Letter Sequence Other |
---|
|
|
MONTHYEARML20136D1721985-12-31031 December 1985 Forwards S&W Proprietary Calculations Re Design of Containment Downcomers Discussed During 851220 Meeting. S&W Affidavit Encl.Calculations Withheld (Ref 10CFR2.790) Project stage: Meeting ML20137M3941986-01-22022 January 1986 Forwards Safety Evaluation Re Power Ascension Program Proposed Test Mods Submitted by 850821,0920,23 & 30 Ltrs. Review of Listed Test Mods Completed.Amend to FSAR for Acceptable Test Mods Requested Project stage: Approval ML20140G0761986-01-31031 January 1986 Summary of 860124 Meeting W/Consultants to Discuss Adequacy of Downcomer Design in Context of Reanalysis Performed by Util.Design Marginal.Recommends Granting OL W/Listed Condition.List of Attendees Encl Project stage: Meeting ML20141N5311986-02-10010 February 1986 Comments on Review of Structural Adequacy of BWR Mark II Downcomers for Nine Mile Point 2 Nuclear Power Station. Allowable Moments Are Less than Calculated Applied Moment of 4914 in-kips Project stage: Other ML20141N5321986-02-14014 February 1986 Summarizes 860124 Meeting W/Nrc & EC Rodabaugh Re Structural Integrity of Facility Downcomer Design.Design Meets Licensing Requirements for Upset & Emergency Conditions Project stage: Meeting ML20236U2261987-11-23023 November 1987 Notification of 871207 Meeting W/S&W & Util in Bethesda,Md to Discuss Downcomers for Facility Project stage: Meeting 1986-01-31
[Table View] |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999 Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed 1999-09-07
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants 05000220/LER-1988-009, FOIA Request for LER 88-09,NRC Enforcement Conference W/Util on 880711,Insp Rept 50-220/88-15 & NRC Notice of Violation Ltr to Util1989-05-15015 May 1989 FOIA Request for LER 88-09,NRC Enforcement Conference W/Util on 880711,Insp Rept 50-220/88-15 & NRC Notice of Violation Ltr to Util ML20147G0741988-01-18018 January 1988 FOIA Request for All Documents Re NRC Investigation of Wg Dick Allegations About S&W & Lilco Re Performing NRC Instructions to Bring Facility Up to Fuel Load Stds ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20148F0581987-12-14014 December 1987 FOIA Request for Documents Re Vendor Lists for Facility as Compiled by Util or Any Contractors Between 1975 & 1978, Including Documentation Re Use of E-BRITE ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls ML20216B8651987-05-0101 May 1987 Forwards Final EGG-NTA-7611, Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components:Nine Mile Point Units 1 & 2, Informal Rept ML20209A8551987-01-16016 January 1987 FOIA Request for Documents to Be Placed in Pdr,Including NRC Re Calibr of Test Equipment allegation,1986 Inservice Insp Repts for McGuire 1 & Surry 1 & NRC 830307 SALP on Nine Mile Point 2 ML20195C5951986-03-14014 March 1986 FOIA Request for Structural Integrity Test Repts for Shoreham,Limerick-1,Nine Mile Point-2 & Susquehanna ML20141N5311986-02-10010 February 1986 Comments on Review of Structural Adequacy of BWR Mark II Downcomers for Nine Mile Point 2 Nuclear Power Station. Allowable Moments Are Less than Calculated Applied Moment of 4914 in-kips ML20133H0871985-10-10010 October 1985 Requests Ltr Stating That Listed Facilities Do Not Have Fuel Element Transfer Tubes.Documentation Needed for IE Bulletin 78-08 Closeout Rept ML18038A0031985-03-0707 March 1985 Forwards Rev 1 to Vol 1, Summary & Conclusions, to Final Rept of Independent Review of Nine Mile 2 Related NRC Const Assessment Team Insps & SALP Rept & Niagara Mohawk Identified Deficiencies, Per 841114 Presentation ML20093J1111984-09-21021 September 1984 Forwards Assessment Program Phase III Interim Repts.Rept Incomplete & Covers Only 169 of 216 Items Included in Program Scope.Total Results of Phase III Will Be Included in Final Rept.W/O Encl ML20084R6521984-02-24024 February 1984 FOIA Request for Computer Printout from Sept 1980 to Present of Civil Penalty Info on 27 Listed Nuclear Facilities.Sample Format Encl ML19347D1581981-03-0606 March 1981 Forwards for Review & Approval Sweco 8101, Models Used in Loctvs Computer Code to Determine Pressure & Temp Response of Vapor Suppression Containments Following Loca. ML20084Q6551970-04-0909 April 1970 Answers Questions Raised at 700426 Meeting,Outlining Alternative Procedures to Repair safe-ends & Future Actions to Minimize Possibility of Unexpected Stress Corrosion ML20084R3521969-10-31031 October 1969 Forwards Rept of Review of Stress Analysis of Steam Line Flow Restrictor Attachment Weld Affected by High Rate Stress Relief. W/O Encl ML20244D9691968-10-23023 October 1968 Provides Final Rept Prepared W/Wj Hall Re Seismic Design of Plant,W/Assistance of Wh Walker.Rept Based on Fsar,On Ref to Certain Sections in Preliminary Hazard Summary Rept & on Applicant Presentations During 680710-11 Site Visit 1989-05-17
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20209B2951999-06-22022 June 1999 Informs That Training Re Pressure Relief Panels Was Completed for Remainder of Target Population on 990226 ML20196E9231999-06-21021 June 1999 Forwards Response to NRC 990510 RAI Re NMP 981116 Application Proposing Changes to TSs to Provide Reasonable Assurance That Coupled neutronic/thermal-hydraulic Instabilities Were Detected & Suppressed in NMPN-1 Reactor ML18040A3651999-06-0707 June 1999 Forwards for Filing Original Application of Central Hudson & Gas & Electric Corp Seeking Extension of Expiration Date of Order,Dtd 980719,issued by Commission ML18040A3661999-06-0404 June 1999 Informs That Entire Attachment to Ltr NMP2L 1862 Dtd 990421, Should Be Replaced with Entire Attachment Being Sent with Present Ltr ML20195C9751999-06-0101 June 1999 Informs That Weld 32-WD-050 Will Be Reclassified Back to GL 88-01 Category a Weld & ASME Code Section XI Insps Will Be Conducted in Next Three Insp Periods ML20195C9601999-05-28028 May 1999 Provides Final Extent of Condition Evaluation Re Failed Cap Screw Beyond Upper Spring.Nmpc Continues to Conclude as Stated in That No Addl Mods Are Needed Other than Those Indicated in Ltr ML20207F1811999-05-24024 May 1999 Petitions NRC to Suspend Operating License of NMP for NMPNS Unit 1 Until Such Time as NMPC Releases Most Recent Insp Data on Plant Core Shroud & Adequate Public Review of Plant Safety Accomplished Because of Listed Concerns ML20195B1861999-05-21021 May 1999 Requests Staff Approval of Proposed Mod to Each of Four Tie Rods Per 10CFR50.55a(a)(3)(i).Summary of Tie Rod Insp Findings,Summary of Root Cause Evaluation of Failure of Cap Screw,Calculation B-13-01739-23 & Summary of Se,Encl ML20207D1541999-05-21021 May 1999 Forwards Issue 5,rev 0 of Physical Security & Safeguards Contingency Plan for Nmpns.Summary of Changes Included to Facilitate Review.Encls Withheld ML20207D5331999-05-21021 May 1999 Forwards Issue 3,Rev 1 of NMP Nuclear Security Training & Qualification Plan.Summary of Changes Is Included with Plan to Provide Basis for Individual Changes & to Facilitate NRC Review.Plan Withheld Per 10CFR2.790 ML20206S2621999-05-16016 May 1999 Expresses Concerns About Safety of Nmp,Unit 1 Nuclear Reactor.Nrc Should Conduct Insp of Reactor Including Area Besides Core Shroud Welds & Publicly Disclose Results at Least Wk Before Restart Date ML20195D5911999-05-13013 May 1999 Submits Final Copy of Open Ltr to Central Ny,With Proposals Re Nine Mile One Core Shroud Insp During Refueling Outage Which Began on 990411 ML20206P1981999-05-11011 May 1999 Forwards Response to NRC RAI Re NMP Previous Responses to GL 96-05, Periodic Verification of Design-Basis of SR Movs, for NMP Units 1 & 2 ML20206R6941999-05-10010 May 1999 Responds to 990413 & 0430 Ltrs Re Apparent Violation Noted in Investigation Rept 1-98-033.Util Agrees with Violation, But Disagrees with Characterization That Violation Was Willful or Deliberate ML20206N0291999-05-0707 May 1999 Forwards Rev 39 to NMP Site Emergency Plan & Revised Epips,Including Rev 1 to EPMP-EPP-03,rev 5 to EPIP-EPP-25 & Rev 5 to EPIP-EPP-28 ML20206G8121999-04-30030 April 1999 Forwards Comments on Draft Reg Guide DG-1083, Content of UFSAR IAW 10CFR50.71(e), Dtd Mar 1999.Util Generally Supports DG-1083 ML20206F7731999-04-22022 April 1999 Forwards Renewal Application for SPDES Permit Number NY-000-1015 for Nmpns,Units 1 & 2 1999-09-07
[Table view] |
Text
c
. ENCLOSURE 2 E. C. cRodaBaugG 09ssoetatas, Dnc.
4625 CEMETERY ROAD e HILUARD, OHIO 43026 614/876-5719 February 10, 1986 Dr. B. D. Liav, Chief Engineering Branch Div. of BWR Licensing US Nuclear Regulatory Commission Washington, DC 20555
Subject:
Dovncomer for Nine Mile Point-2, Your Draft Memorandum to Bernero, Dated 1/28/86
Dear B. D.:
Renee Li called me on 1/31/86 to ask if I concurred with your letter to Bernero. I told her I did and this letter is intended to confirm that con-currence.
Since the meeting, I have looked through the Report, " Review of Struc-tural Adequacy of BWR Mark II Downcomers for Nine Mile Point #2 Nuclear Pov-er Station", prepared for Niagara Mohawk Power by Stevenson & Associates, dated 20 January 1986. Renee Li called me on about 2/5/86, saying she was writing the SER portion on the downcomers and asked for my comments on the Stevenson Report for possible une to her in writing the SER. Renee also ask-ed me to look at the downcomer fatigue evaluation. The remainder of this let-ter gives my comments on the Stevenson Report and the fatigue analysis.
Stevenson Report (Report)
The question is: Since the Report contains three checks of the ability of the downcomers to withstand a moment of 4914 in-kips, and assuming 4914 in-kips is an accurate (or upper-bounding) estimate of the maximum moment that can be applied, why are we still uncertain about the acceptability of the struc-tural adequacy of the downcomers?
4 I 4
The Report, page 7, summarizes the three checks.
(a) Hg by 2x elastic deflection N/4914=1.12 g
(b) H gby NEDO 21985 H/4914's1.03 g
(c) Hg by E a 0.2 t/r Hg /4914 = 1.03 ,
j The problem with check (a) is that it is based on a small displacement analysis that cannot predict buckling. Indeed, the Mg = 5503 in-kip corres-ponds to a strain (see Table 3) of about 0.008 If ( = 0.2t/r = 0.00625 in-dicates the onset of buckling, then the analysis would be invalid for locds greater than about 103% of H = 4914 in-kips. Accordingly, I view check (a) 3 as not meaningful. .
Check (b) creates an uncertainty in that NEDO 21985 was developed for piping systems. The downcomers are different than typical piping systems in that:
(1) Piping systems have two or more anchors; hence, a single plastic hinge vill not lead- to gross plastic displacements of the piping system.
(2) Piping systems usually have internal pressure. Thepressureterm[See Eq.(1)) is usually a conservative aspect in that, for large r/t, the pres-i i sure does not reduce and might even increase the moment capacity. The l
pressure effect can be illustrated by assuming P = 100 psi in Eq. (1).
) ,
j In that case, the allowable moment would be M = (1 5S 7
- PD/4t) x (1.>0.006D/t) x z r(15x22750-100x24/1.5)xo.916x1619 = 4823 in-kips This relatively small internal pressure (PD/2t
- 3200 psi) would change the NEDO criteria from pass by a factor of 1.03 to not pass. l l
1 1
! i i
4 It is pertinent to look at allowable moments if the applicant had chosen 1
to consider the downcomers as structures subject to compressive stresses and 1
used ASME Code guidance for other-than-piping. Enclosure 1 sumrarizes that ,
4 look. These allovahie moments are all less than the calculated applied mo-ment of 4914 in-kips. Perhaps the applicant first tried that route and came to the same conclusion.
Check (c) is dependent on the validity of Es 0.2t/r as a buckling criter-ion. Fig. 2 of the Report shows data from Reddy's paper. Inoking only at Fig. 2 of the Report, it appears that at D/t = 64, a margin on strain of about 0.0088/0.00625 = 1.4 exists. Of course, this .does not mean that a margin of 1.4 exists on mo=ent capacity; the margin on moment loading would be less than t
1.4; perhaps as lov as 1.1.
I Because check (c) depends largely on Reddy's results, I looked through t
Reddy's paper and prepared some comments; Enclosure 2 herewith. Three role-vant aspects are:
(1) The specimens were 25 mm (1 in.) nominal diameter. To obtain a specimen with D/t = 61.46 (Reddy's steel specimen 4), the vall thickness would have i
to be 0.0163 inches. These would seem to involve some experimental prob-l lets in making such a tube; particularly when they were 24" long. Reddy does not discuss actual dimensions of his test specimens; e.g., actual
, vall thickness or out-of-roundness.
1 (2) Reddy states that he used " stainless steel" for his " steel" specimens.
The Stevenson report, Fig. 2, indicates the material was Type 304; I do not find that in Reddy's paper or, indeed, whether the stainless steel was 1
- austenitic or ferritic.
I i
1
- _4_
1 (3) Reddy states that "a number of lengths of 25 mm dia. steel ... tubing were procured and drawn down to thinner vall thicknesses." Reddy, in his j
Fig. 5 (b), shows caterial stress strain for some of his (as-dravn?)' tubes.
He does not give the units for his stress-scale but, as indicated in En- .
closure 2, I think the units are megapascals. If so, then the 0.2% off_
set yield strength in the axial direction of the tube is about 750x145 =
109,000 psi. This, of course, is a far higher yield strength than would j be expected for the downcomer material. In addition, the material was probably significantly anisotropic; e.g., the yield strength in the hoop i
direction might be significantly different than in the axial direction.
i These material-property aspects raise considerable uncertainty as to their l direct relevance to the downcomers.
l l The precedinE is perhaps sufficient to answer the earlier posed question regarding why, despite the Stevenson Report, we are still uncertain about the i
j acceptability of the downcomers. However,, since I am working on the subject, there are some other comments that may later (after the present SER) be rele-l vant.
j Enclosure 2 includes Reddy's Fig. 2 with one test data point added; that i
being the Battelle test on 42"0.D. x 0.280" vall pipe made of Type 304 au-i
, stenitic stainless steel. Enclosure 3 contains my summary of the Battelle test.
Reddy's Fig. 2, in contrast to Stevenson's Fig. 2, indicates very little margin between the ( = 0.2t/r criterion and test data on buckling at r/t = 32. .
t 4
i i
l t
- Reddy's Fig. 2, in conjunction with the Battelle test point, seems to core sist of two types of tests. One set includes the open triangles and the i Battelle test. The other set consists of the remainder of the data. The various references should be carefully examined to see if the reason for this i seeming difference can be identified. The answer may be significant to the ,
, assessment of the adequacy of the downcomers.
l The calculated maximum applied moment of 4914 in-kip presumably is due entirely to dynamic loads. During about the past 5 years, simulated earth-quake tests have been run which suggest that the dynamic moment capacity of piping systems is substantially greater than indicated by static-loading tests;
- e.g., Reddy's Fig. 2 tests. Enclosure 4 describes a recently completed test j involvingType304stainlesssteelpipewithD/t=49. It may be noted that it
! is analogous to the downcomers in that only one end is fixed. Evaluation of 4
- this test, and other dynamic loading tests, may provide a good basis for ao-
, coptability of the IEF-2 downcemer design.
j Fatirue Evaluation I obtained, a't the meeting in Bethesda'on 1/24/86, a copy of "Downcomer
]
Analysis and Fatigue Evaluation", Stone & Webster Calculation No. MS-1869-2, l dated 1/20/86. Fatigue evaluation of the downcomers is described in pp.67-127 l
l of this calculation.
The results are summarized on pp.126 and 127. The maximum cumulative
- usage factor, U, is shown on page 127 to be 0.182; the code requires that.U i
f be less than 1.0. (There is a " typo" on the fourth from last line on p. 127; 0.639shouldbe0.0639.)
f f
The evaluation is for a location on the downcomer at the too of the fil-i let veld between the downcomer and the floor plate. I agree that this is the
{ critical location for fatigue evaluation. The stress indices used are stated I
to be (pp. 92, 98)
C2 " I'43 E2 = 2.0, K3 = 1.7 The indices for a girth fillet veld in the current Code are:
C 2 = 2.1, K 2 = 2.0, Ky=30 If U was calculated to be close to 1.0, rather than U = 0.182, I would be inclined to ask the applicant for more justification of the stress indices.
However, I think that using the Code indices vould still give U << 1.0 The analysis method is not a straightforward application of the Code rules. This can be seen by looking at the first line of results on p.126.
The value of Sdt = 4 kai corresponds to !! = 60100; not 34188; see Fig.
I-9.2.1and/orTableI-9.1oftheCode. It would appear at this point that the tethod is very conservative. But note that n = 24, whereas on p. 71, it appears that n should be 5x10 = 50. Using !! = 66100, n = 50 gives U1 =
50/66,000 = 0.00076; not much different than the indicated value of 0.0007.
However, looking at the third line on p. 126:
Method 11 n Ui$
1
!!s-1869-2 77425 7422 0.0959 Direct Code 156000 24000 0.154 In the above, the estimate of ns W 4000 comes from p. 71; n = (84 + 169 x 30) x 4.8 = 24739.
I would have to review the MS-1869-2 method in much more depth than I have done in order to cay that the method is consistent with the Code rules. How-ever, given that the loadings included in the evaluation are sufficiently com-plete and the stress calculations are correct, I deem the results are sufficient
, , [
I to establish that U 41.0 in accordance with the Code Class 1 fatigue evalua- i tion method.
NRC might want to examine the MS-1869-2 fatigue evaluation method in more t
detail from the standpoint that it could establish a precedent for future fa- {
tigue evaluations. If so, I would be villing to look at the method in more detail and, if appropriate, perhaps frame a'." follow-up" to Stone & Webster.
Yours very truly, bkW E. C. Rodabaugh ECR/cr
Enclosures:
(1) Other-than-Piping Allowable Homento (2) Some Co==ents on Reddy's Paper (3) Battelle Buckling Test (4) NRC/EPRI/GE 6" Sch.10 Test ,
cc: Renee Li .
L 1
I
+
[ncl> s.u ce 3 0 H,ar-1&on- Prpinq A//. =r e 6/e n. <.e/s 1/'ofr s
@ */@
. Fe e P;,,e d:s oesna>> : 2 + O. re. x 0. n r s a.a , r / 2, tc 0. 2 ?r, g/t' 3z Ma /e vocs/ 3 SA 322 fjfe B o 'l ,
Ify* 2 2, I 5~*f
Tev pgraJ. ore : 3 0 0 l~
(1) ASME Code Ses/r m .T 2 , O.v. I or Sec /,.,n M* NC- J t JJ. co As 0, t 2 5-l(r/f) - 0.125,f.3 2 s A oo 29
/rons fsy. S- UH4 - t r. I or Foy. .El - // o Z, *':
8= alto >av/. ca y ra>rses sless.r * //00072l M* 8E= // 000 < / 6 /.1 ~" / 79'O
- a< kip i 2? AsMf Code , Sec/.n 2, &pendu l'*, F~ /231. s id) 2/3 e/ aeavr /aly ca/c.a/.hd *** espori ,ra/./1, d a fu evo t e d I, a st< tosy .
Tofto.sy thtt As kn, rojo (t s e n }s al by 6 ' A 2 f)'t' s.o el fre. s $/ttsnsen *1 **tg**r / , t /. 06 x Y 'Y/ f
/, d 5 Jr f f/ */ X */.3 "F 3J75' / <a /c / /n (b) 1. 5' x Af8- 3 /13 ** /. T ><. I 7 t o v 2 fo ? o .n kry>
(NG- 3I$ b der o eso f s ever o//o.a k/s e e .,,, ,, r p o s s /re girs other No., 5,*se d.os la We 6'e lc e fl4 o<e fr *f le k J* AfC- 1/19 b) esfernel f142 0n.
(c) Co de Case [Cett N-20Y, fres ven* bly} U:14 fes t.: el falt /y of /. S 'f. //stoy -/St/(e), -/stes (n) a.* d -/1/t./. / ta) of Cats. Case A - 2 Bf: !
?ien l cypeer t Qv et rl = 0. tooD f t/r ; ac = 0. 707 gyy .
florpor of til, lt),-tritt*Q irscen soshng /t c /.1/-Isis G F/fg in L C as. Cua. us t ,y ?*= FS = /ssfor e/ .r a /, i, a I. 3 y Joy Gjeds mi apres 1. M f, = 0.20 7 x (f.3)~ / /5 x a%)s.c.sega27etop1 a
fsj iEll-/ y { [ la l 'l + 7. 3 2 ) * /36, coo =v R ::: 15' 100 p.s; jv) , 0; y a 2 Sg o ,, .;;,
. s Oc/>s er t 2.
So m a G n, ,u,,,fs so Exp ,,,,,,e.</.) Asp a fr 2/sojst.
of Cedd y 's paprs
- 4 Srpw. usa 41 Siady et if.a. . g ,f g fla5 he Gaskliny a f Circular Oy /.'.e olers in Parc feeksy ,
. int. 7 Se lads $/ruslares, Vol. / Q / f *19, pp. 6 6 3- f.91
. O1 0:m ..n i ns .I +,,/ spe,~aas fleddy .cf h > /A f has specorucer were 26. s (lin.) ne r.,i.r el d'oro c ht, fr 0 0 m ne { 2 Yin I /e no . To a 6 / air, his 7*.6/e / vft- va lv s e, /4< esatt t/ tic.Ausst
&*
- u ld hm lo ha ve k ee n b e luire n 0. 0 / 0 " (3fe u e r.e 2 ) *.e d 0*02'0'[Tjec/#!*** '* ).
su s)/i s s ,
(an sielgri,e] i$n. fe ,,y rf o f 2 '/ " , to a 6 /e s.s dos e urn 11. th sc A n c osts say , d to% , toov id s e em se he a tough pro s, leser. If if were a. psoble ,
1 I?cddy Connjlele /y iy noees N; e f. , l>e does no/ yare 4 any n.co.t und as1L tA<st esses.
Tasle I shc.wr r]t - va /vi s to 'l sijn ili a.., / hy n, e.r . TXi; io en. /uyt, Git te a ts ,tring o'n M al i f tasolic a h s Hal or /ea s t a v re-je. a s /ae l sar *R tt1re L -e rr> < s *. ray 9 vyrstf.sa /i4 f ent hrCk)
I ha ve k e e <> m e i sed ; 6of noi <<assces,,9 ;er /4.) d a',.<,i/.s i /6afofe.!dy 1A*vy4t h e A.n e u.> b,e (o ver ay e ?) cosa /A ra h.e e o e t' e a te sa t c . D oo *
dl hssy la. //s.i //> ert in a Jorf t str1 ero-la r,** lj am war /AscLn ess oud ray k his (e.s vif.s J ., ks Mj. 2 ( in c l.ided he<e r;ili ) .clea st u in dic a /ad a s o bond of r/4 ; joubsys 4 .5 a r a } de in hale /, A valve.
1 0
f J E.,c/o.sare E O ef @
U) MafreisI f.e ~ Slec/ Spect rerr.s steddy a fa/es f6a/ 4e ased " g/arajeg, g/ga /
- far 4;, ",;,, j ' ,p,,,,,,,,,,,
Sfain/as s afeel car, 4s ass ent/.c. en frerific . Ne sueat L fvets /M.) rue o,.a /* ~ J was asslan t/sc, m aybs lit e 7y* pe soy, h*F Reddy dee r o,.i Jay se .
It) .7asi Spuer,,,er,r ar b rtrain Douse I! eddy aia/os : a no 6er a/ lo.rjAs .1 25 o- dia. s/ce/ . /,%y suara yr.ev,od W
or>d d r a s., +. th i n.,r e w .t> fru. k., aries . Meddy . toes so / say , t, ! z w../J yaass W. dra cciaj war don e a l roo < /e pora /. ors and *% rp scom*.,o .va rs s'* * /* d oil 4 no heal dreal.ne rf al/ar deswi.ry. .
/Tedd y _'s i~<f. Th) is ts cluded b e n .a;M . ,c, ,, ,, ,) aa/,,,/
Me3aa,,4,.,is;
.ig /k m a/ecial ;n tk fes t sj ec t meirr ecp r<t on itI've o f a n n e a led, +ype, so f such at is .as ed fo r NMP- 2 dem co mers , fleddy's Sy. Sis) does or d .ch.us lh an s/s for V. lle sae s t r, l{ nts assJafe 5tddy's 4 lrt ) " ka 5 S A $ "10 f s?,
3' ' ;
l ben }/a kneer f or / son o f 1% e u r e't r i ndice /r/ /Esf O* " '/d o c o r r o ofr a ru cli i
?'o C*ovtet Mef.f arcal/ la ps), enf .*** */l'j* ATJ T
M Pa b y / f C an d, sir,ce f u o se i v 5 c 59000, uis a r <. es a/ 14 g.nss /Ad IEt 0~- scal: Aris/s o<e M i% . T / rave - added /Ae 0. 2 % offse f yroll s/renjM ax sol d:r e s /se a,,
-t a n'eddy 's M . Sto) ; /4a) 3 irid sfreny/A. 4 a hou f //0, 00 0 y si. ??str, of covese , j is far ef reeler /A an saoald As ceprefed for ennes/ed Typs soy maio r r * /. l l
1
Enck.tute 4
@ of @
t.5e )
In aJa. lies, a c.id Jr.wnW,Ikn rs3 n.icn H3 ani.r. 4.eic. Ite aJy :
d,<.eknewnHias a n.t I >> w a - doa a f aJ. A>c ea a,nrie , fr< y. a rl y M in is ho.,a a.,eehan .>,,yis i sa.
These o,,sfee,al ye.,,arly aspas/s ta is e ussstderobly weer/non;/y a s /. f4 elsr es/ . r cle ra,,s e o f }Ces e fes /r k /Re NM f'- t dawncomees.
(3) Teshna Pet > e advic Reddy does a f oo) jo b / deJCidbiny /toul he lO*ded l$se l*EY Sf ts/ryeof, IVitis rosyset fa c. ~p ar is.e wed fi s /.c $3 e Ts er s ( e.f. , GaH, //e, se e . a dded a., d En clo eure 7.D fot.s { , , ,
F3. 7 y , . I?e Jdy 's +n e & d o f <* m pe.smy one o.se o fs & revyf re/a hvely La siy niiicany' a nd, in taa easp ee i, rn.re J:<cc Hy eryid esd cops ~ ay p hc.co>a le NMP- Z do.so ca. "J Man, N e ea a ay le, Bal/r A 's fast.
(4) Ecpers nesla / /?cs ulf.s o
lltJdy (pe 4is p. t 75 under "Teshny traceJure " ) imp /. e i M/ the.le=Js-l uro ene.Js?]sf. collapse emuld k 'c/asely e3haraleJ. Ha ss e ver, h e d.-v u./
1:a h ulale an y c ollapse m or>< e,. h . I th eaj h / o. s* //af s e momen f r.s y k +
4 L< it emed fee spacimens 7 a d 'l fra m d'eddy 's J53 . //. h' owe ve r, I i
Y$rD *f O f0 AM s
- En clos ure 2 es e 6t1 feddy's Ey.(1) is pro h as 17 wr o ny ., i + rs ,,.e .ti ,e.,sn.,/ess o n.f dis ay<tas erin W A;-ra,si.
ny - <eer/e us etesi.,.s.n e 7 ., neay's as..., ica,.. . - . ep ,, m >.
m aca,, e,as a ,,..s.v, -..,,, a ..,, a.i & s.,. s . i, ..,
Y/t and no/ on fla. 9 red / >.<.a.<r.,/. I t dtsageres w 11A IAs dja ;n.%.,
in k vs a fa l:o o r ec}io or , k -= 2c r'j't , 4:<.h to al fees / plavoin/a .
cc >
Reddy 's 53. (to) is c,ereci, b ., ) E;. cit) ;e s, / correa/ s'or eijoir lAs p Ic usible de li.r.'hwr in 1%. n. h ston ( giv e.,y m = k t/r') or //<
i mp la w s.6/< cielensha.,i o f- Ej.r. (!) o.,) (9).- In d e r d, .r.n c e ff. (9) saya we old La 6_)
l iia f k sq in dejr., ds.e f a f k, 80ee f eJa t"/*nsktp he /de r n on a.s J k .
(0) //a / bei.,y readi/g diJcourajed, T ce /cula hd h. cadsp os s., . s o n }- /ne r, . a s ,,, , ,,
itsing m = M/(Etrt'& ) and, fn , , m= 0. si. A r.s y i ves M = Errr2 f m = [3 uso 's we o. s ',/23.j]. g g.it s sg coa , n . is au.,y iceady's Ej.te> ae,c,,, s . , a.; , ,,, ,,oa y:,e n , s s,oe ;,,-ie No sa , u sta,3 /L JYE Oc fjssafron ea rlon P= o, Sy - I'o,100 poi 3 . <s (V{ = /. S x lio, 000 g i o r 9 x 17 e a. S'/23. J -= 2 27 e s*s s -16 n + is i e p a in f, z pve u.y . l I
. .- Earc/o. rare @
$ oI@
An experimental study of the plas buckling of carcular cylinders 678 a.
Os. i e poswe.steet
(, ' e prescal*a4N 0 03- ' e Wdhed Enseewa 16I e Battamen tel a SewwhangISI 03 e O Clasacol elast<
e ',,j (, e 0 6 t/s
~
80, ',;v 03-
03- c, p ,
e o 03X._ _ _\, '
c 0& ,
P
d = 0, '2 t/t' Oz. N.
a 02 --
N
= _ ., f w . 7s
@,a , $ sYsSt ge 0, 0 0 0 f Fig. 2. Emperimental values of critical estreme Abre compressive stb tubes in bending, and crideal strains for tubes in asial compression, vs alt (a)
/
. . . . . . - = -e Cr- anik !! ..
0
- ; " ,'2
._ . . - / . /
n
,.,'i -. . ,.. a
, , ,, - ...t-
=
, AlatAl g .
E - A3. A4 300 ...... ..k3As 13: ,
C fl.)
II (b)
Tag. 5. (s) Dennition of parameters in Ramberg-Osgood representation of stress-strain curves:(b) actual compressive and tensile stress-strain curves for specimens I,2,10. A3, A4, A7, A8 and A9.
E,e c/o s.ra .5 t/te/s s Bage //, res; en gz'o.o,e o, z g o ~ ,,a O of @
Vyps_ Set a v a le.,the stain /rst sfre/ffe,fsp.%.*ftti-3
^
172ss a b1/ae/ Un ha.ted *A d ala tro ,+< Aslle//e's Mys s d nt Pipi .y Preyro n, sj>anurec) by NRC, /Y:// nyist i.c fra yeajesf- me-eike.
Ifu fes/ u as & ren fa d e tar miere /4 b.re u.my in ,m e-/ r} 1 6 y y e. //* e u.v e, b e aria, d ,) oce,,r and 7 ,%;ns y, fe,rt nooy se referaad /. bL trajoal.a o I- JVtt!- x Do .e n c e ~ res ,
Ik e j>;jm loediny afr,we /ar, and some puri6ly sty.oiliced de /.sh ore sk e k. bed bel a
, u .3 e 42 x #* 0. So u.4 4220290 4 2 3r o. fo na.//
q 304 f> f t q roddle, se e de fai t g,,3( l Beafo, se e dele:1
'( F/t seedellss* pjg fjg ( F/g 13.S*ft. } // Ft 13.S // w 4
', Bac Lic l y . , .
eo. So ,, . _
a rye '
,- its' M
!) i
/ sa/Jie f.
ytik wcld
.In } hts '/ Pein + 8e,rds,17 Te.r), tao. Cverte ocevre d af F = 9'?,.r7s /b.
Tle. h ucleting inomraf was 97, S 75 x I.p. s x 12 /t = to co in.xy TXe nemi,sd elashe .s t //u hockhn$ snomea,/ uns 80so sto'
E(yz'-91.19')/fx 32 No shotos yayes wrec u sed in % b o ek /td r ef ,'o rr. T/u un a lert d yse id s lu.ejM
&2 519 eo f.1:, we es/imale that sh sfrein in % b est led a rm was not-m ocJr y<c</ee /4 en /As da s it c r/r atos , S/l
- 2/zoe/29xJo'9 0,oaos 76ts poi.s / Is shosr f ra E n clo sats- 2 ., p . S .
l
Ena/osaru Y 2pejec.
Nrtc,/EP/EI/GE 4 ' Scb. 10 res h D of 0 Sec. lion AX keld A
'/'/// )
7
(
f," Elbof Sch. Y0 f
<)
/.
t -I L
) i/
e s , s.s. io sa r.pe p. p - c. u 1/ o. o v n. y Lu.u w
= >
Inga f Sirr>vla/ed EarA;vake Mo h.n ne. tes/ has 4 ern co m,,Ja led. Failore con.usied a f ^ a fa fry v< ces er.
o lo ng tueu A . .E b is poatble tRet safk a.,+ /,sd was applie.L 1. /A.J Se e/ica, XY mom ent.r wo, e a lw e sfahe tin,.- f na m e., /s ,; e.g .
N G Do - 21115 lien.}s. If so, anol considereny th anc - en l~ asedered and h ete) oli aroue t, 14. tal re seHs may k.<a/euar/ fo evo/v ho.,
of h NMP- E dow- c o mers .
9
. /