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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] |
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@ O R. W. Starhlu 5060 hvens Co r.a n Rcod CMutita, 0:iio Address reply to:
Dr. R. W. St achle Dept. of Metalhtrgical ID r.
116 We: t 19th Aveme Ohio State UniversUy Cohrd>s, Ohio 43210 .
9 A:ril,1970 Mr. R. H. Eb3elken Assistant Dirccitr of Inspcction an-1 I:nforecrient Divinicn c': Cr 11;nce Unitcd E'nt n A'xeJc rn:r:gy Ccrminsicn 7920 "xfolk l ,c:.:a rctheda, *aryhn3 DaTr lab, ,
Daring our twaring on 26 April,1970 in ycur o.Tfice you requestcd my ccrrycnts in tw arcas: (1) With resp.rt to the varicus rcrair prcccdu es t/aich night ha used to repair the eafe crds,1icat are they ard wlut are Iraaibic difi"ultics v;hich might b2 enecantere3. (2) Acc.ning tlnt sensitinol stainicas cteel continucs to b2 usci idnt kinds of prceautions micht be enrciscd in cparatin: plcnts ard durira plant construction to mininize t!'.e possibility of unc:poctal stress corrosion failurcs? This 1ctrer trancaitu my ans;;ers to these questions.
Repair Proccdres ani "' heir Inherent Probles Listcd balcr.; are a numbar of possible prcccdures by which safe erds
.now rade from sensitized stainless steal tr.ight b2 rextired. Discussed og with cnch of thcco alte rutives are possible con:ecns daich Iray effcct gg adversely the quality of the resulting repair.
ng .
88 1. Weld enerlav Sn o ~
.tv The nuin considerations in weld cuerlay procedures are the 00 c,. s follcuing: .-
no -
q< a. Type of rutcrial urol: 3 pes 304L,303L,316L,321, om no In:oloy-800, Incenal-600 "L' b. Thickness of overlay
- c. Proccdure for suld overlay inch.diny hoat input, size of weld bead SCO attaChad table.
~
M 3 '
'"~"
. l i
Q .
Q ;j
( d. Irg tetion p.cccdure to aurare abacrce e2 Thws
[ which effcetively cgocc unicrlying -a tecial. ,
- c. Over]ay of Poth inside nrd outside va. enly the inside,
- f. Residual strcr.s in resulting onrlay.
- g. Susceptjbility of weld overlay r,nterial to other forns of aLtcch.
Prob 2bly tiu most sericus quanticns of cuality in resulting we]d cr/crleys are:
- a. UnrM +r cf r.;:MnicTl ric7crues o" t.he cemite prcAu'; d by tha cver2ny. It is r.ot 1 car tbt r.i;;h infomation is available, for exanole, in tha high strain-lea cycle fatitjuc, cr the th,.rcal check behavior of such structures.
- b. The possibility of lack of fusion c Tosirg the urderlying t materiill to the cr/ironment.
- Clrnairry the rutt al itself s6uld irclu-Je considration2 cf the type of failura s.hich is rcat Jihely. Since the prir,nry failure raie hre is intergrara]ar as associated with cnsitiation it is most roaccmble to rc".cVe the carbon (L-newleu) or use a stahlli zed rate-ial. Ecnicr, the a.~n tnc
=i of scnsitintti5n hre remitiny frc n wahl ove" Jay is not so significant as tMt in furnace sensitizirg.
? To my know1c3ge there is littic information on the ECC behavior of p sensitizcd Incolcy and Inconal. Despite the fact that the weld sensitization is not so as the furnace sensitizing, there is no clear indication as to hcra much is too btd when related to the other variables such au stress,
, contamination, ard oxygen. Regarding a specific choice ard priority of possible materials it muld secm tMt a Ica carbcn In: cloy-SCO offers the nest rcasonabic ccmprcaise. This alloy has a high resistance to the
. transgratular chlo-ido cracking which might start frcm the cutside, especially bccause of the nature of the weld cie-lay stresses. Altra, it does not appear
_i to be so susceptible to the ECC t.hich cccurs in Irron21-600 linen expoce-i to m ter--02 environments. Typa 316 stainless should be avoidcd due to its high susceptibility to ECC.
It secms to me tMt the weld overlay procc ure 4 prcduces tco much
- uncertainty, especially where these safe erds are likely to be subjected to i
high stresses, to be cuploycd withcut substantial ccgerimental justification.
I 2 Replacanent Piping ,
i- Rather than using weld crierlay, there is the possibility j of cutting out the pipe directly and rep 3acin7 it with a seccially fabricatol pipe. The nuin considerations here are the followirg:
m-U a l mNm ',
i . 4 i
r O~ 3_ Q
. a. Th2 we]diro of the rc.nlacerant to t.hc vessel muut be consideral with resget to &c mld sLre , , relief. . .
i b. Tlo choice of traterjnis v.culd be the suo as abo re.
l The major probicn here is prolubly the choice of allaf. It secn"; that the most conservative choice s.culd he a lov carbon g Incoloy 800. Itwaver, an 3noc]cy 800 maid 1.e acccptabic since f the aaoant of sen-itination during weldirg is prolably not I suff!cicat to cause difff aaltica. The usa of a stardard car.crcial p nnterial which can he ::tchine.1 a:d premrcl in the shop sccTs
- to 00 Pr rcre nMme t' -
- c]- c/ cla". La c mr t of l testira to vinilcate the c;a.tlicy of the weld cr/erlay v.ould bc greatcc than tint for the fabricatcd pipe.
r
- 3. ' General Discus 31on of Materialrs, 2 There are a n'raber of general considerations in clnosing the 5 nnterjals t.tcther the weld o/erlay or solid rqdac;.n=t is uscd:
p k a. Type 304L cn3 304 a
s TTnen the cat on is 30 arcd fer the relativclv 1ceer Z nickcl 't;c 30 :L the clicy becc.nas very unstable .'eith '
rcy.d.L to ferr...sj the Zahtm 'bcdy centcca cubic) j l pluse. The nub;. rial can be e gceted to inve tw pinses '
r as it beccr.cs prcnrossively recre pure. Ecwc/cr, it is a not clear tlnt this duplcs structure is h2d. Tha tm a
pinse stracture is usually less sensitive to transgranular e KC induccd bf chloride although the amount of sccord r
plusc which will result in this structure is not clear.
Also, the tw tahase nutcrial teMs not to becone casily '
[ sensitizcd.
s As this less stable nnterial is deformd, it will - - -
transfona to an intermediate nnrtensitic phase; this will F-strengthen the alloy.
R i- The 304L stainless steel generally lus no better
- , resistarce to chloride induccd transgranular stress corrosion I cracking than the ncimul grade. -
m Type 304L Ins a lower allombic strength than type 304.
E -
f 'r -
- In sununry, it is not unreasonable to use type 304L h .
if appropriate allomnce is nnde for lo.eered streryth f aM caterior protection is pro /idcd against chloride -
E .
irducM TC. hhile the amount of sensitization in either ER b -
r
=
= 4 L
mp .' _~__--.--
l .. n
. . g +
o.I I attachu.nt wolds er the ve1C overlay wi)) be less tlan - --
the furr na senaltirem ca n o, i t i c not n' e1. ntly -
c]etu: Mt cu bimtion o? strcns, tr.gerature, oxygen, ard oth= conta.mirar:t im!d esce tEc weld rcnsitirul maler.ial tn unic;. ja the intergnmuMr NC. If it were sin.n e::pri.nentally that this v.culd not cccar, the imentive to une the low carbon grades nny be lessen 21.
Ib'.:cver , ruch a bort.:c should 1r taktn only with careful delibarction. - -
- b. Typa; 316 ani 316L The :,ain bria for usinJ tn:o 316 is its greater resistance to general corrosion ard pitting which is achicved by the acidition of nolylrierna. Ibwevcr, this alloy is smez!nt raore susceptible to chloride irduccd TC than tn>2 304.~70icse allofs contain slightly higher Ni tlun 304 to stabilize the structure against the ferrite fc=1rg tc.demica of tPc .io. Frcr. a practical poirt of -
vic; the.m alloys precily diffcc little frem Tupes 304 - -
and 30b. -
- c. The hight nichel stainless steals: 303, 309, 310 Thesa alkyo c 2c- tM aic.n'r;a c2 pro;rcesively improvc3 resistance to chlorife inluccl FCC. In their -
low carl:on fom the increasc of chrcmium and nickel t.culd off set tJ:e loszerirry of strength in the 304L. Tha b2havior >
of these alleys in tha weld sensitized cordition with respect . .
to intergranular TC is not known. It is reasonable that - -
these alleys i.culd prcvide general imprcuenents only because of their inercased alloy content.
- d. The stabilizcd stainless steels: 321, 347 These offer innunity to censitization litt no improvencnt in resistance to chloride-TC. Difficulties are of ten encountercd in achicting good weld quality uith these materials ard spccial care rust b2 taken during the welding
. operation an3 subsegacnt inspcction.
I -
- e. The intermediate nickel alloys: Incoloy 800 ard 825 -
~,
These alloys offer the optimum canbination of resistance -
, - - 4 to various forms of corrosion kncr.m in this alloy systan.
The nore car.on alley is the 800 ard its use in .this application is prohiblj the most conservation decision.
G 4
6 6M E& mN d
T
~
- +
(9 Q
- f. The high nickel alloys: Inco]ey 713, 000 .
'those allovs of fer al;nolute resist /trce to the chloridc-inium 1 FCC but are micceptible to crackJ:rt (
Jn Iwo t-Acr . 0 pre '.:atcr containiry trace tc.ounts of eggcc cr 1 cad.
- 4. Cource ~of Act.i._en .
Pro!xibly the rnnt conservat.ive overall ccm:se of action wculd be to ure sh;; fiirica w". :afe ca:., of Ircoluj JC0 '..:hich .culd i n @ul j e , ~ 5 t i.- ._ tE m , .
t c.mn'. an1 c ."r of R nriti u : c: ti ec ct _ esi ' , x21:ly r.1 be sufficio:rc to rcqaire the use of a Jo ; carica allcy. The Ica carbon grade of this alloy is not a widely teal rnaterial. My next choice tuuld b2 a Type 310 stainless steel bccause of its ranc.drit jmprovcd resistance to chloride FCC. I muld not suggest the Icw carbon hcre lxmuse of tha bck of carcrcial c:qnrie:ce with such a orade an3 tha fact that tha higher Cr in tha alloy r;xy protcat the grain iraMarica.
Sfety ar i nrctetive "carmes fc>: Prczentin, St' ess Co' rosion Crackim ot Stainb. s allces W er" recreci : ar.dir.g c: stainicaa % c allvg is s ifici."cly .
fregacnt that spccial attention cheuld be given to pro:chren for re?.ucing the protnhility of its occurre:ce. Enile these alloys are gaite resistant to corrosien in the c hsence of sLrcss, they can fail rapidly (within a ,
fcw hours) under cc-tain miironmntal circostances when stresssi. A nomally -
corrosion resistant r:aterial givea a falco cense of security to users despite tha possibility of such a virulent failure prccess.
Because of the wide use of stainless steels in reactor plants ard bccause of the ever present possibility of unevpectcd failure it is appropriate to take special prceautions not only during power operation b2t at all times (testing, construction, shut down) . Spo ific measures which might -
be considered are as follcws:
1.
Leaks ard drips arry.inere in the reacter should be stopperi, collecto1, or directed to the drain. The drip by itself is not necessarily Inrmful bat dripping on hot surfacca where imarities can corcentrate by c/aporation can lead to rapid ECC. Ezen if the drip water is pure, it nay pick up impurities fran the surfaces over which it travels airl deposits than on the hot surface. , ,,
2 Any fonn of chanical contamination should be avoided until approvcd 1ry a person with authcrity. This includes cleaning agents, lubricants, ard organic wastes.
4 a.
7L.__--. _ .
o O
- 3. Aslestoa t.y,m irreilation natc ~ial frca 'zhich conir irants can le 3erl xl shold M m uid .1 L uny toint in the plant. 4 It mald c 1 m to vu .'. .t tc w:' . . ci nc. #7 the metal cirror insalatiam cu.rrrJy u: :d en rrecur.t >1 ants. .
L 4 Scra? concic.n tion :V ild 1. cicca to cultire; the ente::nal surfaces of stajnless type alleys with a suital;1y protcctive material to prezent dircct contni. nation of the surfcce. The spoi.ic ccatirq to ba nao3 is nat pre:mnt clear. Po :J/cr, a suitabi s - r citeri:.1 ..t.uld Irmj& a g>mt rRasure of prctcetion j agairrit crachirg frm the cW:sile r."r#ac~ .
- 5. FL9d $.;JC 1: -
- ~.c 'cc s's:U 1- cse u l .1 : c' :Pir " qi~ e high nu _ ; me.mc.; t:ere/ coa .uve b;ea car;.m to cauce extensive FCC (Oystcc Creek) .
6.
Surface inopcetion chculd not. rely alone on penetrant testing since existira cracks are often minsci bf such a tcchnione. Such tests chaald be supplc anted at least by ultraronic techniques.
- 7. Careful atec. . ic a 4. a lci te ciw.<' to c:a birima srvcc.rcs of a --hd it piping rpt.- s :n ten coE aul i ^t cc:viitiens. Furthur, the later a0 lition c:? tt.r;'ci"ra ' 1mi.ures c;;h as seit ic restraints thculd Le acco',mn. cl by an ay copria c' cly ccmide c'? strt m analysis.
R. Pridicch;.- ~'- ~
c n chc.:'.2 bc adc to c'.;c:: fc,r contami:.:.nta cuch as chierina, trcmine, f]uorine, iodine, sulfur, lead, arac:.ic, ccrper. a .:rcury, an.i cad:aitra. Such chceks v.ould bc :rade unirc dilute acid s' abs '.>hich cro eJbsecucntly cralyzcl for th;Le elcacnts. Lccations for such arnlyses should considcr equially those m cas 'iciere drips might collect. Also points of high stress (applicd plus residual) in critical areas should be checked.
9.
Methods sought. for rcducing high residttal stresses should be rcre extensively Procedures of fabrication for large piping systcms should be carefully revic.eed to ro-luce residual stresses.
I hope the ahoye meets your needs. If you inve arrf questions, please contact me.
- &. cr ly.ycurs,
/ -
1
's -
w R. W. Sta > le w[h -
RWS:lah Consultant cc: Richard Infy 4
tan! I: I-Cin ial Co.cno%n 1.ie Jts .ru1 l'ap for su N meh C..'d;; : cent.ps) i Q b IkQnatkna y
or }
type E:n Si P S Nur. A r C W s. E s. 5f n. E s.
Ca Ni 0:1.ct l.lmirnh.
- 1. L!n.nhic ( h r#.a.n .w. !s 403 0.15 tin. 1.00 0.50 0.0-t o 0.030 11.50-1100 410 0.15 ?dn. 1 00 1.00 OW0 0.0 L 11.5&13.f 0 414 0.15 hin. 1.00 1.00 0.040 u.02 J l l.50-l M 0 1.25 2.50 416 0.15 h n. 1.25 1.00 0.05 0.15 Siin. 12 00 14.00 416 Sc 0.15 hin. 1.25 1.00 51o:0.60 Siu.
0.05 0.0G 12.00 14.00 420 0.w 015 1.00 Se:0.15 !.!ia.
1.09 0.0:0 0.030 12.0414.00 431 0.2011u. 1.00 1.00 0.0 ;0 0.030 440A 15.00 17.00 1.25 2.50 0.00 0.75 1.00 1.00 0.0 :0 0 010 16.00-1".o] Eto:0.75 ?.l.it 4403 0.'i51 M 1.00 1.00 0.0;0 o.m o 16.001100 110:0.75 .' ! :t 410C 0% 1. .'o I rn 1.00 0.0 :a C.c m IUn p :.0 .h 0.75 :i s 501 0.cr D.10 1M 1.0a 0 01'] t.. ') 4.00 a >!o:0 4 0 G 502 0.10 T!n. 1.00 1.00 0.00 0.0: 0 4.006.00 Afo:0.40-0.65
- 11. I craitic Chromium Stet b 405 0.08 Tfn. 1.00 1.00 0.040 0.030 11.50-14.50 At:0.10 0.30 430 0.12 :4n. 1.00 1.00 0.040 0.030 14.00-10.00 430!' O.12 mt 1.25 1.00 0 06 0.15 . Min. 14.00 13.00 h!o:0.60 5f n.
410F Sc 0.1 : Sin. 1.25 1.00 0.06 0. ~. 14.001 M S::0.15 .%.
416 0.20 Lt 1.50 1.00 0.040 0.030 23.0327 c0
=- N:0.25 ?!:x.
I!!. Aum nisb Ch:c.mim.W.! Steds 201 0.15 .Mn. 5.507.50 1.00 0.050 0.030 16.00 12 10 202 0.15 :4n. 3.50-5.'0 N.O.25 M u.
7.5& lE c0 1.00 0.000 0.019 201 17.00 19.00 4.00 6.C3 N:0.25 ):n.
- 0. I '. '.S 2D !.00 0.0 ;5 C .1.' a 4 T. U,- i :. .
E.:4 2...
304 0.15:1n. 2.00 1.00 0.045 0.020 17.00 19.00 302B 0.15 tn. 2.00 8.00-10.00 2033.00 0.045 0.030 17.00 19.00 8.0010.C 0 303 0.15 Lt 2.00 1.00 0.20 0.15 Min. 17.00 19 00 303Se 0.15 .'.i n. 2.00 8.0010.00 5fo:0.60 Sin.
1.00 0.20 0.05 17.00-19.00 301 0.0S Mn. 8.00-10.00 S :0.15 Min.
2.00 1.00 0.045 0 03a 304L 18.0} 20.00 8.00 12.00 0.03 Mn. 2.00 1.00 0.045 0.030 305 18.0420.00 8.00 12.00 0.12 Mn. 2.00 1.00 0.045 308 0.030 17.00 19.03 10.00513.00 0.0S M:x. 2.00 0.045 1.0Q 0.030 19.00-21.00 10.00 12.00 309 .20 Mn. 2.00 1.00 .045 .030 22.00-24.00 309S 12.00-15.00
.0S Mn. 2.00 1.00 .045 .030 310 22.00-24.00 12.00 15.00
.25 Mav. 2.00 1.50 .045 310s .030 24.00-26.00 19.00-22.00
.08 Mn. 2.0Q 1.50 .045 .030
- 314 24.00-26.00 19.00-22.00
.25 Mn. 2.00 1.50 3.00 .045 .030 316 23.00 26.00 19.0422.00 Mo:2.00 3.00
.03 Mn. 2.00 1.00 .045 .030 316L 16.00 1S.00 10.00-14.00 Mo:2.00 3.00
.03 Mn. 2.00 1.00 .045 .030 317 16.00-18.00 10.00 14.00 Mo:3.00-4.00
.03 Mn. 2.00 1.00 .045 .030 321 18.03 20.00 11.00-15.00 Ti:5 x C. Min.
.03 m s. 2.00 1.00 .045 .030 347 17.00 19.00 9.00 12.00 Cb-Ta:10 x C, Min.
.0S Mn. 2.00 1.00 .045 .030 348 17.00-19.00 9.00-13.00 Cb-Ta:10 x C, Min.,
.08 Mu. 2.00 1.00 .045 .030 17.00-19.00 9.00-13.00 Ta : 0.10 .'.f u.,
s Co:0.20 Mn.
. n. -: -
w -
l A. ,8 1
fk N-k
~
- 4 1 A!.l.t; I (mnfJ.) ~
ILd;na rian or
- 1ype Mn Si l' S t;n u t..r C E s. E x. E s. M n. Cr Ni Orlwr ! tu.i:nts
!V.11ccti in tna fin l'.ilw; mi .le s *it cis Pil!5 7 Mo .07 E s. .70 .40 15.00 7.00 1.15 A1, 2.25Mo 17 4 P1I .0 t Es. 40 .50 16.50 4.25 .25Cb, 34 Cu l 17 7 Pil .07 Mn. .70 .40 '
17.00 7.00 1.15 Al AM-35 0 .lD Mn. .75 .35 16.50 4.25 2.75 M o, 0.10N AM 355 .13 Mn. .65 .35 15.50 4.25 2.75 M o, 0.12 N V. 0:he s ini v:x I 600 .0 i Mn. .20 .20 .007 15.3 76.0 7.201 e 625 .0$ Mn. .15 .30 .007 22.0 61.0 31'c, 4Cb, 9 M o 718 .01 Mn. .20 .20 .007 19.0 $ 2.5 18.01'c 60Al,
.80Ti, 5.2Cb, 3M o X750 .04 Max. .70 .30 .007 15.0 73.0 6.751 c, .80Al.
2.50'l i, 0.S5 Cb Incoloy 80n .04 M n. .75 .35 .007 20.5 32.0 46.0Fe 30Cu 60; .06. h . .9 .007 29 43.7 24.5 0Fe. :Tu H25 .03 Ma. .65 .35 .007 2 t.5 41.8 30Fe,1.E ' .
0.15Al,O E :i.
3.0Mo flimoni.:
75 .10 Mn. .45 .45 .007 20.5 77.6 0.50Fe 20At. 351i Tencion .08 Mn. 14.70 .52 .025 .005 18.0 .13Mo, .l lCu,40N Cro tuy 16 1 .03 Mu. 16.75 1.09 1.51Mo, .90Cu Carpenter 20 .07 .7 20.0 29 2.00Mo, 3.00Cu 7 Mo(') .20 1.0 23-28 2.55 12Mo CD4MCu .04 1.0 25-27 4.7-6.0 1.75-2.25 M o, 2.75-3.25 Cu WCarpenter 7 Mo isT> pc 329.
Of special interest :ue the single p!use a Fe (ferritic) and This equation is valid for the fo!!owing r.mpe of comp +
7-Ni (austenitic) reg' ions and the two phase a 7 region.1he sitions:
7 - a transformation is very slu;gi>h with the result that Element Range of Composition (9) the nominally two phase ta + 7) ai:oys are generally smgle phase unless the alloy is defonned or unless certain gamma .C 0.03 - 0.20 stabilizing impurity elements (su,h as N, C) are absent. hin 0.4 - 4.0 Carbon, nitrogen, manganese, cobalt, nickel, and copper Si 'O.30- 0.50 contribute to the stability of austenite; chromium. Or '
14.0 -25 tungsten, tantalum, mo ybdenum, columtium, silicon, Ni 7.5 -21 titanium, unadium, and aluminum stabilize the ferrite. The hio' O.1 -3 -
amount of nickel necessary to maintam a stable austenitie structure with respect to the presence of other ferrite or austenite stabilizers has been quantitied in an emption by Nitrogen is a ver; potent stabilii.ing element. It lowers Post and liberly as fol!ous: the Fe-N cuteeteid to 590 C at 2.35 wei ht g pereeni compared with 723 C and 0.80 weight percent fer
, (Cr + 1.5 51o - 20)2 h!n carbon. The effect of nickel on stabilizing austenite h
- 35 C + 15 12 2 shown in l'igures 6 and 7. This elemert lowers the
.