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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20207E0051999-03-0202 March 1999 Transcript of 990302 Public Meeting with Commonwealth Edison in Rockville,Md.Pp 1-104.Supporting Documentation Encl ML20236H9381998-06-30030 June 1998 Transcript of 980630 Meeting W/Commonwealth Edison in Rockville,Md.Pp 1-123.Supporting Documentation Encl ML20198P3001997-11-0404 November 1997 Transcript of 971104 Public Meeting W/Ceco in Rockville,Md Re Measures Established by Ceco to Track Plant Performance & to Gain Understanding of CAs Put Into Place to Improve Safety.Pp 1-105.W/Certificate & Viewgraphs ML20149M2951996-11-29029 November 1996 Exemption from Requirements of 10CFR50.60 Re Safety Margins Recommended in ASME Boiler & Pressure Vessel Code Case N-514 TXX-9522, Comment Opposing Proposed GL on Testing of safety-related Logic Circuits.Believes That Complete Technical Review of All Surveillance Procedures Would Be Expensive & Unnecessary Expenditure of Licensee Resources1995-08-26026 August 1995 Comment Opposing Proposed GL on Testing of safety-related Logic Circuits.Believes That Complete Technical Review of All Surveillance Procedures Would Be Expensive & Unnecessary Expenditure of Licensee Resources ML20059C2351993-12-17017 December 1993 Comment Supporting Petition for Rulemaking PRM-21-2 Re Commercial Grade Item Dedication ML20044A8111990-06-27027 June 1990 Comment Opposing Closure of Lpdr of Rockford Public Library ML20245J0191989-04-14014 April 1989 Comment Re Proposed Rule 10CFR50 Re Ensuring Effectiveness of Maint Programs for Nuclear Power Plants ML20214X1871987-06-11011 June 1987 Order Imposing Civil Monetary Penalty in Amount of $25,000 Based on Four Severity Level III Violations Noted During 860721-0808 Insp ML20205Q1711987-04-0202 April 1987 Order Imposing Civil Monetary Penalty in Amount of $25,000. App Re Evaluations & Conclusions Encl IR 05000812/20100311987-02-26026 February 1987 Order Imposing Civil Monetary Penalty in Amount of $100,000 Based on Violations Noted During Insps on 850812-1031 ML20210T7321987-02-11011 February 1987 Unexecuted Amend 6 to Indemnity Agreement B-97 Substituting Item 3 of Attachment to Indemnity Agreement in Entirety W/ Listed License Numbers,Effective 870130 ML20209J3251987-01-30030 January 1987 Transcript of 870130 Commission Discussion/Possible Vote on Full Power OL for Facility.Pp 1-72.Supporting Viewgraphs Encl ML20213G4381986-10-24024 October 1986 Unexecuted Amend 5 to Indemnity Agreement B-97,substituting Item 3 of Attachment to Agreement in Entirety W/Listed License Numbers,Effective on 861106 ML20211B0841986-08-0505 August 1986 Transcript of 860805 Meeting Between Region Iii,Computer Interference Elimination & Util in Redmond,Wa Re Plant as-built Drawing Review.Pp 1-200 IR 05000506/20070221986-05-0202 May 1986 Order Imposing Civil Monetary Penalty in Amount of $25,000 for Violations Noted During Insp on 850506-0722.Violations Noted:Failure to Establish Radiological Safety Procedures & to Adequately Train Personnel ML20138C7301985-12-0909 December 1985 Order Imposing Civil Penalty in Amount of $25,000 Per 850606 Notice of Violation & Proposed Imposition of Civil Penalty.Licensee May Request Hearing within 30 Days of Date of Order ML20205E8741985-10-28028 October 1985 Exemption from GDC 4 of 10CFR50,App a Requirement to Install Protective Devices Associated W/Postulated Pipe Breaks Primary Coolant Sys.Topical Rept Evaluation Encl ML20102A2981985-01-0707 January 1985 Petition Requesting Aslab Grant Intervenor Appeal & Order Further Hearings on Safety of Plant ML20099L2581984-11-27027 November 1984 Notice of Withdrawal of Appearance in Proceeding.Certificate of Svc Encl ML20099G5381984-11-23023 November 1984 Supplemental Appeal Brief in Response to Intervenor 841106 Supplemental Brief on Appeal & in Support of ASLB 841016 Supplemental Initial Decision Authorizing Issuance of Ol. Certificate of Svc Encl ML20100K0411984-11-22022 November 1984 Submits Concerns Re Safety of Local Residents in Event of Accident & Excessively High Cost of Projected Operation of Facility ML20107H7841984-11-0606 November 1984 Supplemental Brief on Appeal of ASLB 841016 Supplemental Initial Decision Granting Authority for Issuance of Ol. Decision Should Be Reversed.Certificate of Svc Encl ML20140E4081984-10-31031 October 1984 Executed Amend 1 to Indemnity Agreement B-97,deleting Items 2A & 3 in Entirety ML20098G8841984-10-0202 October 1984 Joint Statement of RW Manz & W Faires Re Findings 3-11 Through 3-17 of NRC 830930 Integrated Design Insp Rept. Certificate of Svc Encl ML20098G8681984-10-0202 October 1984 Answer to Intervenor Motion to Reopen Record Re Bechtel Independent Design Review.Motion Should Be Denied ML20098G8901984-10-0202 October 1984 Joint Statement of Kj Green & RW Hooks Re Integrated Design Insp ML20098G8911984-10-0202 October 1984 Joint Statement of Cw Dick & EM Hughes Re Independent Design Insp ML20098G8821984-10-0101 October 1984 Affidavit of Kj Green Re Integrated Design Insp Concerning Mechanical Engineering Work ML20098G8741984-10-0101 October 1984 Affidavit of Br Shelton Re Integrated Design Insp ML20098G8881984-09-29029 September 1984 Affidavit of RW Hooks Re Integrated Design Insp Concerning Structural Design ML20098G8831984-09-28028 September 1984 Affidavit of W Faires Re Findings 3-15 & 3-16 of NRC 830930 Integrated Design Insp Rept ML20098G8811984-09-28028 September 1984 Affidavit of Cw Dick Re Independent Design Review ML20098G8791984-09-28028 September 1984 Affidavit of RP Tuetken Re Readiness for Fuel Loading ML20098G8781984-09-28028 September 1984 Affidavit of RW Manz Concerning Findings 3-11 Through 3-14 & 3-17 of NRC 830930 Integrated Design Insp Re Westinghouse ML20098G8871984-09-28028 September 1984 Affidavit of EM Hughes Re Idvp ML20098G8851984-09-27027 September 1984 Affidavit of Rl Heumann Re Costs of Delay in Startup & Operation of Unit 1 ML20098E2371984-09-24024 September 1984 Reply to Intervenor 840918 Proposed Supplemental Initial Decision.Certificate of Svc Encl ML20097E7221984-09-13013 September 1984 Agreed Motion for Time Extension Until 841101 to File Petition for Hearing Re Emergency Planning Commitment W ML20097C5311984-09-12012 September 1984 Motion to Reopen Record to Include Plant Design as Issue. Supporting Documentation & Certificate of Svc Encl ML20097B7791984-09-10010 September 1984 Proposed Supplemental Initial Decision Re Reinsp Program. Certificate of Svc Encl ML20096A6391984-08-30030 August 1984 Rebuttal Testimony of RW Hooks Re Validity of Info in Attachment 7 to Stokes Testimony Concerning Design Assumption for Plant.Stokes Info Inapplicable to Plant. Related Correspondence ML20096A6191984-08-30030 August 1984 Rebuttal Testimony of B Erler Re Stokes Allegations Concerning Evaluations of Discrepancies in Calculated Actual Stress Performed by Sargent & Lundy.Related Correspondence ML20096A6261984-08-30030 August 1984 Summary of Rebuttal Testimony & Testimony of ML Somsag, Eb Branch,D Demoss,Mr Frankel,Bf Maurer & Jk Buchanan Re Plant QC Inspector Reinsp Program & C Stokes Allegations Re Welds.Related Correspondence ML20096A6441984-08-28028 August 1984 Notice of Withdrawal of Appearance in Proceeding.Related Correspondence ML20112D5271984-08-24024 August 1984 Applicant Exhibit A-R-4,consisting of Feb 1984 Rept on Bryon QC Inspector Reinsp Program ML20112D5031984-08-24024 August 1984 Applicant Exhibit A-R-5,consisting of June 1984 Suppl to Rept on Bryon QC Inspector Reinsp Program ML20112D7441984-08-23023 August 1984 Intervenor Exhibit I-R-1,consisting of Undated List of Teutken Safety Category Insp Types ML20112D7511984-08-21021 August 1984 Staff Exhibit S-R-1,consisting of 840813 Instruction for Walkdown of Cable Tray Hanger Connection Welds ML20112D4641984-08-21021 August 1984 Intervenor Exhibit I-R-11,consisting of Undated Chronological Date Listing of Util Responses to Interrogatory 12.VA Judson to Mi Miller Re Interrogatory 12 & Supplemental Responses Encl 1999-03-02
[Table view] Category:TRANSCRIPTS
MONTHYEARML20207E0051999-03-0202 March 1999 Transcript of 990302 Public Meeting with Commonwealth Edison in Rockville,Md.Pp 1-104.Supporting Documentation Encl ML20236H9381998-06-30030 June 1998 Transcript of 980630 Meeting W/Commonwealth Edison in Rockville,Md.Pp 1-123.Supporting Documentation Encl ML20198P3001997-11-0404 November 1997 Transcript of 971104 Public Meeting W/Ceco in Rockville,Md Re Measures Established by Ceco to Track Plant Performance & to Gain Understanding of CAs Put Into Place to Improve Safety.Pp 1-105.W/Certificate & Viewgraphs ML20209J3251987-01-30030 January 1987 Transcript of 870130 Commission Discussion/Possible Vote on Full Power OL for Facility.Pp 1-72.Supporting Viewgraphs Encl ML20211B0841986-08-0505 August 1986 Transcript of 860805 Meeting Between Region Iii,Computer Interference Elimination & Util in Redmond,Wa Re Plant as-built Drawing Review.Pp 1-200 ML20096A6261984-08-30030 August 1984 Summary of Rebuttal Testimony & Testimony of ML Somsag, Eb Branch,D Demoss,Mr Frankel,Bf Maurer & Jk Buchanan Re Plant QC Inspector Reinsp Program & C Stokes Allegations Re Welds.Related Correspondence ML20096A6191984-08-30030 August 1984 Rebuttal Testimony of B Erler Re Stokes Allegations Concerning Evaluations of Discrepancies in Calculated Actual Stress Performed by Sargent & Lundy.Related Correspondence ML20096A6391984-08-30030 August 1984 Rebuttal Testimony of RW Hooks Re Validity of Info in Attachment 7 to Stokes Testimony Concerning Design Assumption for Plant.Stokes Info Inapplicable to Plant. Related Correspondence ML20094P7721984-08-17017 August 1984 Summary of Testimony & Direct Testimony of CC Stokes on Reinsp Program.Related Correspondence ML20094R1021984-08-17017 August 1984 Transcript of CC Stokes 840817 Deposition in Chicago,Il. Pp 1-173.Vol Ii.Related Correspondence ML20094P5991984-08-16016 August 1984 Direct Testimony of CC Stokes Re Engineering Evaluations Performed & Use of Engineering Judgement by Sargent & Lundy. Suggests Need for Independent Engineering Analysis of Safety Significance of Reinsp Program.Related Correspondence ML20094P6311984-08-14014 August 1984 Summary of Testimony & Testimony of Ds Kochhar on Contention 1 Re Reinsp Program.Certificate of Svc Encl.Related Correspondence ML20094P6831984-08-13013 August 1984 Summary of Testimony & Testimony of Wh Bleuel on Contention 1 Re Reinsp Program.Resume Encl.Related Correspondence ML20094P6951984-08-13013 August 1984 Summary of Testimony & Testimony of EP Erickson on Contention 1 Re Reinsp program-inspector Qualification & Work Quality.Resume & Certificate of Svc Encl.Related Correspondence ML20093L4881984-07-30030 July 1984 Summary of Testimony & Testimony of Eb Branch Re Contention 1 (Reinsp Program,Work Quality).Related Correspondence ML20093L1811984-07-30030 July 1984 Summary of Testimony & Testimony of KT Kostal on Contention 1 Re Capacity of Sys Control Corp Supplied Components to Carry Design Loads.Related Correspondence ML20093L2721984-07-30030 July 1984 Summary of Testimony & Testimony of Ak Singh on Contention 1 Re Evaluations of Discrepancies in Cable Tray Hanger Connections,Solid Bottom Tray Welds & Ladder Tray Weld Connections.Related Correspondence ML20093L2051984-07-30030 July 1984 Summary of Testimony & Testimony of Ld Johnson on Contention 1 Re Adequacy of Sys Control Corp Supplied Main Control Boards.Related Correspondence ML20090E5521984-07-17017 July 1984 Testimony of Eb Branch Re Job Responsibilities,Educ Background & Work Experience.Related Correspondence ML20090A7981984-07-0909 July 1984 Testimony of Gf Marcus Re Pittsburgh Testing Lab Source Insp of Equipment & Components Supplied by Sys Control Corp ML20090A8121984-07-0909 July 1984 Testimony of Bf Maurer Re Analysis of Structural Adequacy of Main Control Panels Designed & Fabricated by Sys Control Corp ML20092P7921984-07-0202 July 1984 Summary of Testimony & Testimony of ML Somsag Re QA Inspector Reinsp Program for Hunter Corp.Related Correspondence ML20092P7891984-07-0202 July 1984 Summary of Testimony & Testimony of Rv Laney on Contention 1 Re Work Quality.Related Correspondence ML20092P7951984-07-0202 July 1984 Summary of Testimony & Testimony of Ak Singh on Contention 1 Re Reinsp Program,Work Quality.Related Correspondence ML20092P7941984-07-0202 July 1984 Summary of Testimony & Testimony of LO Delgeorge on Contention 1 Re Reinsp Program,Inspector Qualification & Work Quality.Related Correspondence ML20092P5541984-07-0202 July 1984 Summary of Testimony & Testimony of Dl Leone on Contention 1 Re Reinsp Program for Work Quality ML20092P5551984-07-0202 July 1984 Summary of Testimony & Testimony of R French on Contention 1 Re Reinsp Program ML20092P7781984-07-0202 July 1984 Summary of Testimony & Testimony of Wj Shewski on Contention 1 Re Reinsp Program,Inspector Qualification.Related Correspondence ML20092P7811984-07-0202 July 1984 Summary of Testimony & Testimony of Jm Mclaughlin on Contention 1 Re Reinsp Program,Work Quality.Related Correspondence ML20092P7871984-07-0202 July 1984 Summary of Direct Testimony & Testimony of RP Tuetken Re Reinsp Program.Related Correspondence ML20092P7851984-07-0202 July 1984 Summary of Testimony & Testimony of Wb Behnke on Contention 1 Re Overview of Quality Program,Work Quality. Related Correspondence ML20092N4971984-06-29029 June 1984 Testimony of Bg Treece on Issues 5 & 6 Re Cable Overtensioning,As Limited by ASLB 840608 Order.Related Correspondence ML20092N4911984-06-29029 June 1984 Summary of Direct Testimony of Jo Binder on Issues 5 & 6 Re Cable Overtensioning,As Limited by ASLB 840608 Order.Related Correspondence ML20092K7691984-06-26026 June 1984 Summary of Testimony of J Hansel on Contention 1 Re Reinsp Program.Prof Qualifications Encl.Related Correspondence ML20205H8901983-08-10010 August 1983 Public Version of Transcript of 830810 in Camera,Ex Parte Hearing in Rockford,Il.Pp 7,585-7,610 ML20205H8941983-08-10010 August 1983 Public Version of Transcript of 830810 in Camera,Ex Parte Hearing W/Ofc of Investigations in Rockford,Il.Pp 7,611.1- 7,611.71 ML20205H8841983-08-0909 August 1983 Public Version of Transcript of 830809 in Camera,Ex Parte Hearing in Rockford,Il.Pp 7,304-7,405 ML20080B3051983-08-0303 August 1983 Testimony of RP Tuetken Re Util Reinsp Program of Work Performed by Contractor Insp Personnel Prior to NRC Region III Mar,Apr & May 1982 Insps.Appropriate Steps Taken to Remedy Problems ML20080B3091983-08-0303 August 1983 Testimony of Aw Koca Re General Nature of Hatfield Inspector Training & Certification Program.Certification of J Hughes Described ML20080B2951983-08-0303 August 1983 Testimony of Ma Stanish Re Recertification of Qa/Qc Inspectors Subsequent to NRC Region III Mar,Apr & May 1982 Special Team Insps.Reinsp Program Implemented to Review Work Performed by Inspectors Before NRC 1982 Insp ML20023C7151983-05-12012 May 1983 Testimony of P Holmbeck Re Investigation Into Adequacy of Emergency Plans Re Emergency Planning Contentions.Util Made No Attempt to Study Protective Value of Sheltering Populations Around Plant ML20204F5721983-04-26026 April 1983 Transcript of 830426 Hearing in Rockford,Il.Pp 5,964-6,156 ML20069M4791983-04-25025 April 1983 Handwritten Testimony of J Hughes Re Qa/Qc at Facility ML20069K5691983-04-21021 April 1983 Testimony of Ld Butterfield Re Steam Generator Tube Integrity.Proposed Steam Generator Mods Would Minimize Tube Wear Due to Flow Induced Vibration.Related Correspondence ML20069K5631983-04-21021 April 1983 Revised Testimony of Tf Timmons Re Steam Generator Tube Integrity (Flow Induced Vibration Phenomenon).No Significant Tube Wear Will Be Experienced in Steam Generators Due to Flow Induced Vibration.Related Correspondence ML20073J6691983-04-18018 April 1983 Testimony of Jl Murphy on Rockford League of Women Voters & Dekalb Area Alliance for Responsible Energy/Sinnissippi Alliance for Environ Consolidated Emergency Planning Contentions 3 & 13.Related Correspondence ML20073K4461983-04-18018 April 1983 Rebuttal Testimony of Levine Re Rockford League of Women Voters Contentions 8 & 62 & Dekalb Area Alliance for Responsible Energy/Sinnissippi Alliance for Environ Contention 2a on Public Risk.Related Correspondence ML20073G4241983-04-11011 April 1983 Testimony of Ee Jones Re State of Il Emergency Svc & Disaster Agency Responsibilities Concerning Emergency Planning for Nuclear Facilities & Intervenor Amended Emergency Planning Contention ML20073G4051983-04-11011 April 1983 Testimony of Jc Golden Re Amended Emergency Planning Contention ML20073G4121983-04-11011 April 1983 Testimony of Dl Smith Re Resources Available for Transport & Treatment of Contaminated Injured Persons.Resume Encl 1999-03-02
[Table view] Category:DEPOSITIONS
MONTHYEARML20207E0051999-03-0202 March 1999 Transcript of 990302 Public Meeting with Commonwealth Edison in Rockville,Md.Pp 1-104.Supporting Documentation Encl ML20236H9381998-06-30030 June 1998 Transcript of 980630 Meeting W/Commonwealth Edison in Rockville,Md.Pp 1-123.Supporting Documentation Encl ML20198P3001997-11-0404 November 1997 Transcript of 971104 Public Meeting W/Ceco in Rockville,Md Re Measures Established by Ceco to Track Plant Performance & to Gain Understanding of CAs Put Into Place to Improve Safety.Pp 1-105.W/Certificate & Viewgraphs ML20209J3251987-01-30030 January 1987 Transcript of 870130 Commission Discussion/Possible Vote on Full Power OL for Facility.Pp 1-72.Supporting Viewgraphs Encl ML20211B0841986-08-0505 August 1986 Transcript of 860805 Meeting Between Region Iii,Computer Interference Elimination & Util in Redmond,Wa Re Plant as-built Drawing Review.Pp 1-200 ML20096A6261984-08-30030 August 1984 Summary of Rebuttal Testimony & Testimony of ML Somsag, Eb Branch,D Demoss,Mr Frankel,Bf Maurer & Jk Buchanan Re Plant QC Inspector Reinsp Program & C Stokes Allegations Re Welds.Related Correspondence ML20096A6191984-08-30030 August 1984 Rebuttal Testimony of B Erler Re Stokes Allegations Concerning Evaluations of Discrepancies in Calculated Actual Stress Performed by Sargent & Lundy.Related Correspondence ML20096A6391984-08-30030 August 1984 Rebuttal Testimony of RW Hooks Re Validity of Info in Attachment 7 to Stokes Testimony Concerning Design Assumption for Plant.Stokes Info Inapplicable to Plant. Related Correspondence ML20094P7721984-08-17017 August 1984 Summary of Testimony & Direct Testimony of CC Stokes on Reinsp Program.Related Correspondence ML20094R1021984-08-17017 August 1984 Transcript of CC Stokes 840817 Deposition in Chicago,Il. Pp 1-173.Vol Ii.Related Correspondence ML20094P5991984-08-16016 August 1984 Direct Testimony of CC Stokes Re Engineering Evaluations Performed & Use of Engineering Judgement by Sargent & Lundy. Suggests Need for Independent Engineering Analysis of Safety Significance of Reinsp Program.Related Correspondence ML20094P6311984-08-14014 August 1984 Summary of Testimony & Testimony of Ds Kochhar on Contention 1 Re Reinsp Program.Certificate of Svc Encl.Related Correspondence ML20094P6831984-08-13013 August 1984 Summary of Testimony & Testimony of Wh Bleuel on Contention 1 Re Reinsp Program.Resume Encl.Related Correspondence ML20094P6951984-08-13013 August 1984 Summary of Testimony & Testimony of EP Erickson on Contention 1 Re Reinsp program-inspector Qualification & Work Quality.Resume & Certificate of Svc Encl.Related Correspondence ML20093L4881984-07-30030 July 1984 Summary of Testimony & Testimony of Eb Branch Re Contention 1 (Reinsp Program,Work Quality).Related Correspondence ML20093L1811984-07-30030 July 1984 Summary of Testimony & Testimony of KT Kostal on Contention 1 Re Capacity of Sys Control Corp Supplied Components to Carry Design Loads.Related Correspondence ML20093L2721984-07-30030 July 1984 Summary of Testimony & Testimony of Ak Singh on Contention 1 Re Evaluations of Discrepancies in Cable Tray Hanger Connections,Solid Bottom Tray Welds & Ladder Tray Weld Connections.Related Correspondence ML20093L2051984-07-30030 July 1984 Summary of Testimony & Testimony of Ld Johnson on Contention 1 Re Adequacy of Sys Control Corp Supplied Main Control Boards.Related Correspondence ML20090E5521984-07-17017 July 1984 Testimony of Eb Branch Re Job Responsibilities,Educ Background & Work Experience.Related Correspondence ML20090A7981984-07-0909 July 1984 Testimony of Gf Marcus Re Pittsburgh Testing Lab Source Insp of Equipment & Components Supplied by Sys Control Corp ML20090A8121984-07-0909 July 1984 Testimony of Bf Maurer Re Analysis of Structural Adequacy of Main Control Panels Designed & Fabricated by Sys Control Corp ML20092P7921984-07-0202 July 1984 Summary of Testimony & Testimony of ML Somsag Re QA Inspector Reinsp Program for Hunter Corp.Related Correspondence ML20092P7891984-07-0202 July 1984 Summary of Testimony & Testimony of Rv Laney on Contention 1 Re Work Quality.Related Correspondence ML20092P7951984-07-0202 July 1984 Summary of Testimony & Testimony of Ak Singh on Contention 1 Re Reinsp Program,Work Quality.Related Correspondence ML20092P7941984-07-0202 July 1984 Summary of Testimony & Testimony of LO Delgeorge on Contention 1 Re Reinsp Program,Inspector Qualification & Work Quality.Related Correspondence ML20092P5541984-07-0202 July 1984 Summary of Testimony & Testimony of Dl Leone on Contention 1 Re Reinsp Program for Work Quality ML20092P5551984-07-0202 July 1984 Summary of Testimony & Testimony of R French on Contention 1 Re Reinsp Program ML20092P7781984-07-0202 July 1984 Summary of Testimony & Testimony of Wj Shewski on Contention 1 Re Reinsp Program,Inspector Qualification.Related Correspondence ML20092P7811984-07-0202 July 1984 Summary of Testimony & Testimony of Jm Mclaughlin on Contention 1 Re Reinsp Program,Work Quality.Related Correspondence ML20092P7871984-07-0202 July 1984 Summary of Direct Testimony & Testimony of RP Tuetken Re Reinsp Program.Related Correspondence ML20092P7851984-07-0202 July 1984 Summary of Testimony & Testimony of Wb Behnke on Contention 1 Re Overview of Quality Program,Work Quality. Related Correspondence ML20092N4971984-06-29029 June 1984 Testimony of Bg Treece on Issues 5 & 6 Re Cable Overtensioning,As Limited by ASLB 840608 Order.Related Correspondence ML20092N4911984-06-29029 June 1984 Summary of Direct Testimony of Jo Binder on Issues 5 & 6 Re Cable Overtensioning,As Limited by ASLB 840608 Order.Related Correspondence ML20092K7691984-06-26026 June 1984 Summary of Testimony of J Hansel on Contention 1 Re Reinsp Program.Prof Qualifications Encl.Related Correspondence ML20205H8901983-08-10010 August 1983 Public Version of Transcript of 830810 in Camera,Ex Parte Hearing in Rockford,Il.Pp 7,585-7,610 ML20205H8941983-08-10010 August 1983 Public Version of Transcript of 830810 in Camera,Ex Parte Hearing W/Ofc of Investigations in Rockford,Il.Pp 7,611.1- 7,611.71 ML20205H8841983-08-0909 August 1983 Public Version of Transcript of 830809 in Camera,Ex Parte Hearing in Rockford,Il.Pp 7,304-7,405 ML20080B3051983-08-0303 August 1983 Testimony of RP Tuetken Re Util Reinsp Program of Work Performed by Contractor Insp Personnel Prior to NRC Region III Mar,Apr & May 1982 Insps.Appropriate Steps Taken to Remedy Problems ML20080B3091983-08-0303 August 1983 Testimony of Aw Koca Re General Nature of Hatfield Inspector Training & Certification Program.Certification of J Hughes Described ML20080B2951983-08-0303 August 1983 Testimony of Ma Stanish Re Recertification of Qa/Qc Inspectors Subsequent to NRC Region III Mar,Apr & May 1982 Special Team Insps.Reinsp Program Implemented to Review Work Performed by Inspectors Before NRC 1982 Insp ML20023C7151983-05-12012 May 1983 Testimony of P Holmbeck Re Investigation Into Adequacy of Emergency Plans Re Emergency Planning Contentions.Util Made No Attempt to Study Protective Value of Sheltering Populations Around Plant ML20204F5721983-04-26026 April 1983 Transcript of 830426 Hearing in Rockford,Il.Pp 5,964-6,156 ML20069M4791983-04-25025 April 1983 Handwritten Testimony of J Hughes Re Qa/Qc at Facility ML20069K5691983-04-21021 April 1983 Testimony of Ld Butterfield Re Steam Generator Tube Integrity.Proposed Steam Generator Mods Would Minimize Tube Wear Due to Flow Induced Vibration.Related Correspondence ML20069K5631983-04-21021 April 1983 Revised Testimony of Tf Timmons Re Steam Generator Tube Integrity (Flow Induced Vibration Phenomenon).No Significant Tube Wear Will Be Experienced in Steam Generators Due to Flow Induced Vibration.Related Correspondence ML20073J6691983-04-18018 April 1983 Testimony of Jl Murphy on Rockford League of Women Voters & Dekalb Area Alliance for Responsible Energy/Sinnissippi Alliance for Environ Consolidated Emergency Planning Contentions 3 & 13.Related Correspondence ML20073K4461983-04-18018 April 1983 Rebuttal Testimony of Levine Re Rockford League of Women Voters Contentions 8 & 62 & Dekalb Area Alliance for Responsible Energy/Sinnissippi Alliance for Environ Contention 2a on Public Risk.Related Correspondence ML20073G4241983-04-11011 April 1983 Testimony of Ee Jones Re State of Il Emergency Svc & Disaster Agency Responsibilities Concerning Emergency Planning for Nuclear Facilities & Intervenor Amended Emergency Planning Contention ML20073G4051983-04-11011 April 1983 Testimony of Jc Golden Re Amended Emergency Planning Contention ML20073G4121983-04-11011 April 1983 Testimony of Dl Smith Re Resources Available for Transport & Treatment of Contaminated Injured Persons.Resume Encl 1999-03-02
[Table view] Category:NARRATIVE TESTIMONY
MONTHYEARML20207E0051999-03-0202 March 1999 Transcript of 990302 Public Meeting with Commonwealth Edison in Rockville,Md.Pp 1-104.Supporting Documentation Encl ML20236H9381998-06-30030 June 1998 Transcript of 980630 Meeting W/Commonwealth Edison in Rockville,Md.Pp 1-123.Supporting Documentation Encl ML20198P3001997-11-0404 November 1997 Transcript of 971104 Public Meeting W/Ceco in Rockville,Md Re Measures Established by Ceco to Track Plant Performance & to Gain Understanding of CAs Put Into Place to Improve Safety.Pp 1-105.W/Certificate & Viewgraphs ML20209J3251987-01-30030 January 1987 Transcript of 870130 Commission Discussion/Possible Vote on Full Power OL for Facility.Pp 1-72.Supporting Viewgraphs Encl ML20211B0841986-08-0505 August 1986 Transcript of 860805 Meeting Between Region Iii,Computer Interference Elimination & Util in Redmond,Wa Re Plant as-built Drawing Review.Pp 1-200 ML20096A6261984-08-30030 August 1984 Summary of Rebuttal Testimony & Testimony of ML Somsag, Eb Branch,D Demoss,Mr Frankel,Bf Maurer & Jk Buchanan Re Plant QC Inspector Reinsp Program & C Stokes Allegations Re Welds.Related Correspondence ML20096A6191984-08-30030 August 1984 Rebuttal Testimony of B Erler Re Stokes Allegations Concerning Evaluations of Discrepancies in Calculated Actual Stress Performed by Sargent & Lundy.Related Correspondence ML20096A6391984-08-30030 August 1984 Rebuttal Testimony of RW Hooks Re Validity of Info in Attachment 7 to Stokes Testimony Concerning Design Assumption for Plant.Stokes Info Inapplicable to Plant. Related Correspondence ML20094P7721984-08-17017 August 1984 Summary of Testimony & Direct Testimony of CC Stokes on Reinsp Program.Related Correspondence ML20094R1021984-08-17017 August 1984 Transcript of CC Stokes 840817 Deposition in Chicago,Il. Pp 1-173.Vol Ii.Related Correspondence ML20094P5991984-08-16016 August 1984 Direct Testimony of CC Stokes Re Engineering Evaluations Performed & Use of Engineering Judgement by Sargent & Lundy. Suggests Need for Independent Engineering Analysis of Safety Significance of Reinsp Program.Related Correspondence ML20094P6311984-08-14014 August 1984 Summary of Testimony & Testimony of Ds Kochhar on Contention 1 Re Reinsp Program.Certificate of Svc Encl.Related Correspondence ML20094P6831984-08-13013 August 1984 Summary of Testimony & Testimony of Wh Bleuel on Contention 1 Re Reinsp Program.Resume Encl.Related Correspondence ML20094P6951984-08-13013 August 1984 Summary of Testimony & Testimony of EP Erickson on Contention 1 Re Reinsp program-inspector Qualification & Work Quality.Resume & Certificate of Svc Encl.Related Correspondence ML20093L4881984-07-30030 July 1984 Summary of Testimony & Testimony of Eb Branch Re Contention 1 (Reinsp Program,Work Quality).Related Correspondence ML20093L1811984-07-30030 July 1984 Summary of Testimony & Testimony of KT Kostal on Contention 1 Re Capacity of Sys Control Corp Supplied Components to Carry Design Loads.Related Correspondence ML20093L2721984-07-30030 July 1984 Summary of Testimony & Testimony of Ak Singh on Contention 1 Re Evaluations of Discrepancies in Cable Tray Hanger Connections,Solid Bottom Tray Welds & Ladder Tray Weld Connections.Related Correspondence ML20093L2051984-07-30030 July 1984 Summary of Testimony & Testimony of Ld Johnson on Contention 1 Re Adequacy of Sys Control Corp Supplied Main Control Boards.Related Correspondence ML20090E5521984-07-17017 July 1984 Testimony of Eb Branch Re Job Responsibilities,Educ Background & Work Experience.Related Correspondence ML20090A7981984-07-0909 July 1984 Testimony of Gf Marcus Re Pittsburgh Testing Lab Source Insp of Equipment & Components Supplied by Sys Control Corp ML20090A8121984-07-0909 July 1984 Testimony of Bf Maurer Re Analysis of Structural Adequacy of Main Control Panels Designed & Fabricated by Sys Control Corp ML20092P7921984-07-0202 July 1984 Summary of Testimony & Testimony of ML Somsag Re QA Inspector Reinsp Program for Hunter Corp.Related Correspondence ML20092P7891984-07-0202 July 1984 Summary of Testimony & Testimony of Rv Laney on Contention 1 Re Work Quality.Related Correspondence ML20092P7951984-07-0202 July 1984 Summary of Testimony & Testimony of Ak Singh on Contention 1 Re Reinsp Program,Work Quality.Related Correspondence ML20092P7941984-07-0202 July 1984 Summary of Testimony & Testimony of LO Delgeorge on Contention 1 Re Reinsp Program,Inspector Qualification & Work Quality.Related Correspondence ML20092P5541984-07-0202 July 1984 Summary of Testimony & Testimony of Dl Leone on Contention 1 Re Reinsp Program for Work Quality ML20092P5551984-07-0202 July 1984 Summary of Testimony & Testimony of R French on Contention 1 Re Reinsp Program ML20092P7781984-07-0202 July 1984 Summary of Testimony & Testimony of Wj Shewski on Contention 1 Re Reinsp Program,Inspector Qualification.Related Correspondence ML20092P7811984-07-0202 July 1984 Summary of Testimony & Testimony of Jm Mclaughlin on Contention 1 Re Reinsp Program,Work Quality.Related Correspondence ML20092P7871984-07-0202 July 1984 Summary of Direct Testimony & Testimony of RP Tuetken Re Reinsp Program.Related Correspondence ML20092P7851984-07-0202 July 1984 Summary of Testimony & Testimony of Wb Behnke on Contention 1 Re Overview of Quality Program,Work Quality. Related Correspondence ML20092N4971984-06-29029 June 1984 Testimony of Bg Treece on Issues 5 & 6 Re Cable Overtensioning,As Limited by ASLB 840608 Order.Related Correspondence ML20092N4911984-06-29029 June 1984 Summary of Direct Testimony of Jo Binder on Issues 5 & 6 Re Cable Overtensioning,As Limited by ASLB 840608 Order.Related Correspondence ML20092K7691984-06-26026 June 1984 Summary of Testimony of J Hansel on Contention 1 Re Reinsp Program.Prof Qualifications Encl.Related Correspondence ML20205H8901983-08-10010 August 1983 Public Version of Transcript of 830810 in Camera,Ex Parte Hearing in Rockford,Il.Pp 7,585-7,610 ML20205H8941983-08-10010 August 1983 Public Version of Transcript of 830810 in Camera,Ex Parte Hearing W/Ofc of Investigations in Rockford,Il.Pp 7,611.1- 7,611.71 ML20205H8841983-08-0909 August 1983 Public Version of Transcript of 830809 in Camera,Ex Parte Hearing in Rockford,Il.Pp 7,304-7,405 ML20080B3051983-08-0303 August 1983 Testimony of RP Tuetken Re Util Reinsp Program of Work Performed by Contractor Insp Personnel Prior to NRC Region III Mar,Apr & May 1982 Insps.Appropriate Steps Taken to Remedy Problems ML20080B3091983-08-0303 August 1983 Testimony of Aw Koca Re General Nature of Hatfield Inspector Training & Certification Program.Certification of J Hughes Described ML20080B2951983-08-0303 August 1983 Testimony of Ma Stanish Re Recertification of Qa/Qc Inspectors Subsequent to NRC Region III Mar,Apr & May 1982 Special Team Insps.Reinsp Program Implemented to Review Work Performed by Inspectors Before NRC 1982 Insp ML20023C7151983-05-12012 May 1983 Testimony of P Holmbeck Re Investigation Into Adequacy of Emergency Plans Re Emergency Planning Contentions.Util Made No Attempt to Study Protective Value of Sheltering Populations Around Plant ML20204F5721983-04-26026 April 1983 Transcript of 830426 Hearing in Rockford,Il.Pp 5,964-6,156 ML20069M4791983-04-25025 April 1983 Handwritten Testimony of J Hughes Re Qa/Qc at Facility ML20069K5691983-04-21021 April 1983 Testimony of Ld Butterfield Re Steam Generator Tube Integrity.Proposed Steam Generator Mods Would Minimize Tube Wear Due to Flow Induced Vibration.Related Correspondence ML20069K5631983-04-21021 April 1983 Revised Testimony of Tf Timmons Re Steam Generator Tube Integrity (Flow Induced Vibration Phenomenon).No Significant Tube Wear Will Be Experienced in Steam Generators Due to Flow Induced Vibration.Related Correspondence ML20073J6691983-04-18018 April 1983 Testimony of Jl Murphy on Rockford League of Women Voters & Dekalb Area Alliance for Responsible Energy/Sinnissippi Alliance for Environ Consolidated Emergency Planning Contentions 3 & 13.Related Correspondence ML20073K4461983-04-18018 April 1983 Rebuttal Testimony of Levine Re Rockford League of Women Voters Contentions 8 & 62 & Dekalb Area Alliance for Responsible Energy/Sinnissippi Alliance for Environ Contention 2a on Public Risk.Related Correspondence ML20073G4241983-04-11011 April 1983 Testimony of Ee Jones Re State of Il Emergency Svc & Disaster Agency Responsibilities Concerning Emergency Planning for Nuclear Facilities & Intervenor Amended Emergency Planning Contention ML20073G4051983-04-11011 April 1983 Testimony of Jc Golden Re Amended Emergency Planning Contention ML20073G4121983-04-11011 April 1983 Testimony of Dl Smith Re Resources Available for Transport & Treatment of Contaminated Injured Persons.Resume Encl 1999-03-02
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )
)
COMMONWEALTH EDISON COMPANY ) Docket No. 50-454-OLA
) 50-455-OLA (Byron Station, Units 1 and 2) )
TESTIMONY OF WILSON D. FLETCHER CONCERNING STEAM GENERATOR TUBE INTEGRITY
(.AN OVERVIEW OF THE SAFETY SIGNIFICANCE OF THE ISSUE)
Submitted on behalf of the Applicant, Commonwealth Edison Company in Response to DAARE/ SAFE
~
Contetion 9c and League Contention 22 February 25, 1983 i
(
B303010312 830225 PDR ADOCK 05000454 T PDR w , , - +y- m yc,,,- -
,,y _._y - - ,--m --,--,
, v UNITED STATES'OF AMERICA-NUCLEAR REGULATORY COMMISSION i BEFORE THE ATOMIC SAFETY AND LICENSING BOARD l
In the-Matter of )
)
COMMONWEALTH EDISON COMPANY ) l Docket No. 50-454-OLA_
) 50-455-OLA
, (Byron Station,-Units 1 and 2) )
SUMMARY
4 j ~
The testimony of Mr. Wilson D. Fletcher provides an overview of the safety significance of the steam generator tube integrity' issue. Mr. Fletcher is Manager of Westing-house's Division of Steam Generator Materials and Chemistry, ;
and for the past 12 years he has held various positions of responsibility at Westinghouse involving various aspects of steam generator design and operation with particular emphasis
, on tube degradation matters. This work experience together i
with his educational background provide Mr. Fletcher with impeccable credentials as an expert.
Mr. Fletcher con'cludes that tube rupture should not occur even under conditions of postulated loss-of-coolant accidents and main steam line accidents, and therefore that steam generator tube degradation is not a cause for a safety concern as-suggested by intervenors' contentions. This
- opinion is based upon'Mr. Fletcher's extensive personal knowledge and experience in the_ field and on the testimony of j other witnesses appearing on behalf of Commonwealth Edison Company. With respect to the other witnesses' testimony,.Mr.
Fletcher relies upon (i) the conservatism of the 40% tube l plugging criterion as detailed by Dr. Patel, (ii) the capa-
- bility of eddy current testing to detect tube degradation at j or above the tube plugging criterion as articulated by Mr.
F Malinowski, (iii) the success of AVT water chemistry to
< minimize' tube corrosion as discussed. by Dr. Wootten, (iv) the continual design evolution of Westinghouse steam generators that resulted in the Byron Station steam generators embodying the very best design features from the perspective of reducing tube degradation as described by Dr. Conway, and (v) the assurance, as demonstrated by Mr. Timmons, that the flow-induced vibration phenomenon is well-understood and that measures will be taken to render the matter of little concern.
Finally, Mr. Fletcher's also relies on the various commitments testified to by Mr. Blomgren as being adopted by Commonwealth
, Edison Company for implementation at the Byron Station.
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )
)
COMMONWEALTH EDISON COMPANY ) Docket No. 50-454-OLA
) 50-455-OLA (Byron Station, Units 1 and 2) )
TESTIMONY OF WILSON D. FLETCHER CONCERNING STEAM GENERATOR TUBE INTEGRITY (AN OVERVIEW OF THE SAFETY SIGNIFICANCE OF THE ISSUE) 0.1. State your name, address and occupation.
A.1. My name is Wilson Douglas Fletcher. I am Manager of Steam Generator Materials and Chemistry with the Westinghouse Electric Corporation, Forest Hills I
Site, Avenue A and West Street,'Pittsburgh, Penns'fi vania.
Q.2. Please state your educational background.
A.2. I was graduated from Hardin Simmons University in l 1950 with a Bachelor's Degree in Chemistry and from Fordham University in 1960 with a Master's Degree in Chemistry. I also have taken course work at Stevens l
Institute of Technology in chemical thermodynamics and at Carnegie-Mellon University in radio-l chemistry.
i I
l
I have published over 12 articles in various technical periodicals and have authored or co-authored over 12 Westinghouse reports, all of which have pertained to plant chemistry, steam generator operating experience and corrosion. I am a member of the American Chemical Society, the American Nuclear Society, the National Association of Corrosion Engineers and the American Society of Mechanical Engineers. I am also a member of the Committee on Water in Thermal Power Systems of the ASME.
Q.3. Please state your work experience.
A.3. I was employed with the Vitro Corporation from 1951 to 1955 where I performed research on organo-phosphorus compound synthesis, reaction kinetics and mechanisms of organo-phosphorus compounds, phase studies, bench scale and pilot plant production of organo-phosphites, high and low temperature kinetic studies of boron hydride synthesis, and electro-kinetic studies of electrophoretic deposition of inorganic oxides in the manufacture of reactor fuel l elements.
~
-In 1957, I began my employment with Westinghouse and have been engaged in development work on the I
4 heterogeneous catalysis of reactions between hydrogen and oxygen produced through radiolysis of reactor coolants, reaction kinetics and mechanisms, catalyst development and evaluation in high
. temperature and pressure aqueous solutions; evaluation and study of reactor coolant contaminants and means of coolant purification; study of behavior of fission and corrosion products-in reactor coolants; in-pile studies of reactor coolants as pertains to chemical shim technology; reactor plant chemistry control, analyses, and data collection and interpretation of all operating reactor systems designed by Westinghouse.
Since 1970, I have been directly involved in development and design activities related to Westinghouse steam generators. Under my direction, steam generator programs related to operations have been executed involving chemistry and materials as well as specific design configurations. During this period, I held management positions pertaining to chemistry, materials and steam generator operations and analysis.
Recently, and until November 1982, I was Manager of Steam Generator Development and Performance l
F s
Engineering which had responsibilities for steam generator thermal / hydraulic design and verification, advanced steam generator design and analysis and field modification designs.
Prasently, as Manager of Steam Generator Materials I
and Chemistry, I am responsible for plant chemistry and material aspects related to steam generators and the reactor primary system. This entails operating plant follow and resolution of filed issues, research and development programs related to both l
the steam generator chemistry and materials and the reactor primary system.
Q.4. What is the purpose of your testimony?
A.4. The purpose of my testimony is to provide an l %
overview summary of the other %estinghouse witnesses testimony on the panel with respect to addressing both the Rockford League of Women Voters Contention l
22 and DAARE/ SAFE Contention 9c. These contentions question the safety of Commonwealth Edison's Byron plant owing to the potential for steam generator tube degradation under either normal operation o$
accident conditions.
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I do not agree with the apparent safety concerns raised by the intervenors.on the basis of my own understanding of the issues and the previous witnesses' testimony having shown~that the inherent features and operating measures and limitations of the Byron steam generators minimize the potential for safety-related events consistent with NRC's General Design Criterion 14; and, therefore, steam generator tube degradation should not be considered a safety issue.
Q.5. Who are the witnecses you referred to in your A.4.?
A.S. The testimony of Dr. Conway, Dr. Wootten, Dr. Patel, Mr. Malinowski, Mr. Timmons, Mr. Blomgren and Mr.
Paul.
^
Q.6. What is the basis for your opinion that tube degradation in the Byron steam generators should not be considered a safety issue?
A.6. As I previously stated, my opinion is based on the expert opinion of the witnesses I have identified and my understanding of the commitments made by Commonwealth Edison for the Byron Station and my own experience during the past 12 years working on the steam generator tube degradation issues. If I ray explain further -
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4 The Byron steam generators are progressive evolutions in the state-of-the-art design as described by Dr. Conway. These steam generators, being the Model D4 in Byron and 1 and Model D5 in Byron 2, have features which are designed to minimize the occurrence of tube corrosion. Included among the features are a flow distribution baffle which maintains a horizontal sweep of water across the upper surface of the tubesheet so as to minimize the potential for sludge deposition. This sweeping action is directed toward the center of the hot leg tube bundle where the blowdown pipe is located. The blowdown location is another feature different from earlier feedring models, having the design objective of added efficiency for sludge removal. Another feature included in the Model D4 and D5 steam
- generators is that the tubes are full-depth expanded into the tubesheet to minimize accumulation of impurities in the tube-tubesheet crevice. -
All steam generators for Byron 1 and 2 have Inconel 600 tubing material which is a corrosion resistant nickel alloy that has been studied and evaluated extensively by the industry during the last decade.
The properties of Inconel 600 are very well known and the impurities that may affect Inconel 600 in a l
1 l
l
7-manner to cause stress corrosion cracking or- '
thinning'are also quite well known.
The Byron 2'DS. steam' generators also have further advanced state-of-the-art features. The Inconel 600
' tubing has been thermally treated, using a well defined temperature cycle during tubing manufacture
- to provide a microstructural change in the material, -
as well as to provide for reduction in residual stresses. The thermally treated material has'been 4
-demonstrated by Westinghouse and-others in the industry to provide significant resistance to stress corrosion cracking. In addition, in the Model D5 steam generator for Byron 2, the-tube support plate i
material has been changed from carbon steel to a Type 405 stainless steel which also provides corrosion resistance against impurities.
I Operating plant experience has indicated the need for rigorous control of the water chemistry i
environment of the entire steam cycle. As described by Dr. _Wootten, All Volatile Treatment (AVT) has been selected by the majority of the industry as the most suitable chemistry for the system, which includes the steam generators, AVT chemistry control is based on a philosophy of minimum i
contaminant ingress through'the practice of good initial design and material selection of condensers, feedwater heaters, makeup water systems and other components. Further, AVT control.is maintained by appropriate inspection and maintenance practices and operator actions during plant operation. Adherence to AVT guidelines enhances the long term integrity of the steam cycle, by minimizing the corrosion of condenser'and feedwater heater materials, the steam generator and the turbine. This in-turn minimizes the formation of corrosion products which are delivered to the steam generator, thus reducing the potential for tube corrosion.
AVT chemistry guidelines were first issued by Westinghouse during 1974 and they have been adopted by the majority of the utilities in the U.S. These guidelines have been reviewed by industry groups and more recently, in order to reinforce the need for rigorous chemistry control, EPRI has issued AVT guidelines as a model to be reviewed by the industry. Because of the extensive laboratory work that has been performed in evaluating the mechanisms of stress corrosion cracking, thinning and denting of the steam generator tubes, it is clear that impurities admitted to the steam cycle which
l ultimately may reside in the steam generator, must be_ limited. Impurities such as air, which contains-oxygen, condenser cooling water such as fresh water sources that contain excess alkalinity, make-up water impurities and the like must be excluded to the extent possible. It has also been demonstrated that copper bearing alloys in the feed train can participate in corrosion reactions when transported to the steam generator. There are no copper bearing alloys in the feed train at the Byron Station. The industry has progressed significantly in operating and maintenance practices by the utilities in meeting the AVT guidelines.
Mr. Malinowski has described in some detail the types of corrosion that have occurred in operating plant steam generatc~3 Each of these types of l
corrosion have been examined in detail by Westinghouse and other industry groups and in conjunction with EPRI so that we bel.ieve to have a good understanding of the mechanisms and causes l involved. Caustic impurities have been responsible for much of the observed tubing corrosion, which provides the basis for minimizing condenser leakage of caust'ic-forming natural waters and leakage of I
caustic from condensate polishers and makeup water l
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systems. Correspondly, acid chloride along with oxidizing impurities which are responsible for tube denting and pitting are to be avoided by rigorous attention to condenser leakage.
Mr. Timmons has provided a detailed description of the Model D4 and D5 steam generators along with the status of operating experience and testing applicable to these units. Tube wear due to flow induced vibration is not expected to be a continuing concern because of the lesser amount of tube vibration noted for the counterflow steam generator.
Moreover, candidate modifications to the counterflow steam generators have been identified and are undergoing laboratory and in-plant testing for effectiveness in reducing vibrations. Modifications at the Byron Station are expected to be finally identified and available by the third quarter of 1983, to support the plant schedule.
At this point, I would likt to briefly review the five events in operating plant steam generators that have led to large rates of primary coolant leakage through a steam generator tube.
, The first event occurred in a steam generator tube at' Point Beach' Unit 1 in 1975Ethat had previously been thinned by phosphate chemistry. . Subsequent conditions believed related to the conversion of
, steam generator chemistry from phosphate to AVT led to the accumulation of caustic around one tube and this in turn led to stress corrosion cracking within the previously thinned. region. When stress l corrosion cracking penetrated the tube wall at the unreinforced thinned region of the wall the tube developed an abrupt, large leak. The plant was shutdown following the normal procedures. As described by Dr. Wootten, phosphate chemistry control of the steam generator water led to tube corrosion in some plants, which included Point Beach
- Unit 1. With this finding, Westinghouse recommended i
in 1974 that phosphate control be replaced by AVT and the majority of utilities have adopted thisi j chemistry, including Commonwealth Edison for the Byron Station. For all other plants on AVT since its introduction, there has not been a large leak event as that at Point Beach, and, therefore, such mechanism is not expected at Byron.
A second event of large tube leakage occurred at Surry Unit 2 in 1976 in a steam generator that was
experiencing extensive, active tube denting.
Because of denting,.the apex of a narrow radius U-bend tube was ovalized producing high stresses to such a degree that stress corrosion cracking occurred in that location of the tube. Cracking originated from the inside surface of the tube which was diagnosed to be due to the presence of high stress and. active straining of the tube wall in contact with high temperature water. The cause and effect is rather clear in that secondary side tube support plate crevice corrosion led to tube denting which in turn led to closing together of the tube legs at the upper plate, causing the active straining and high stress in the tube wall. To minimize the potential for this occurrence,.
secondary side water chemistry control is to be maintained and thus avoid the incidence of denting.
The elements of AVT chemistry control were described by Dr. Wootten. Moreover, periodic steam generator inspections as described by Mr. Malinowski will detect tube denting, if present, to allow for actions to be taken in advance of extensive straining of tubes in the U-bend. These actions may consist of more rigorous chemistry control or ,
plugging of affected tubes, if necessary. Also, in Byron 2, the steam generator tube support plate
material in 405 stainless steel which significantly resists the corrosion mechanism which can lead to tube denting. For these reasons, therefore, tube leakage at the apex of the U-bend of the tubes is not expected _to occur at the Byron Station.
The third event occurred in 1979 in a Doel Unit 2 steam generator. The Doel plant is located in Belgium. The leakage was confirmed by visual examination to have occurred at the apex of the U-bend of the small radius (innermost) tube.
Investigation by gauging techniques showed the tube, at the location of leakage, had significant ovality in that it would not pass selected ball gauges. The high degree of ovality imparts high residual stresses to the tube which influences its susceptibility to stress corrosion cracking.
Investigators have attributed the ovality to be the result of improper fabrication. Other tubes found to have excess ovality were plugged and there has not been a recurrence of leakage at this location.
The Byron steam generator tubes are all inspected after fabrication so that the extent of ovality is measured to be within design limits. Thus, leakage l 1
from this cause is not expected in the Byron Steam generators.
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The fourth large tube leakage event occurred at the Prairie Island Unit 1 plant in 1979. Following plant. shutdown,-inspection showed the leaking tube on the periphery of the tube bundle had undergone localized wear due to the presence of a foreign object. The object was a coil spring which remained-in the steam generator following an' earlier outage for steam generator maintenance. Application of rigorous ?nspections and inventory control of items-
! used for s'eam generator maintenance is expected to minimize.the potential for this type of occurrence.
A fifth large leakage of event occurred at-the Ginna
. plant during 1982. This occurrence was also due to
[ the presence of a foreign object which. impacted
! against and severed a previously plugged tube. 'The l severed tube subsequently wore against an unplugged tube providing a long wear scar which ultimately lead to tube leakage. Again, with due attention to
- loose parts through inventory and inspection, a repeat of this event is not expected.
As to the question of loose parts in a steam generator and the potential impact on steam i
- generator tubes, this issue is being actively pursued by the industry. Special attention is being l
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1 applied-to inspection and retrieval techniques for.
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loose objects in the steam generator through tooling developmental efforts. Fiberoptic and. television.
~
- view devices are being utilized for searching annular regions of the steam generator and other confined areas. Inventory control procedures are implemented such that during maintenance operations 1
-i tooling and other devices are accounted for before j and after the-work is completed so as to not leave l
, any part in the steam generator. Further, loose i
parts monitoring systems are utilized for l indications of impact signals within the steam generator that alert operators to the possible
, . presence of metal objects. Thus, with the implementation of these controls, observations and procedures, the loose parts issue should diminish.
Mr..Malinowski further described the process of inspecting steam generator tubes in. considerable detail and illustrated that tube degradation can be detected and quantified before the integrity of the tube is called into question as a safety issue.
i Periodic inspection by the operating plant utilities have provided the means by which tube degradation, I
I if present, can be measured with respect to the tube
- plugging criteria established by the U.S.N.R.C. in
[.
t I.
V - ire a- *-*- - p -.g.gy .- g ..~y .w,p. 1 y _,,,_m ,yy_,,,,,,m , , , , , , , , p ,_ y, y, p _
the plant technical specifications. The sensitivity of eddy current testing'using multi-frequency techniques is generally expected to meet the requirement to' detect 40% tube wall penetration and below. This is expected for such forms of tube degradation as cracking, thinning, or wear.
Presently under refinement is the eddy current technique for detecting and measuring the existence of intergranular attack, which is another form of caustic corrosion. Continually active programs in the industry have yielded state-of-the-art improvements in c '.iy current testing to a high degree of reliance. These techniques are being further developed for ease of signal interpretation-and efficiency of inspection.
Eddy current testing is only one means that provides surveillance against tube degradation. Eddy current testing is substantially supported by the inherent features of the steam generator tubing material.
These features as described by Dr. Patel include recognition that Inconel 600 is a material with considerable toughness and ductility. This means that the tube material will behave in a fashion to first resist very high pressures and then to respond in an elastic, rather than a brittle, manner. This
behavior supports the characteristic referred to as leak-before-break which has been established through extensive testing of the Inconel 600 tube material.
Should stress corrosion occur in the_ tube wall, the propagation of the crack will be such as to penetrate the wall before the crack extends a certain length. Inherent to operator control is the leak rate limitation placed on the plant during operation in the case of tube degradation such as to preclude a crack length in excess of the critical crack length. In other words, leakage from crack penetration of the tube wall can be detected at an early stage in crack progression allowing for appropriate action by plant operators. It further means that while meeting primary to secondary leak rate limitations, if the tube were to be subjected to high pressure such as resulting from a MSLB, the tube would not burst because the length of the crack would not have exceeded the critical crack size.
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l l In addition to eddy current testing and leak-before-l l break characteristics, other operations are applicable which provide margin against safety concerns related to the tube. One is that periodic hydrostatic testing of the steam generators is performed which provides an overall measure of the
tube bundle integrity.. Another' feature is in the
, _ tube plugging criteria established by.theHU.S.N.R.C.
V which contains'conservatisms within regard to the actual strength capabilities-of the tube.
Mechanical analysis of the strength of the steam generator tube material under normal operation, LOCA ,
and the more limiting Feedline~ Break / Steam Line Break conditions provides the basis.for the tube plugging criterion as described by Dr. Patel. The analysis is supported by extensive burst and collapse testing and shows that there is conserva-tism in the U.S.'N.R.C._ applied tube plugging criteria. All of these features couple'd with the inherent corrosion resistance of Inconel 600 provide significant margin against tube degradation becoming a safety concern.
[ Overall, my summary emphasizes.the important l considerations that have been made so that reliance can be placed on steam generator design, operation,
- inspection, and maintenance to conclude that tube
, . rupture should not occur even under conditions of the postulated MSLB or LOCA accidents. The events which led to large tube leaks are well understood by i the industry and considerable attention has been l
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i devoted by the indostry to substantially minimize a reoccurrence of-these experiences. Therefore, I-do not believe that the contentions identified by the League of Women' Voters and DAARE/ SAFE should remain a Concern.
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