -
f (")m f{ gL l.981 M l
'((
li i I
.e.ta:
3-
.~ . , . - . . . _)y j ,
SENSOR EL 1.2!9 M l
/ -r
-# y f
f# l I 2
IGNITER EL 1.088 M
_ ' ' . F a '; n===
7i h '
YL l.372 M 1
- !( l.
4
- % := ~ l l
- .. c
- =.e_ ::s t w n ] ,
T)
.,,,.</l & 3
~
.( R -
l vd \
N NL .762 M
\
3::. .. .,s. . ..: . .f 7 .
N -THERMOCOUPLE B
,,[ \\
\
--EL .152 M 7, g:..;;;ng : /
P \s THERMOCOUPLE A b SENSOR EL .305 M N 2 F%ur 3. LO:nion of the instrumentation in the igniter effectiveness test.
1 1
0.6 ,
T 1
I l
~
n 0. 4- -
as (L
v o
L
- )
m 0.3 -
m O
M (L
i
~
! 0.2 -
?
i . . . . . . i. . . . . i . .
1 O 5 10 15 20 Experiment Time (min)
I Figure 4. Surtsey vessel pressure in.the IIIT-1 well-mixed condensation test.
I i
l l
2 420 n
M v
e 400 -
p p
a e
L o
a b
o 380 - -
8 360 - - - - - - -
0 5 10 15 20 Experiment Time (min)
Figure 5. Surtsey vessel average gas temperature in the condensation test.
w l
{ , , , ,
3
, ,r-- . .
'T, Ch41 (bottonn)
- 440 -
~ 'e t Ch42
/ /
ti ---- Ch43
~
\g g ------
Ch44 gf -
Ch45
^ '
g ...-, - - - Ch46 s- 420 6 = 'c. 's - - - - Ch47 -
,, . 'll . Ch48 Q) :
'" - >% 4 y/
g ,,
p
.s
\g N
Ch49 (top) s x s: . .* . .y. en . t.
4 ti. 4 e o. }gi '.
' 400 ' .- s ' i*"i(i. v 4
o s -<-:g-e a
y
- s. ,
.v-a ,aw.
sn,- s,
, .s e .
~. w. , . ts s e.;; %
s
-* - bg.,,. N,'
O s. -s _ _ . .
380 - *
.N\ g .
~. ~
. _ - . =
% f r% .. . , -n ]
- m. % . s,,-
< :z . . - -=,--
' :-M w:z:.s :._. p, -
~, -
~ ~.4. < a:s
- g,.v" -T.j .
360 - - - - - - - - -
0 5 10 15- 20 Experiment Time (min)
Figure 6. Surtsey vessel gas temperatures from the A thermocouple array in the condensation test.
~ .
. i b
l 5
T I I '
I 4 i-Ch50 (bottom) '
Cn51 440 -
-I
Ch52
Ch53 Ch54 em ---- Ch55 xg
- - - - Ch56 -
v 420 Qss fN. . . . . ,h. ' s s Ch57 g
L N --
Ch58 (top)
'%g.. , v c
o t a5 - .s3 s. . t
" 400
'l ' '. '. s s o .
. Cl 4 s If N ,
a\ g, c*. .
D : s-E-4
- 'e. c. , \ j 7
s.,c, s 380 -
~
pr e -=
?'.t.Q2.:..
.o .s _ " %
- n... ::..: ~ > .~. ,7; +
. ,,yp. -
-Y.s ,
. ..u~ r .,.- gi.
360 - - - - - - - - -
O 5 10- 15 20 i Experiment Time (min) _
g Figure 7. Surtsey vessel gas temperatures from the B thermocouple array in the condensation test. .
1
l l
l l-i i i i Ch59 (bot. tom)
<{ <{ Q - --
Ch60 ~
Ch61
Ch62 ,
Ch63
^
l - - - Ch64
- M
\
v 420 -
.., , v - - - - - Ch65 -
g ar.i'JA,s K Ch68 L g4: 4 ' - --
Ch67 (top) l g . sy .3 (N l 4 ' *%.' . %
as
" 400
- %( x i
Q)
'i .
s ..'. g -
a .
~.s s ..
%' .D g 6 s... , ....... ..
- e ~ .. :
s Y q s.. .
380 -
~Ns%. .f _ . _ . . _ . .
' %s s...
- g- ' \ ,5 'f s =- -.
.. s Q Nu..;.:., ?g,%.g... 3.%p . ==
l
. s- -----
- ....:.:: c ' ...
i 360 - - - - - - - - - - -
l 0 5 10 15 20 Experiment Time (min)
- ! Figure 8. Surtsey vessel gas temperatures from the C thermocouple array in the condensation test.
l -
i
~ . -
i i r~ '
i
. Ch68 (bottom) 4-4 0 -
.i; 0 - -
Ch69 -
i ,1 t
- ---- Ch70 t
j- . ------ Ch71 l \ -
Ch72
^ .f 'g
- g _ . - - Ch73 M -. .,. . ., j s.. Ch74 v 420 .- s g L-?g -
s Ch75 Ch76 (top)
L
, Q,- 'y ( \ - -
p , ~. .
a -, s.. \
cd s .' '
" 400 o
%'t~-' -
.. ~. .
a ' @.
s s.. s g ., . u. . .
......~
,f s'.. ..
e-< ~ -.. w. 's N ..
380 'o -
=="
' c.w.hys.,
-W s,
..N ,
y k s.. q . .:. .
, ~2 - '-
~ ,,~...y*..
, ,. ~
g,, -
~ . -1;:.. .s I:
~ - g.g, r
~
360 - - -
0 5 10 15 20 Experiment Time (min) i Figure 9. Surtsey vessel gas temperatures from the D thermocouple array in the condensation test.
i J
M v.
e a
'g i,
2 :
N
),./ ~
a
^
i ) il E
! ', t 4 i.t . 5
,,a c.
O Y *\ ' .\ $o s;s ' . ,N _
w w .
U t- D Cn ~ 02 t'3 4 tt) to ,'] j G c- e- t- emeeme , . : .a AAAA A A A .C .C , j lll OO U U UUUUU ,
rj l:
., / g
=m "
g
- . o k l.ls :l .
I ' ' : I I l sI
.a 5.e s s e
,f / ;g g y -
j'
,s y : / .m' *
/l l o %' %
- , U D 1 ) * *M ~
O
,' / i lY Q o
,/ : :I e
/
d E.
q u
- / .m o i
o I .
l ., _
o A w
W
// :/
/ / ,/ :l/
.a int
~
i .
g a
/ l' l .!I q) 0 o / .ll :Y &G8
,' i : U .2 . .-<
o 4 ~
s / : / :.o y ,
,l l jl
.Q
/ f s' / .fi j' C
M .3
/ / ./ M l /
E O
o / f:: / ..*/ _
O.
I f ll l.ll B
o
/ . f .' { .
,' f l /,E / e u
s / c
~' y
,a 7 ll /
M e
o l '
' .i... / U j*'.a * ' al
,. g= * .'/ .:. -
Q g e
I I U t I : : a
't i L P. I 1 eJ 8.e 3
o o o o o e v N o w w w +
(>I) aanquaedulel e a
..t.2
i i - -
i i 420 ..
. 't
,j-w
._-___%. s.~._._.
N
._. m ..~
.~.____- .._..f.s..
>- .~.x. .
,_ s ,
^ .- '**.,
s s M
v .-
. .3 .
- /. . . .,
. s
' , ,,x
. , . . . %---.~..------.-.._...._,,_,,,,_,,,,,_..._....._,...,
e 400 -
% :-., s
.[. ,
.. . ~
4 Q .. -
~~ ~
s
~
~
A ..
~.
~~~%
% ., .'... - ' ~ s q) --
g
.J........,,'.~~.~.'~s.
d Ch01 (floor) ..
N s
R --
Ch39 (floor) .
o 380 -
Ch00 (floor) .
E- .
Ch38 (wall) ..
Ch88 (wall) ..
Ch37 (wall) ,,.. - ......... ~~....... . -
, ---- Ch87 (wall)
! Ch92 (dome) l l 360 ' - - - - - - - - - - - - - -
0 5 10 15 20 Experiment Time (min)-
Figure 11. Surtsey vessel floor, wall, and dome temperatures in the condensation test.
.____________________________________.--______a
35 , , , , ,
30 -
m 25 -
2 a
o 20 v -
a>
a c5 ,
s 15 -
> ~
O N 10 -
5 -
sui 0 - - - - - - - - - - - - c - - - -
0 5 10 '15 20 Experiment Time (min).
Figure 12. Spray nozzle water flowrate in the condensation test.
, , , a+. ._. -_ -
330 . , , i 320 '
(
2 v 310 -
N -
e -
L _
M Y 300 -
L e -
6 o 290 E- _
\
280 -
i _
270 ' - - ' - - - - ' - - -
0 5 10 15 20
- Experiment Time (min)
Figure 13. Spray nozzle water ternperature in the condensation test.
e aw- - - -
0.8 . , , ,
m c
o o
O d 0.7 - -
u a
O O
i i
v 0.6 - -
c O _
er-4 o
e b
c 0.5 - -
e O
c -
o .
o 0.4 - - - - - - - - - - - - -
0 5 10 15 20 i Experiment. Time (min)
Figure 14. Surtsey vessel steam fraction in the condensation tent.
, u
i . . -
0.10 . . , , . , ,
n Oxygen C --
Helium
.H o 0.09 -
o d
L 0.08 -
/
0 -
0.07 -
v 9 -
' /
c 0.06 -
o
.H '
a ,
c '
.b 0.05 c ,'
O O /
d 0.04 -
O -
o ,
/
0.03 c 0 5 10 15 20 Experiment Time (min)
Figure 15. Surtsey vessel oxygen and helium gas fractions in the condensation test.
. - _ _ _ . _ - - . _ _ - _ _ _ - _ _ _ _ _ _ - .- _ --. -- -. .-