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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20205C3521988-09-23023 September 1988 Final Response to FOIA Request for Documents Re Plant. Forwards App D Documents.App D Documents Also Available in PDR ML20093K3281984-10-11011 October 1984 Requests Discontinuance of Document Distribution to Offshore Power Sys,Which Closed on 840901 ML20083K7301984-03-27027 March 1984 Responds to IE Bulletin 83-08.Circuit Breakers Not Purchased or Specified for safety-related Applications.No Further Design Activities Planned Prior to Obtaining Customer ML20073B5171983-04-0808 April 1983 Responds to Generic Ltr 83-10D Re Resolution of TMI Action Item II.K.3.5, Study Need for Auto Trip of Reactor Coolant Pumps. Resolution Will Be Initiated When Customer for First FNP Is Attained & Final Design Efforts Begun ML20071E8321983-03-0101 March 1983 Ack Receipt of Generic Ltr 83-07 Re Requirements of Nuclear Waste Policy Act of 1982.Lists Reasons for Not Entering Into Waste Disposal Contract W/Doe ML20072A8671982-12-29029 December 1982 Requests Public Statement Responding to 760615 Testimony Before NRC Re Safety Concerns Associated W/Ops Floating Nuclear Power Plants ML20072A8621982-12-12012 December 1982 Requests Response to Previous Correspondence Opposing OPS Floating Nuclear Power Plants,Heretofore Unacknowledged by Nrc.June 1976 Testimony on SER Encl ML20072A8761982-12-0101 December 1982 Requests Response to ,Mistakenly Directed to Former Chairman Jm Hendrie ML20069G5291982-09-17017 September 1982 Forwards Revisions to Environ Protection Plan Per 820915 Telcon ML20072A8701982-08-14014 August 1982 Lists Reasons for Opposing Issuance of Mfg License to OPS for Floating Nuclear Power Plants ML20054M3461982-06-23023 June 1982 Confirms 820623 Telcon Re Official Closing of Lpdr for Offshore Nuclear Power Plant.Lpdr in Jacksonville,Fl Will Remain Open ML20052G6091982-05-11011 May 1982 Advises of RA Thomas Appointment as Acting Manager of Offshore Power Sys Div.Pb Haga Appointed Director of Engineering.Svc List Encl.Related Correspondence ML20041E5781982-03-0505 March 1982 Advises That OPS Became Div of Water Reactor Div of Westinghouse on 820201.Change Does Not Affect Licensing Process.Svc List Encl ML20041D6861982-02-24024 February 1982 Advises of Westinghouse Nuclear Energy Sys Organizational Changes.Organizational Charts Encl ML20040G3531982-01-29029 January 1982 Requests Public Response to 760615 Testimony ML20039E7421981-12-21021 December 1981 Delegates Authority for Review of Info Sought to Be Withheld from Public to Pb Haga,Director of Power Sys Technology ML20062M2991981-12-11011 December 1981 Forwards Applicant 811211 Proposed Findings of Fact & Conclusions of Law in Form of Proposed Initial Decision. Document Supersedes Applicant 790601 Proposed Partial Findings of Fact in Form of Proposed Initial Decision ML20038B9601981-12-0202 December 1981 Repts on 811113 Telcon.Aslb Denied Applicant Request That Answers to ASLB 811112 Questions Be Provided Orally at 811204 Hearing.Answers Are to Be Filed in Advance by 811127. Certificate of Svc Encl.Related Correspondence ML20038B5911981-11-12012 November 1981 Submits Info Requested in 811106 Telcon W/Nrc Re Turbine Missile Shield ML20049A7371981-09-17017 September 1981 Confirms 810917 Telcon Re Containment Design Pressure.Util Reluctantly Commits to Design Containment Vessel to Meet ASME Svc Level a Stress Limits for Design Interval Pressure of 25 Psig at Ambient Temp ML20010J3741981-09-10010 September 1981 Submits Addl Info Re Equipment Qualification Modifying 810902 Response Re Generic Issue A-24.Safety-related Equipment Will Be Qualified in Accordance w/NUREG-0588, Category I Requirements ML20010F8661981-09-0404 September 1981 Ack Receipt of NRC 810831 Ltr Re Meeting W/Util to Discuss Facility.Gl Paulson No Longer W/Nj Dept on Environ Protection.A Mclellan Now Assistant Commissioner for Science & Research & Should Replace Paulson on Mailing List ML20010E6101981-08-28028 August 1981 Corrects Date of Ref Cited in 810818 Ltr Responding to NRC Request for Info Re Generic Technical Issues A-2 & A-36 ML20009C8931981-07-22022 July 1981 Advises That Review of Plant Design Rept & Amends for Barge Mounted Floating Nuclear Plant Has Been Completed.Final Approval Will Depend on Successful Plan Review,Insp During Const & Approval by Officer in Charge ML19346A4151981-06-11011 June 1981 Forwards Draft App C to Plant Design Rept, in Response to post-TMI Requirements.App C Will Be Filed Formally at Conclusion of Technical Review & Upon Resolution of NRC Concerns ML20004E5451981-06-0606 June 1981 Requests Name Be Deleted from Mailing List Re Hearings ML20126F4071981-03-10010 March 1981 Forwards Characteristics & Sketch of Floating Nuclear Power Plant & Info Sheets on Floating Nuclear Power Plant & Mfg Facility,On Behalf of Ofc of General Counsil.Requests Insp of Facility & Testimony at 810526 Trial Re Mfg of Plants ML20008F5561981-03-0404 March 1981 Urges Inclusion of OPS Mfg License Application in Proposed Rule Defining TMI accident-related Requirements for Pending CP & Mfg Licenses ML20008F5621981-03-0303 March 1981 Expresses Concern Re Inclusion of OPS Application in Proposed Rule Currently Under Consideration for near-term Cp/Mfg License Applications ML20008F5671981-02-24024 February 1981 Urges Inclusion of OPS Mfg License Application in Proposed Rulemaking Defining TMI accident-related Requirements for Pending CP & Mfg Licenses ML20002E3551980-12-16016 December 1980 FOIA Request for All Documents Re OPS Application for License to Mfg Floating Nuclear Plants Containing Statements Re Alternate Land Uses ML19345C2711980-10-29029 October 1980 Requests Info Re Facilities W/Active CPs Pending,License Definitions & Requirements for Floating Nuclear Plants ML19332A0831980-09-0505 September 1980 Requests That Schedule Be Established for Completing Review of Application for Mfg License & That NRC Resources Be Committed for That Purpose.Nrc Should Initiate Review of Util 800715 Responses to NUREG-0660 ML19331C6281980-07-22022 July 1980 Requests Available Info Re Projected Offshore Floating Nuclear Power Plant ML19320D4621980-07-15015 July 1980 Forwards 36A93, OPS Responses to Post-TMI NRC Requirements, Revision 1.Rept Represents Vast Majority of New Info Required to Support Issuance of Mgt License. Requests Meeting W/Nrc at Earliest Possible Convenience ML19329G1971980-05-21021 May 1980 Requests Reply to CT Brown 800407 Ltr Expressing Support for Floating Nuclear Power Plant Project ML19320B7581980-05-16016 May 1980 Ack Receipt of Encl 800407 Ltr to President Carter Re Employment Opportunities Offered by Offshore Floating Nuclear Plant Project.Decisions on Commercial Projects Are Made by Private Sector,W/Nrc Approval ML19323C6321980-05-0606 May 1980 Forwards Review Re Applicability of post-TMI Action Plan Requirements Contained in Draft 3 of NUREG-0660 & Applicability of Item III.A.2-2 of NUREG-0654.Response to All Action Plan Items,Except Item II.B.8 Planned for ML19305C4241980-03-18018 March 1980 Forwards Response to NRC 791017 Ltr Requesting Addl Info Re Core Thermohydraulic Effects ML19257A3011979-12-21021 December 1979 Forwards 36A93, Responses to Post-TMI NRC Requirements, Per IE Bulletin 79-06,NRC 791010 & 1109 Ltrs Re TMI Lessons Learned Task Force short-term Requirements & TMI Lessons Learned Task Force Final Rept. ML19210D0981979-11-0707 November 1979 Forwards Response to OPS 790709 Ltr Re Mobilization & Deployment of Coast Guard Vessels in Response to Emergency at Floating Nuclear Power Plant ML19210C9341979-10-18018 October 1979 Responds,On Behalf of Applicant,To NRC 791011 Ltr Addressed to ASLB Re Unavailability of NRC Witness.Requests Scheduling of 791031 or 1101-02 & 05 Hearing Session Re ASLB Questions Pending Since Mar 1979.Urges Publication of SER Schedule ML19253B4191979-10-0505 October 1979 Requests Plan & Schedule for Completion of Review of Application for Mfg License ML19253B5911979-09-26026 September 1979 Agrees to Use McGuire Nodalization Scheme or More Detailed Model for Analyses of Pressure Transient in Steam Generator Encl Following Steam Line Rupture ML19208D5551979-09-21021 September 1979 Forwards Revision 2 to Rept 36A59, Fnp Core Ladle Design & Safety Evaluation. Revision Reflects Sandia Lab Comments Transmitted in NRC 790605 Ltr & Results of 790724 Meeting W/Nrc & Sandia Lab ML19209C9571979-09-20020 September 1979 Protests NRC Recommendation That Floating Nuclear Power Station Not Be Built ML19208B0281979-09-14014 September 1979 Forwards Responses to ACRS Subcommittee 790725 Questions Re Core Ladle & TMI-2.Response Modifies Design Presented in Rept 36A59 Floating Nuclear Plant Core Laddle Design & Safety Evaluation. Requests ACRS Meeting in Oct ML19209B4791979-09-0606 September 1979 Forwards 790806 Ltr from B Peters Expressing Concern About Possible NRC Decision to Issue License for Const of Offshore Nuclear Power Plants.Requests Review & Assistance in Responding to Ltr ML19211A8421979-09-0606 September 1979 Forwards B Peters Ltr Re NRC Decision to Issue License for Const of Floating Nuclear Plants.Requests Comment ML19209B3511979-08-22022 August 1979 Forwards Ltr from PA Nilsson Expressing Concern About Plans to Issue Mfg License.Requests Info in Order to Respond to Constituent Inquiry 1988-09-23
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20093K3281984-10-11011 October 1984 Requests Discontinuance of Document Distribution to Offshore Power Sys,Which Closed on 840901 ML20083K7301984-03-27027 March 1984 Responds to IE Bulletin 83-08.Circuit Breakers Not Purchased or Specified for safety-related Applications.No Further Design Activities Planned Prior to Obtaining Customer ML20073B5171983-04-0808 April 1983 Responds to Generic Ltr 83-10D Re Resolution of TMI Action Item II.K.3.5, Study Need for Auto Trip of Reactor Coolant Pumps. Resolution Will Be Initiated When Customer for First FNP Is Attained & Final Design Efforts Begun ML20071E8321983-03-0101 March 1983 Ack Receipt of Generic Ltr 83-07 Re Requirements of Nuclear Waste Policy Act of 1982.Lists Reasons for Not Entering Into Waste Disposal Contract W/Doe ML20072A8671982-12-29029 December 1982 Requests Public Statement Responding to 760615 Testimony Before NRC Re Safety Concerns Associated W/Ops Floating Nuclear Power Plants ML20072A8621982-12-12012 December 1982 Requests Response to Previous Correspondence Opposing OPS Floating Nuclear Power Plants,Heretofore Unacknowledged by Nrc.June 1976 Testimony on SER Encl ML20072A8761982-12-0101 December 1982 Requests Response to ,Mistakenly Directed to Former Chairman Jm Hendrie ML20069G5291982-09-17017 September 1982 Forwards Revisions to Environ Protection Plan Per 820915 Telcon ML20072A8701982-08-14014 August 1982 Lists Reasons for Opposing Issuance of Mfg License to OPS for Floating Nuclear Power Plants ML20052G6091982-05-11011 May 1982 Advises of RA Thomas Appointment as Acting Manager of Offshore Power Sys Div.Pb Haga Appointed Director of Engineering.Svc List Encl.Related Correspondence ML20041E5781982-03-0505 March 1982 Advises That OPS Became Div of Water Reactor Div of Westinghouse on 820201.Change Does Not Affect Licensing Process.Svc List Encl ML20041D6861982-02-24024 February 1982 Advises of Westinghouse Nuclear Energy Sys Organizational Changes.Organizational Charts Encl ML20040G3531982-01-29029 January 1982 Requests Public Response to 760615 Testimony ML20039E7421981-12-21021 December 1981 Delegates Authority for Review of Info Sought to Be Withheld from Public to Pb Haga,Director of Power Sys Technology ML20062M2991981-12-11011 December 1981 Forwards Applicant 811211 Proposed Findings of Fact & Conclusions of Law in Form of Proposed Initial Decision. Document Supersedes Applicant 790601 Proposed Partial Findings of Fact in Form of Proposed Initial Decision ML20038B9601981-12-0202 December 1981 Repts on 811113 Telcon.Aslb Denied Applicant Request That Answers to ASLB 811112 Questions Be Provided Orally at 811204 Hearing.Answers Are to Be Filed in Advance by 811127. Certificate of Svc Encl.Related Correspondence ML20038B5911981-11-12012 November 1981 Submits Info Requested in 811106 Telcon W/Nrc Re Turbine Missile Shield ML20049A7371981-09-17017 September 1981 Confirms 810917 Telcon Re Containment Design Pressure.Util Reluctantly Commits to Design Containment Vessel to Meet ASME Svc Level a Stress Limits for Design Interval Pressure of 25 Psig at Ambient Temp ML20010J3741981-09-10010 September 1981 Submits Addl Info Re Equipment Qualification Modifying 810902 Response Re Generic Issue A-24.Safety-related Equipment Will Be Qualified in Accordance w/NUREG-0588, Category I Requirements ML20010F8661981-09-0404 September 1981 Ack Receipt of NRC 810831 Ltr Re Meeting W/Util to Discuss Facility.Gl Paulson No Longer W/Nj Dept on Environ Protection.A Mclellan Now Assistant Commissioner for Science & Research & Should Replace Paulson on Mailing List ML20010E6101981-08-28028 August 1981 Corrects Date of Ref Cited in 810818 Ltr Responding to NRC Request for Info Re Generic Technical Issues A-2 & A-36 ML20009C8931981-07-22022 July 1981 Advises That Review of Plant Design Rept & Amends for Barge Mounted Floating Nuclear Plant Has Been Completed.Final Approval Will Depend on Successful Plan Review,Insp During Const & Approval by Officer in Charge ML19346A4151981-06-11011 June 1981 Forwards Draft App C to Plant Design Rept, in Response to post-TMI Requirements.App C Will Be Filed Formally at Conclusion of Technical Review & Upon Resolution of NRC Concerns ML20004E5451981-06-0606 June 1981 Requests Name Be Deleted from Mailing List Re Hearings ML20126F4071981-03-10010 March 1981 Forwards Characteristics & Sketch of Floating Nuclear Power Plant & Info Sheets on Floating Nuclear Power Plant & Mfg Facility,On Behalf of Ofc of General Counsil.Requests Insp of Facility & Testimony at 810526 Trial Re Mfg of Plants ML20008F5561981-03-0404 March 1981 Urges Inclusion of OPS Mfg License Application in Proposed Rule Defining TMI accident-related Requirements for Pending CP & Mfg Licenses ML20008F5621981-03-0303 March 1981 Expresses Concern Re Inclusion of OPS Application in Proposed Rule Currently Under Consideration for near-term Cp/Mfg License Applications ML20008F5671981-02-24024 February 1981 Urges Inclusion of OPS Mfg License Application in Proposed Rulemaking Defining TMI accident-related Requirements for Pending CP & Mfg Licenses ML20002E3551980-12-16016 December 1980 FOIA Request for All Documents Re OPS Application for License to Mfg Floating Nuclear Plants Containing Statements Re Alternate Land Uses ML19345C2711980-10-29029 October 1980 Requests Info Re Facilities W/Active CPs Pending,License Definitions & Requirements for Floating Nuclear Plants ML19332A0831980-09-0505 September 1980 Requests That Schedule Be Established for Completing Review of Application for Mfg License & That NRC Resources Be Committed for That Purpose.Nrc Should Initiate Review of Util 800715 Responses to NUREG-0660 ML19331C6281980-07-22022 July 1980 Requests Available Info Re Projected Offshore Floating Nuclear Power Plant ML19320D4621980-07-15015 July 1980 Forwards 36A93, OPS Responses to Post-TMI NRC Requirements, Revision 1.Rept Represents Vast Majority of New Info Required to Support Issuance of Mgt License. Requests Meeting W/Nrc at Earliest Possible Convenience ML19329G1971980-05-21021 May 1980 Requests Reply to CT Brown 800407 Ltr Expressing Support for Floating Nuclear Power Plant Project ML19323C6321980-05-0606 May 1980 Forwards Review Re Applicability of post-TMI Action Plan Requirements Contained in Draft 3 of NUREG-0660 & Applicability of Item III.A.2-2 of NUREG-0654.Response to All Action Plan Items,Except Item II.B.8 Planned for ML19305C4241980-03-18018 March 1980 Forwards Response to NRC 791017 Ltr Requesting Addl Info Re Core Thermohydraulic Effects ML19257A3011979-12-21021 December 1979 Forwards 36A93, Responses to Post-TMI NRC Requirements, Per IE Bulletin 79-06,NRC 791010 & 1109 Ltrs Re TMI Lessons Learned Task Force short-term Requirements & TMI Lessons Learned Task Force Final Rept. ML19210D0981979-11-0707 November 1979 Forwards Response to OPS 790709 Ltr Re Mobilization & Deployment of Coast Guard Vessels in Response to Emergency at Floating Nuclear Power Plant ML19210C9341979-10-18018 October 1979 Responds,On Behalf of Applicant,To NRC 791011 Ltr Addressed to ASLB Re Unavailability of NRC Witness.Requests Scheduling of 791031 or 1101-02 & 05 Hearing Session Re ASLB Questions Pending Since Mar 1979.Urges Publication of SER Schedule ML19253B4191979-10-0505 October 1979 Requests Plan & Schedule for Completion of Review of Application for Mfg License ML19253B5911979-09-26026 September 1979 Agrees to Use McGuire Nodalization Scheme or More Detailed Model for Analyses of Pressure Transient in Steam Generator Encl Following Steam Line Rupture ML19208D5551979-09-21021 September 1979 Forwards Revision 2 to Rept 36A59, Fnp Core Ladle Design & Safety Evaluation. Revision Reflects Sandia Lab Comments Transmitted in NRC 790605 Ltr & Results of 790724 Meeting W/Nrc & Sandia Lab ML19209C9571979-09-20020 September 1979 Protests NRC Recommendation That Floating Nuclear Power Station Not Be Built ML19208B0281979-09-14014 September 1979 Forwards Responses to ACRS Subcommittee 790725 Questions Re Core Ladle & TMI-2.Response Modifies Design Presented in Rept 36A59 Floating Nuclear Plant Core Laddle Design & Safety Evaluation. Requests ACRS Meeting in Oct ML19209B4791979-09-0606 September 1979 Forwards 790806 Ltr from B Peters Expressing Concern About Possible NRC Decision to Issue License for Const of Offshore Nuclear Power Plants.Requests Review & Assistance in Responding to Ltr ML19211A8421979-09-0606 September 1979 Forwards B Peters Ltr Re NRC Decision to Issue License for Const of Floating Nuclear Plants.Requests Comment ML19209B3511979-08-22022 August 1979 Forwards Ltr from PA Nilsson Expressing Concern About Plans to Issue Mfg License.Requests Info in Order to Respond to Constituent Inquiry ML19209B1511979-08-15015 August 1979 Notifies That Intervenor Atlantic County,Nj,Will Take Passive Role in Proceedings Unless Interests Are Directly Affected ML19250C0621979-08-0808 August 1979 Forwards H Padula 790806 Ltr Re Authorizing of OPS to Mfg Eight Floating Nuclear Plants in State of Fl.Requests Comment ML19249D9771979-08-0808 August 1979 Three Citizen Ltrs Opposing Licenses to Build Nuclear Power Plants in Atlantic Ocean & Gulf of Mexico 1984-03-27
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20093K3281984-10-11011 October 1984 Requests Discontinuance of Document Distribution to Offshore Power Sys,Which Closed on 840901 ML20083K7301984-03-27027 March 1984 Responds to IE Bulletin 83-08.Circuit Breakers Not Purchased or Specified for safety-related Applications.No Further Design Activities Planned Prior to Obtaining Customer ML20073B5171983-04-0808 April 1983 Responds to Generic Ltr 83-10D Re Resolution of TMI Action Item II.K.3.5, Study Need for Auto Trip of Reactor Coolant Pumps. Resolution Will Be Initiated When Customer for First FNP Is Attained & Final Design Efforts Begun ML20071E8321983-03-0101 March 1983 Ack Receipt of Generic Ltr 83-07 Re Requirements of Nuclear Waste Policy Act of 1982.Lists Reasons for Not Entering Into Waste Disposal Contract W/Doe ML20069G5291982-09-17017 September 1982 Forwards Revisions to Environ Protection Plan Per 820915 Telcon ML20041D6861982-02-24024 February 1982 Advises of Westinghouse Nuclear Energy Sys Organizational Changes.Organizational Charts Encl ML20039E7421981-12-21021 December 1981 Delegates Authority for Review of Info Sought to Be Withheld from Public to Pb Haga,Director of Power Sys Technology ML20062M2991981-12-11011 December 1981 Forwards Applicant 811211 Proposed Findings of Fact & Conclusions of Law in Form of Proposed Initial Decision. Document Supersedes Applicant 790601 Proposed Partial Findings of Fact in Form of Proposed Initial Decision ML20038B5911981-11-12012 November 1981 Submits Info Requested in 811106 Telcon W/Nrc Re Turbine Missile Shield ML20049A7371981-09-17017 September 1981 Confirms 810917 Telcon Re Containment Design Pressure.Util Reluctantly Commits to Design Containment Vessel to Meet ASME Svc Level a Stress Limits for Design Interval Pressure of 25 Psig at Ambient Temp ML20010J3741981-09-10010 September 1981 Submits Addl Info Re Equipment Qualification Modifying 810902 Response Re Generic Issue A-24.Safety-related Equipment Will Be Qualified in Accordance w/NUREG-0588, Category I Requirements ML20010E6101981-08-28028 August 1981 Corrects Date of Ref Cited in 810818 Ltr Responding to NRC Request for Info Re Generic Technical Issues A-2 & A-36 ML19346A4151981-06-11011 June 1981 Forwards Draft App C to Plant Design Rept, in Response to post-TMI Requirements.App C Will Be Filed Formally at Conclusion of Technical Review & Upon Resolution of NRC Concerns ML20008F5671981-02-24024 February 1981 Urges Inclusion of OPS Mfg License Application in Proposed Rulemaking Defining TMI accident-related Requirements for Pending CP & Mfg Licenses ML19332A0831980-09-0505 September 1980 Requests That Schedule Be Established for Completing Review of Application for Mfg License & That NRC Resources Be Committed for That Purpose.Nrc Should Initiate Review of Util 800715 Responses to NUREG-0660 ML19320D4621980-07-15015 July 1980 Forwards 36A93, OPS Responses to Post-TMI NRC Requirements, Revision 1.Rept Represents Vast Majority of New Info Required to Support Issuance of Mgt License. Requests Meeting W/Nrc at Earliest Possible Convenience ML19323C6321980-05-0606 May 1980 Forwards Review Re Applicability of post-TMI Action Plan Requirements Contained in Draft 3 of NUREG-0660 & Applicability of Item III.A.2-2 of NUREG-0654.Response to All Action Plan Items,Except Item II.B.8 Planned for ML19305C4241980-03-18018 March 1980 Forwards Response to NRC 791017 Ltr Requesting Addl Info Re Core Thermohydraulic Effects ML19257A3011979-12-21021 December 1979 Forwards 36A93, Responses to Post-TMI NRC Requirements, Per IE Bulletin 79-06,NRC 791010 & 1109 Ltrs Re TMI Lessons Learned Task Force short-term Requirements & TMI Lessons Learned Task Force Final Rept. ML19253B4191979-10-0505 October 1979 Requests Plan & Schedule for Completion of Review of Application for Mfg License ML19253B5911979-09-26026 September 1979 Agrees to Use McGuire Nodalization Scheme or More Detailed Model for Analyses of Pressure Transient in Steam Generator Encl Following Steam Line Rupture ML19208D5551979-09-21021 September 1979 Forwards Revision 2 to Rept 36A59, Fnp Core Ladle Design & Safety Evaluation. Revision Reflects Sandia Lab Comments Transmitted in NRC 790605 Ltr & Results of 790724 Meeting W/Nrc & Sandia Lab ML19208B0281979-09-14014 September 1979 Forwards Responses to ACRS Subcommittee 790725 Questions Re Core Ladle & TMI-2.Response Modifies Design Presented in Rept 36A59 Floating Nuclear Plant Core Laddle Design & Safety Evaluation. Requests ACRS Meeting in Oct ML19247A0491979-07-19019 July 1979 Discusses Effect of Core Ladle on Reactor Cavity Pressure Analysis.Supersedes 790711 Ltr ML19225A0261979-07-13013 July 1979 Forwards Assessment of Potential Impacts of Releases of Insoluble Core Debris Following Postulated Core Melt Accident.Transport of Radioactivity as Particulate Matter Is Considered Highly Unlikely ML19241B9231979-07-11011 July 1979 Provides Addl Info for Plant Design Rept Re Effect of Core Ladle on Reactor Cavity Pressure Analysis ML19241B8931979-07-0909 July 1979 Discusses Problems Experienced W/Pipe Support Baseline Design,As Outlined in IE Bulletin 79-02 & Transmitted to ASLB on 781207.Criteria for Design of Steel Embedments Prevents Problems Occurring ML19289F5471979-06-0606 June 1979 Forwards Revision 1 to 790517 Core Ladle Rept (OPS Rept 36A59) ML19282D1631979-05-11011 May 1979 Discusses Current Activities of Product Assurance Organization:Review & Approval of Drawings & Specs.Seeks to Obtain Mfg License & Customers as Soon as Possible. & Approve Drawings & Specifications ML19283B5821979-02-12012 February 1979 Informs NRC of Recent Changes of Upper Mgt at Offshore Power Sys ML19274D5621979-01-31031 January 1979 Submits Addl Info Re Containment Shell Buckling Criteria & Application.Requests Concurrence W/Approach Before Inclusion in Rept ML19289C8931979-01-11011 January 1979 Responds to 780809 Ltr Which Forwarded NRC Guidelines Re Component Cooling Water Supply to Reactor Coolant Pumps.As Discussed in Util 781031 Ltr & NRC 781122 Ltr,Category 4 Matters Will Be Addressed During Final Design Review Stage ML19256A7151979-01-0505 January 1979 Forwards Amend 26 to Application for License to Mfg Floating Nuclear Plants.Amend Deals Soley W/Subj Matter of the Plant Design Rept ML19322A0641978-12-21021 December 1978 Notifies NRC That Document SS15A18/A, Portable Fire Extinquishers-Sys Specs Is Being Forwarded to Us Coast Guard for Review & Approval ML19263B0651978-12-21021 December 1978 Responds to NRC Request of 781106 for Addl Info Re Containment Shell Buckling Criteria & Application of Criteria to Static Buckling Load ML19263A7251978-12-15015 December 1978 Forwards Revised Language to Motion to Plead Matter in Controversy Filed 780905.Areas Remaining for ASLB Resolution Are Identified ML20150E8961978-12-15015 December 1978 Disagrees w/780817 Licensing Sched Review Comm(Lsrc)Meeting Conclusions That Plant Design Rept Req Significant Updating to Assure Licensability.W/Enc Outlining Disagreements ML20150D4811978-11-29029 November 1978 Forwards 781103 EPA Ltr to OPS Re Riverine & Estuary Siting of Floating Nuc Plants & Requests Its Inclusion in the Comments Section of RDES-11 to Complete the Record ML20204D5391978-11-29029 November 1978 Requests That Bd Defer Ruling on Applicant'S Motion to Plead a Matter in Controversy,As Applicant Will Send Rev Language Documenting Areas of Agreement During Week of Dec 11,1978, Based on Comments Received from Staff ML20147D8031978-11-28028 November 1978 Informs NRC That Attach Elec on-line Diagrams Are Being Forwarded to USCG for Review & Approval.W/Att List ML20150E6201978-11-21021 November 1978 Forwards Newspaper Article Re Death of Kenneth Walton, Intervenor Pro Se in Proceeding, & Requests Deletion of His Name from Service Lists ML20148F7661978-10-31031 October 1978 Responds to 781012 NRC Ltr W/Addl Info Re Sched for Update Review of Plant Design Rept 1984-03-27
[Table view] |
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4 FNP-MNE-875 Offshore Power Systems 8000 Arlington Expresswav 904 ~724 -7700 Box Boo 0. Jacksonville, Florida 32211 Telex:568406 December 15, 1978 Mr. Robert L. Baer, Chief Light Water Reactors Branch No. 2 Division of Project Management U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20852
Dear Mr. Baer:
RE: DOCKET N0. STN 50-437; COMMENTS ON 8/17/78 LSRC MEETING MINUTES We recently received a copy of the minutes:of the August 17, 1978 meeting of the Licensing Schedules Review Committee (LSRC). As noted in the NRC trans-mittal, dated November 27, 1978, this document was "recently released to the Public Document Room" and was therefore not previously available to the public (including Offshore Power Systems). ' Upon review of these minutes we note that the " age" of the SER for the Manufacturing License application has again been stressed unduly. In a letter from R. S. Boyd dated '
October 12, 1978, the Staff suggested the need for an "ypdate review" and presented an exhaustive list of RJC and RESAR-3 items which, it was stated, must be addressed before issuance of the Manufacturing License. Offshore Power Systems responded in a letter dated October 31, 1978 and in our response we analyzed each category of information and showed that, in' fact, only a relatively few items were of any immediate significance (a copy of our October 31, 1978 letter is attached for your convenience). This letter records our disagreement with the overall tone of the August 17, 1978 meeting minutes and addresses specific statements which we believe lead to inaccurate conclusions.
Although the OPS /FNP SER was issued in September,1975, the passage of time to the present is in itself not significant. As we have pointed out previously, only changes in plant design or changes in regulatory re-quirements would affect staff conclusions contained ,
in the SER. l Yi m u2 coon Boollsls
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Mr. Paer December 15, 1978 Page 2 Plant design changes were reported in Amendment 24, dated August 1977. In Amendment 25, dated June 1978, the responses to all staff questions concerning Amend-ment 24 were incorporated in the Plant Design Report (these responses had been supplied mucn earlier by letter). -As the meeting minutes suggest and we would certainly agree, only Category II and Category III R 3C items are of sufficient importance as to require addi-tional information from Offshore Power Systems prior to the award of the Manufacturing License. We are prepared to address in the near future each of these items (except those very recent items which arose after January 1,1978). The meeting minutes incorrectly sug-gest that there'are numerous Category II and III R 3C items which are not addressed in the FNP application.
This is not the case. Of the 27 items in Categories II and III, nine do not apply to the FNP; seven are basically addressed in the PDR at this time, and eleven require new information. Of the eleven issues requiring new information, five arose after January 1,1978.
The meeting minutes also cite PDR references to RESAR-3 as casting doubt over licensability of the present design without significant updating of the PDR. RESAR-3 deficiency items are listed in Enclosure 5 to R. S. Boyd's October 12, 1978 letter. Enclosure 5 is a letter dated November 17, 1977 from D. B. Vassallo with accompanying attachments. Mr. Vassallo's letter was sent to all applicants referencing RESAR-3, except Offshore Power Systems. Offshore Power Systems was not included'in distribution because the FNP application had already been reviewed against current requirements. Mr. Vassa11o's letter states in part that, "We have determined that these matters can reasonably be addressed in the course of the operating license review of your plant. However, we are identifying them to you now for your consideration as appropriate during the final design of your plant and the preparation of your Final Safety Analysis Report." It is apparent that the significance of our utilization of RESAR-3 has been overstated.
In summary, we do not agree that the FNP Plant Design Report requires significant updating to assure licensability. In fact, just the opposite is the case, i.e., our application requires very little updating. We have proposed-to. amend the PDR to address nearly all of the existing Category II and Category III R 3C items (This amendment will be minimal l
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Mr. Baer l December 15, 1978 i Page 3 l
in volume and will require a correspondingly small review effort on the part of the Staff). We have already updated plant design information to reflect progress since 1975.
Finally, most if not all RESAR-3 information items are contained in the PDR and have been for some time; those that are not can reasonably be left to the final design approval stage.
We appreciate the opportunity to' review these meeting minutes and to correct what we see as an unduly negative view of the status of the Manufacturing License application.
We ask that this letter be brought to the. attention of those persons to whom the LSRC meeting minutes were ad-dressed. -
Ve' tru1y ours,
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,j d f 4 P. B. Hag ', Chief Engineer Mechanical & Nuclear Engineering leb Attachment cc: R. C. De Young, USNRC A. R. Collier V. W. Campbell o
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Of fshore Power Systerns ::nno A,innoon I s p.m ,,,y onq f:ri ffon nn < llUt H ), .l.,r! .. .nvill. , I h ,i n i.i . v / l i 1,.h *.',6f;11;f.
October 31, 1978 !
Mr. R. S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ,
7920 Norfolk Avenue
'Bethesda , Maryland 20852
Dear Mr. Soyd:
RE: DOCKET NO. STN 50-437: Manufacturing License Application Update Review Your letter o# October 12, 1978, advised Offshore Power ,
Systems that cr. update review of the Plant Design Report will_ be requit ed prior to issuance of the manufacturing license. The purpose of this letter is to outline the intended schedule and content of our responses to the review requirements expressed in your letter. The follow-ing comments are directed first to the general issues raised by the proposed update review and then to the specific matters identified in the enclosures to your October 12, 1978, letter. <
General The scope of the update review suggested in the opening paragraph of your letter goes well beyond that discussed during our meeting on September 29, and is tantamount to -
beginning the Floating Nuclear Plant review anew. Such an of fort at the eleventh hour is both novel and unnecessary.
The need for an update review can arise only by reason of plant design changes or regulatcry requirement changes since the SIR baseline date. In August, 1977, Offshore Power Sys tem". filed the unprehensive Amendmen,L 24 which updated the Plant.1)esign Report tn reflect design progress since 1975. Subt.equent to this filing, meetings were held with Staf f reviewers and questions were received concerning the cont'bnt of Amendment 24. These questions were answered I
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Page Two Oc tober 31, 1978 first by letter early this year and then in PDR Amendment 25, filed in June. Plant design changes having recently been described, there remain nuly regulatory requirement changes as the potential cause for an update review. New and revised regulatory requirements, which are 1imited in number and conveniently compiled in the "RRRC" list, certainly do not occasion the extensive update review suggested in your letter.
Our application is in the final stages of what is analgous to a construction permit proceeding. After the Manufacturing License is issued, Offshore Power Systems must still obtain approval of the final plant design. Therefore, ample time remains to address new review matters and to incorporate necessary process. design changes during the final design and approval The point is that at this late stage in the p.e-liminary design review, there is no compelling need to require that new matters be completely resolved prior to issuance of the Manufacturin,9 License. _
We, therefore, believe that the scope of Plant Design Report update review can and should be limited to certain matters as discussed in detail below.
Enclosure 1 Category I matters are defined in your letter as those which "are to be applied to applications, filed af ter a specific cutoff date." Even though cutoff dates are not-given in Enclosure 1, it appears that .none of the matters applies to the Manufacturing License application since not one of the listed items was in existence at the time of Plant Design Report docketing. Further, since the Staf f states that little or no design change is likely to result f m Category I matters, there is no need to address these matte- in a hurried manner prior to issuance of the Manufact,. n og License.
We, therefore, propose to describe the extent of ch ! Floating Huclear Plant conformance to each of these matter during the final design.
Enclosures 2 and 3 With a possible few exceptions where a letter response may be more appropria te, Of fshore Power Systems will address the Categdey 11 and Category 'Il matters in an amendment to the Plant Design Report; we expect to file this amendment before the end of 1978.
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Page Three ,
October.31, 1978-t 4..
Some of tho Category 11 'and ill ' matters' are very recent '
' developments. In such instances, it is unreasonable to
- require that complete information be developed prior to issuance-of the. Manufacturing l.icense. It is. obvious 4
that such a procedure can result in a situation in which an applicant continually progresses part way to the. award of a license...with never-ending, last minute reviews ',
forever barring the applicant from receiving the sought after' license. In order to prevent such a scenario, some cutoff date must be established. Consideration of new review matters which 'arise af ter this cutoff date will be
' deferred to.the final ' design review stage. We believe that a cutoff date of January 1,1978, is reasonable and request your concurrence.
In some cases the Category II or 111 matter involves a generic issue which is primarily in the scope of the NSSS vendor. In those cases our, response may be in the form of'a commitment to incorporate during final plant design whatever resolution is forthcoming, EJ1closure _4, P;y the Staf f's can definition, Category IV review matters are " matters which the Staff is preparing for RRRC consid-eration and are considered to'be of such safety significance that they must be addressed during the review". The Sta ff -
appears to be usurping an RRRC function by prejudging the significance of these matters and requiring them to be.
addressed prior to issuance of the Manufacturing License.
The matters' contained in Subcategory C of Category IV have-not yet been published in the form of Regulatory Guides, Standard Review Plans, or even Branch Technical posicions.
The substance of the Subcategory C matters has, for the most part .not been defined other than in the brief titles listed in Enclosure 4. Under these circums tances, a requirement to address Category IV mallers prior to issuance of the Manufacturing Licerfse is premature and unreasonable. Offshore
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Power Systems proposes to address each of these matters, when and~ if they are categorized by RRRC, during the iinal design approval phase.
'l:hclosure b In a letter dated Hovember 17, 1977, the NRC notified con-struction permiL applicants referencing RCSAR-3 of several 1
-deficiencies.in the content of RESAR-3. It was further s ta ted th'a t' considera tion of the matters identi fied could
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Page.Four October 31. 1978-i reasonably be d.eferred to the operating license review, This letter was not. transmitted' to OPS in November,1977, because the Staff had determined at that time that the -
Plant Design Report had already been reviewed against current requirements. Your present letter requires not
' only.that 0fTshore Power Systenis now address these issues- .
but that they be. addressed prior to issuance of the manu-facturing license. 0ffshore Power Systems considers this
[ reo6irement to be unnecessary and unreasonable. . We propose j-to address these matters to the extent' which may be necessary j during the final design approval phase.
e In summary, it is our intent .to file'a Plant Design' Report an,endment prior to January 1,1979, in response to the Category II and III RRRC~ matters. (In some cases a letter "
response may be more appropriate.) .W e propose to defer those matters' arising af ter January'1,1978, to the final -l design review. It is.our further intent to address Category '1, F
Category IV and RESAR-3 matters, to.the extent they have ,
not become' moot ' issues, during the final design review. We1 wish to emphasize that the final design of the Floating f!uclear Plant.will be developed with full consideration of each. review matter identified in your October 12, 1978, letter which is in force and . applicable at the time of final design review. We do object to the additional delay which would result from a general Plant Design. Report re-review and from'certain demands for information, both of-which we see as. unnecessary and unreasonable at this late stage in the Manufacturing License review.
Very truly yours ,
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()4). ,>O- (6) . ,M> iWL P. B. Hag 6'/ Chief Engineer Mechanical'and fluclear Engineering
/eb CC: V. W. Campbell A. R. Collier 5
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