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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
[Table view] |
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. . . __ _ ______. - __ _ _
3- .
DOCKETED U.;W f' UNITED STATES OF AMERICA NUCLEAR REGULATORY) CgiIpSI,9N59 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) )
a TESTIMONY OF MICHAEL J. HITCHLER CONCERNING STEAM GENERATOR TUBE INTEGRITY (QUANTITATIVE ASSESSMENT)
Submitted on behalf of the Applicant, Commonwealth Edison Company in Response to DAARE/ SAFE Contention 9c and League Contention 22 February 28, 1983 n.-
T m-y ,n- , - - - - ,
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) )
SUMMARY
m The summary of Mr. Michael J. Hitchler sets forth his professional qualifications and provides a quantitative assessment of the frequency of steam generator tube ruptures under normal operating conditions and accident and transient conditions, such as main steam line breaks, loss-of-coolant-accidents'and other events. Mr. Hitchler finds.that the frequency of tube ruptures in such circumstances is sufficiently low that these accidents and other events coincident with tube ruptures need not be considered further in the design of the Byron Station. Mr. Hitchler concludes by confirming Mr. Fletcher's opinion that steam generator tube degradation under normal operating and accident conditions is not a safety concern.
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 3) )
TESTIMONY OF MICHAEL J. HITCHLER CONCERNING STEAM GENERATOR TUBE INTEGRITY (QUANTITATIVE ASSESSMENT) 0.1. State your name, address and occupation.
A.l. My name is Michael John Hitchler. I am Manager of Probabilistic Risk Assessment with the Nuclear Safety Department of Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230.
Q.2. Please state your educational background.
A.2. I graduated from Lowell Technological Institute in 1974 with a Bachelor of Science Degree in Nuclear and Mechanical Engineering and from Carnegie-Mellon University in 1978 with a Master of Science Degree in Mechanical Engineering.
i I have published over five articles in various technical periodicals and have authored or co-
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authored over eight Westinghouse reports, which g, y
pertained to reactor accident analyses, emergency / - '
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abnormal operating instruction' development and probabilistic risk analyses'. ,
J r, h l Q.3. Please state your professional work experience with si; s \
Westinghouse, , 's , ,
.'i A.3. I joined Westinghouse in June 1975 as dn Engineer.'
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I was promoted to Senior Engineer in' December'1978. .
My responsibilities during that time included #
performing accident analysis for accidents used in licensing dccuments. I have served ~as a Westinghouse interface with the NRC, architect engineers and utilities for . issues concerning ~~
reactor protection system design requirements. .,
Specific areas of specialization include core and 1
systems response to transients initiated in the '
primary system, development of methodology for '
safety analysis of reload cores, and simulation of ,
actual plant transients for computer verification ,
j purposes, included was the lead responsibility for the transfer of the above technology to various
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utility customers. This included the structuring of - .
i l classroom as well as on-the-job training for a l
number of utility personnel.
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j 'In June 1981, I was assigned responsibilities in the
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, risk assessment area.
These responsibilities tn-
,, involved the development and implementation of strategkeprogramstoenhanceandtoapplyrisk-
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assessmen't technology for use in nuclear power plant design and licensing. .This work included
> ,, develophent;and quantification of event trees for
- use in revi' ewing emergency and abnormal operating
' procedures as part of the' Westinghouse Owner's' Group a r e response to post TMI issues. I assisted in the
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development and review of Auxiliary Feedwater System
, . , , Reliability Studies for three nuclear plants.
/ .
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'In October 1981, I was promoted to the position of a
Manager,'Probabilistic Risk Assessment Group. I presently have lead responsibility for a I probab listic risk study of the Sizewell B. (British National Nuclear Corporatica) Nuclear Station, which c 4 include development of a risk baseline and an assessment of potential design alternatives. I have
/
s also worked on the Zion and Indian Point risk studies, contributing extensively in the following are,as :' plant and containment, event tree co struction, systems success criteria for fault tree ' dev'elopment , external (seismic, wind, fire,
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4-etc.) event analysis and review of the ramification sections.
I am a member of the American Nuclear Society and the American' Society of Mechanical Engineers. I served on two AES Standards committees and contributed to several AIF and IEEE committees on development of Risk. Criteria and Utilization of PRA
~~
Approach to licensing. I am currently a member of 1
the PRA Fethodology Procedures Handbook Committee.
Q.4.- What is the purpose of your testimony?
A.4. The purposesof my testimony is to address those aspects of thle Rockford League of Women Voters' c, , Contention 22 and DAARE/ SAFE Contention 9c concerning i steam generator tube ruptures both during
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, , . /' normalsoperation and under accident conditions, such
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..s' a .main steam line breaks (MSLB) and loss-of-
"l [ coolarit-accidents (LCCA). Specifically, I provide a
- / y v quant'itative assessment of the frequency of these
,s - ,,,< . >- events and.an assessment.of their impact on safety.
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l Q.5. Please de, scribe the nature of your assessment.
A.5. I have supervised and participated in the develop-ment of'a model', which is summarized in Attachment
. , 4 A, for, providing a coniservative assessment of steam
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generator tube rupture frequencies based on the pressure differentials across the steam generator tubes. The model is conservative because it takes no credit for recent modifications in steam generator design or operations. Rather it conserva-tively assumes that steam generator tube degradation rates in the future will be the same as over the previous 2.5 million tube years of operating expe-rience. Also the model assumes that the five major i tube leaks which have occurred were full tube ruptures when in fact a full tube rupture has never occurred. Most of these events had less than 20% of the leak rate of full tube ruptures.
Q.6. What are the results of your assessment?
A.6. The results of this assessment are that single and multiple tube ruptures as initiating events are
-2 predicted to occut at frequencies of 3 x 10 and
-5 The frequency of 3 x 10 per year respectively.
multiple tube ruptures combined or as a consequence
~
of (i) large LOCA events is 5 x 10 , and (ii) small LOCA and transient events with normal pressure
-5 differentials is 2 x 10 . The frequency of multiple tube ruptures combined or as a consequence
-5
. of steam / feed line break events is 3 x 10 ,
Q.7. What conclusions, if any, have you drawn from the results of your assessment?
A.7. The frequency of postulated tube ruptures combined or as a consequence of transient conditions and accident conditions such as MLSB's and LOCA's are extremely low over the 40 year's of plant operation.
Therefore, I would expect the PWR operating experience (presently 350 years) of no steam generator tube ruptures occurring as a result of steam-line breaks, LOCA's or other events, to continue. Finally, I conclude that these events are of sufficiently low frequency that they need not be considered further in the Byron Station design.
Q.8. What is the basis for your opinion that the steam generator tube-rupture frequencies from the accidents and transients discussed above are sufficiently low a exclude further consideration in the Byron Statir design?
A.8. A precise nume al definition for what events are beyond the desi,n basis has not been made. However, numerous events have been defined as being at the design basis limit. From these can be inferred a frequency range below which events need not be considered.
The SSE (Safe Shutdown Earthquakes) is an example.
For the Byron units, the SSE is defined as a 0.2g ground acceleration earthquake. Most nuclear plants are designed near this value. This seismic design 4
basis takes into account those events with recurrence frequencies of one every 1,000 to 10,000 years (10 -3 to 10-4). Probabilistic quantifications utilizing techniques similar to Attachment A (for example, WASII-1400 and the Zion and Indian Point Probabilistic Safety Studies) conservatively show other postulated events, such as, large and medium size LOCA's and steam line breaks to have recurrance intervals of approximately 1000 years per reactor.
Another approach to defining frequency limits for events beyond the design basis is the proposed NRC Safety Goal. The safety goal recently issued by the USNRC for trial use is also consistent with the 10-
-4 to 10 range of recurrence. The severe core damage frequency limit is 10 -4 per year or a recurrence intervpl of once every 10,000 years, and it represents a summatic.t of the frequencies of all scenarios that could lead to severe core damage.
Using the above values as a baseline, the frequency of events described in my answer to question 5. are
beyond the design envelope established by the nuclear industry and the NRC over the years. This does not mean that these events will rever happen, but rather that their frequency of occurrence are sufficiently small relative to the operating life of the units to be cor.sidered incredible.
Moreover, tube rupture events are predicted to result in severe core damage at frequencies of 10-per year for the Byron Station. Stated differently, the likelihood.of a severe core melt occurring at the Byron Station from tube rupture events is one-in-a-billion per year, an extremely low value, well below NRC's proposed safety goal, and a negligible contributor to meeting the goal.
Q.9. Have you read Mr.-Fletcher's testimony in this case?
A.9. Yes.
Q.10. How does your conclusion concerning the consideration of steam generator tube ruptures compare with his assessment?
A.10. My conclusion is consistent with that drawn by Mr.
Fletcher. Mr. Fletcher, using traditional deterministic methodology, concludes that steam generator tubes should not rupture as a result of a
_9_
MSLB or LOCA because the various meastres identified in his testimony assure that steam ge:1erator tube integrity will be maintained. My analysis does not take credit for recent modifications in steam generator design or operation to minimize tube degradation, but it nevertheless shows that such accidents are very low frequency events. Therefore, if the modifications in steam generator design and operation discussed by Mr. Fletcher and the other panel witnesses were taken into account, my frequency values would be even lower. I can only conclude that.my assessment, conservative as it is, confirms Mr. Fletcher's opinion that steam generator tube degradation under normal operating and accident conditions is not a safety concern.
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SGTR PROBABlLXTY MODEL
- 1. TUBE RUPTURE FREQUENCY The experienced frequency of tube rupture events is about x =
2x10-0 per tube year of operation. This is cased on 5 events in about 2.5 million tube years experience. There are 4578 tubes in each of the four Byron steam generators. The frequency of tube ruptured based on this historical data would then be 0.037 per year of plant operation. This should be a conservative estimate Decause improvements in operation and design as a result of knowledge gained from the experience to date would be expected to reduce the frequency of tube' rupture in the future. In this study, the conservative value of U.037 ruptures per year will be employed.
This approach is taken for two reasons. First of all', this study is attempting to ascertain the effects of tube rupture on risk. The use of a conservative value helps .to set an upper bound on the tube rupture risk impact while avoiding potential concerns about the validity of a more realistic estimate. Secondly, the use of a more realistic value would involve a " fine tuning" of the data and analyses that would be inconsistent with the scope depth of this study.
- 2. TUBE RUPTURE PROBA8ILITY AS A RESULT OF PRESSURIZATION LUA0
. The x = 2x10-6 per tube year rupture frequency identified above is the frequency of degradation to the extent of rupture under the normal operation tube differential pressure load in the range of 1250 psi . The frequency of degradation to the extent of rupture under faulted condition loads sucn as the approximately 2650 psi secondary pressurization accident differential pressure would.have to be of this magnitude also. It is assumed that for a tube that does degrade to this extent, it may take anywhere from 0 to 40 years of operation with equal probability. The time that a degrading tube spends in the 2650-1250 psi capability range is thus estimated to be (sec Figure 1)
2650-1250 t* *E10,000-1260] t = 0.16t
'n tnis expression,10,000 psi is the minimum virgin tube ourst capability caseo upon laboratory testing, and t is the time for a degrading tube to cegrade to 1250 psi capaoility wnicn is assumed to De a uniform distribution from J to 40 years of service life. Ine average value of t would be 20 years.
uiven an accidental secondary depressurization event, then the probability that a tube exposed to 2650 psi differential pressure would rupture is (1) p = A t* = 0.16xt per tube The steambreak/feedbreak high pressure differentials are applied to only one of the steam generators should uncontrolleo blowdown occur. Based on this and the assumption that each tube's failure probability is random and independent, the probability of various numbers of tubes rupturing can be evaluated from the binomial distribution (2) P(r) =
r'(n r)' Y" * (1-P}" "
where n = no. of tubes in one SG = 4578 r = no. of tubes rupturing, i.e.1 or 2 or J . ..
p = probability of individual tube failure from Eq. (1)
P,( r) = probability of r tubes failing.
This model gives the following results for 1, 2, or 3 tubes rupturing from FL8/SLB loads.
f l
Probability That steam dreak Event l'ould Causs
-', Tune Rupture YEARS OF PLANT OPERATION No. of Tuoes Ruoturin9 t = 1 yr. t = 20 y r. t = 40 yr. AVG Proc. of one tuce rupture 1.4 x 10-3 2.8 x 10-2 5.6 x 10-2 3 x 10-2 Proo. of two tuce ruptures 1.1 x 10-6 4.2 x 10-4 1.7 x 10-3 6 x 10-4 Proo. of three tuce ruptures b x 10-10 3.9 x 10-0 J.2 x 10-5 g x 10-6 The uncertainty range on 1 is about a factor of 2.5. Allowing an additional factor of 2 to cover uncertainties in the Figure 1 model and tne linear degradation assumption, the 90 percent uncertainty range for p in equation (1) would be a factor of aoout 5. Based on this, the uncertainties on the results for one, two and three tubes rupturing is estimated to be factors of 5, 25, and 125 respectively.
This same approacn can be used to estimate the consequential tube rupture probability for other events in which the differential pressures experienced are greater than for nonnal operation but less than those for severe faulted
~
events as above. This includes ATWS where all four steam generators are subjected to lower tube differential pressures. Extensive testing has snown that the strength requirement to guard against tube rupture during a postu-1ated feedwater 1ine or steam 1ine break (FLB/SLB) is always acre-1imiting in tenns of tube wall thickness than for tube collapse for a postulated LOCA.
For this reason the FLB/SLB tube rupture probabilities can be conservatively employed for a LOCA, although it should be realized that the loading in case of a LOCA would be in a direction to seal off leaks or collaspe tubes rather than cause a large leakage path.
- 3. TUBE RUPTURE LEAR RATE PROBABILITY DISTRiduTION Table 1 summarizes the 5 tube rupture events experienced to date and gives the estimated initial leak rates. Figure 2 provides the probability of
_ exceeding various leak rates based on this experience. It is noted that in only 20 percent of the cases are the leakages as high as the greater
" ~ - -
. than 600 GPM ranga typical of 4 double ended rupture. Tho avsrage has
. btea 273 GPM or less dian half. Furthermore, the experience has b :n on 0.875 incn u0 tubes as opposed to the 0.75 inch UD tubes on the dyron 04 steam geneator. Based on tnis, the leak rates of Figure 2 would be expected to De scaled down by the square of the diameters or a factor of u.735. On this basis, assumption of a 600 GPM leak would already corres-pano to practically 2 to 3 tunes of average expectea leakage. Therefore, it would be appropriate to comoine a distribution of the type shown in Figure 2 with multiple tube rupture frequencies to obtain more realistic frequency vs leak rate relations.
(
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, FIGURE 1 MODEL FOR PROBABILITY OF TUBE RUPTURE J LLOAD INCREASE 10,000 7------L = Initial tuce pressure capability = 10,000 psi g
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6 8,000 -
\
2 \
F \
7,000 -
Assumed path of tube that would degrade to failure in
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g t years of operation a
s-y 5 6,000 - \
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5,000 -
g b
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2 4,000 \
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v 3,000 \
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L slb = Capability of tube failing under FLB/SLB load = 2650 psi E 2,000 -
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Ly--L" = Capability of tube that fails 1,000 -
t % 'under normal operating load
= 1250 psi 0
10 20 30 40 YEARS OF SERVICE l
A = Frequency of severe degradation to rupture (per tube year) = 2 X 10-6 per year per tube l t = Time to fail under nonnal load (assumed random over period 0 to 40 years) t* = Time vulnerable to feedbrwak/steambreak load (years)
'slb ~ 'no t* = t ( )
L o
-L a
!. Lslb - L no i p = Probability of failure given FLB/SLB loads = At* = At ( )
Lg -L no l -- - . - - - - _
. FIGURE 2 PROBABILITY OF EXCEEDING VARIOUS INITIAL LEAK RATES GIVEN A STEAM GENERATOR TUBE RUPTURE
1.0 BASIS
Leak rate estimates from five tube rupture events that have occurred 0.9 -
to December 1982 (see Table 1) 0.8 -
x al 0.7 _ tVENT LEAK RATE o
0.6 1 125 GPM 2! _ _
a 2 80 j 0.5 -
3 135 4 390 3! 0.4 -
- 5 634 S 0.3 - -
@ AVG 273 a = 235 0.2 -
0.1 -
, , , , , , i 0 100 200 300 400 500 600 700 LEAK RATE (GPM)
NOTE: The above experience has been with 0.875 inch OD tubes. For 0.75 inch OD Byron tubes the above should be apportioned down by approximately a factor of
= 0.735
( 0.875 )
g -r
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TABLE 1 ,
TUBE RUPTURE EXPERIENCES
SUMMARY
t I
Occurrence NO. Date P iu.. .'startup date) Attributed Cause Estimated Leak Rate 1 Feb. 26,1975 Point Beach 1 (Oct. 70) Phosphate Wastage + SCC 125 gpm III
, 2 Sept. 15, 1976 Surry 2 (Jan. 73) Denting + SCC 80 gpm III 3 June 25, 1979 Doel 2 (June 75) Ovality + SCC 135 apm III l 4 Oct. 2,1979 Prarie Island 1 (Aug. 73) Loose part (spring) 390 gpm III 5 Jan. 25, 1982 Ginna (Sept. 69) Loose part (plate) 634 gpm(2) i W
l Raf.
- 1. NUREG-0651, Evaluation of Steam Generator Tube Rupture Events, USNRC, Appendices Card H,11 arch 1980
- 2. Response to Long Term Commitments, Ginna Restart SER, Steam Generator Tube Rupture incident, November 22, 1982 Attachment 8, Analysis of Plant Response During January 25, 1982 Steam Generator Tube Failure at the R.E. Ginna Nuclear Power Plant. ,
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