|
|
Line 24: |
Line 24: |
| ==Dear Mr. Boyd:== | | ==Dear Mr. Boyd:== |
|
| |
|
| RE: DOCKET N0. STN 50-437; Manufacturing License Application Update Review Your letter of October 12, 1978, advised Offshore Power Systems that an update review of the Plant Design Report will be required 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. | | RE: DOCKET N0. STN 50-437; Manufacturing License Application Update Review Your letter of October 12, 1978, advised Offshore Power Systems that an update review of the Plant Design Report will be required 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 {{letter dated|date=October 12, 1978|text=October 12, 1978, letter}}. |
| General l 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 l an effort at the eleventh hour is both novel and unnecessary. | | General l 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 l an effort at the eleventh hour is both novel and unnecessary. |
| t The need for an update review can arise only by reason of plant design changes or regulatory requirement changes since the SER baseline date. In August,1977, Offshore Power Systems filed the comprehensive Amendment 24 which updated the Plant Design Report to reflect design progress j since 1975. Subsequent to this filing, meetings were held with Staff reviewers and questions were received concerning the content of Amendment 24. These questions were answered | | t The need for an update review can arise only by reason of plant design changes or regulatory requirement changes since the SER baseline date. In August,1977, Offshore Power Systems filed the comprehensive Amendment 24 which updated the Plant Design Report to reflect design progress j since 1975. Subsequent to this filing, meetings were held with Staff reviewers and questions were received concerning the content of Amendment 24. These questions were answered |
Line 55: |
Line 55: |
| The substance of the Subcategory C matters has, for the most- l part, not been defined other than in the brief titles listed i in Enclosure 4. Under these circumstances, a requirement ' | | The substance of the Subcategory C matters has, for the most- l part, not been defined other than in the brief titles listed i in Enclosure 4. Under these circumstances, a requirement ' |
| to address Category IV matters prior to issuance of the Manufacturing License is premature and unreasonable. Offshore ; | | to address Category IV matters prior to issuance of the Manufacturing License is premature and unreasonable. Offshore ; |
| Power Systems proposes to address each of these matters, i when and if they are categorized by RRRC, during the final design approval phase, j Enclosure 5 l In a letter dated November 17, 1977, the NRC notified con- l struction' permit applicants referencing RESAR-3 of several-deficiencies in the content of RESAR-3. It was further , | | Power Systems proposes to address each of these matters, i when and if they are categorized by RRRC, during the final design approval phase, j Enclosure 5 l In a {{letter dated|date=November 17, 1977|text=letter dated November 17, 1977}}, the NRC notified con- l struction' permit applicants referencing RESAR-3 of several-deficiencies in the content of RESAR-3. It was further , |
| stated that consideration of the matters identified could i | | stated that consideration of the matters identified could i |
| k l | | k l |
Line 63: |
Line 63: |
| 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 , | | 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 l only that Offshore Power Systems now address these issues but that they be addressed prior to issuance of the manu-facturing license. Offshore Power Systems considers this requirement to be unnecessary and unreasonable. We propose i to address these matters to the extent which may be necessary during the final design approval phase. | | current requirements. Your present letter requires not l only that Offshore Power Systems now address these issues but that they be addressed prior to issuance of the manu-facturing license. Offshore Power Systems considers this requirement to be unnecessary and unreasonable. We propose i to address these matters to the extent which may be necessary during the final design approval phase. |
| In summary, it is our intent to file a Plant Design Report amendment 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.) We propose to defer those matters arising after January 1,1978, to the final design review. It is our further intent to address Category I, Category IV and RESAR-3 matters, to the extent they have f not become moot issues, during the final design review. We wish to emphasize that the final design of the Floating Nuclear 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. | | In summary, it is our intent to file a Plant Design Report amendment 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.) We propose to defer those matters arising after January 1,1978, to the final design review. It is our further intent to address Category I, Category IV and RESAR-3 matters, to the extent they have f not become moot issues, during the final design review. We wish to emphasize that the final design of the Floating Nuclear Plant will be developed with full consideration of each review matter identified in your {{letter dated|date=October 12, 1978|text=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, | | Very truly yours, |
| / | | / |
|
---|
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] |
Text
2
. FNP-MNE-865
/
A Offshore Power Systems 8000 Arlington E xpressway 904 -724 -7700 Box 8000, Jacksonville, Floiida 32211 Telex:568406 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 Sethesdu Maryland 20852
Dear Mr. Boyd:
RE: DOCKET N0. STN 50-437; Manufacturing License Application Update Review Your letter of October 12, 1978, advised Offshore Power Systems that an update review of the Plant Design Report will be required 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 l 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 l an effort at the eleventh hour is both novel and unnecessary.
t The need for an update review can arise only by reason of plant design changes or regulatory requirement changes since the SER baseline date. In August,1977, Offshore Power Systems filed the comprehensive Amendment 24 which updated the Plant Design Report to reflect design progress j since 1975. Subsequent to this filing, meetings were held with Staff reviewers and questions were received concerning the content of Amendment 24. These questions were answered
\
0O i
7811090l(;3 4 9o \
l
6 Page Two October 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 only regulatory requirement changes as the potential cause for an update review. New and revised regulatory requirements, which are limited in number and conveniently compiled in the "RRRC" list, certainly do not ' .
occasion the extensive update review suggested in your letter. i 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 design changes during the final design and approval process. The point is that at this late stage in the pre-liminary design review, there is no compelling need to require ;
that new matters be completely resolved prior to issuance of '
the Manufacturing 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 after 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 Staff states that i little or no design change is likely to result from Category I '
matters, there is no need to address these matters in a ;
hurried manner prior to issuance of the Manufacturing License.
We, therefore, propose to describe the extent of the Floating Nuclear Plant conformance to each of these matters during the final design.
Enclosures 2 and 3 With a possible few exceptions where a letter response may be more appropriate, Offshore Power Systems will address the Category II and Category III matters in an amendment to the Plant Design Report; we expect to file this amendment before the end of 1978.
s Page Three October 31, 1978
'Some of the' Category II and III matters are very recent developments. In such instances, it i:; unreasonable to require that complete information be developed prior to issuance of the Manufacturing License. It is obvious 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 after 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 III 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.
Enclosure 4 By the Staff's own 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 Staff 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 i not yet been published in the form of Regulatory Guides, Standard Review Plans, or even Branch Technical positions. )
The substance of the Subcategory C matters has, for the most- l part, not been defined other than in the brief titles listed i in Enclosure 4. Under these circumstances, a requirement '
to address Category IV matters prior to issuance of the Manufacturing License is premature and unreasonable. Offshore ;
Power Systems proposes to address each of these matters, i when and if they are categorized by RRRC, during the final design approval phase, j Enclosure 5 l In a letter dated November 17, 1977, the NRC notified con- l struction' permit applicants referencing RESAR-3 of several-deficiencies in the content of RESAR-3. It was further ,
stated that consideration of the matters identified could i
k l
~
Page Four October 31, 1978 reasonably be deferred 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 l only that Offshore Power Systems now address these issues but that they be addressed prior to issuance of the manu-facturing license. Offshore Power Systems considers this requirement to be unnecessary and unreasonable. We propose i to address these matters to the extent which may be necessary during the final design approval phase.
In summary, it is our intent to file a Plant Design Report amendment 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.) We propose to defer those matters arising after January 1,1978, to the final design review. It is our further intent to address Category I, Category IV and RESAR-3 matters, to the extent they have f not become moot issues, during the final design review. We wish to emphasize that the final design of the Floating Nuclear 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,
/
P. B. Hag Chief Engineer Mechanical and Nuclear Engineering
/eb CC: V. W. Campbell A. R. Collier
,