Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/E Duda on 850731 in Newport,MiML20237J911 |
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Fermi |
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07/31/1985 |
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NRC OFFICE OF INVESTIGATIONS (OI) |
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ML20237J518 |
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References |
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FOIA-86-245 LB-85-214, NUDOCS 8708260364 |
Download: ML20237J911 (27) |
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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARNRC-99-0093, Comment on Prs 10CFR30,31,32,170 & 171 Re Requirements for Certain Generally Licensed Industrial Devices Containing Byproduct Matl. Licensee Unclear Whether Requirements Apply to Holder of Operating License1999-10-12012 October 1999 Comment on Prs 10CFR30,31,32,170 & 171 Re Requirements for Certain Generally Licensed Industrial Devices Containing Byproduct Matl. Licensee Unclear Whether Requirements Apply to Holder of Operating License NRC-99-0080, Comment Opposing Proposed Rule 10CFR50 Re Consideration of Potassium Iodide in Emergency Plans.Detroit Edison Strongly Urges NRC to Not Issue Amend to 10CFR50.471999-09-13013 September 1999 Comment Opposing Proposed Rule 10CFR50 Re Consideration of Potassium Iodide in Emergency Plans.Detroit Edison Strongly Urges NRC to Not Issue Amend to 10CFR50.47 NRC-99-0071, Comment Supporting Draft RG DG-1083, Content of Ufsar,Iaw 10CFR50.71(e), Dtd Dec 19981999-04-30030 April 1999 Comment Supporting Draft RG DG-1083, Content of Ufsar,Iaw 10CFR50.71(e), Dtd Dec 1998 ML20205A7871999-03-26026 March 1999 Error in LBP-99-16.* Informs That Footnote 2 on Pp 16 of LBP-99-16 Should Be Deleted.With Certificate of Svc.Served on 990329 ML20205A8321999-03-26026 March 1999 Initial Decision (License Granted to Sp O'Hern).* Orders That O'Hern Be Given Passing Grade for Written Portion of Reactor Operator License Exam Administered on 980406.With Certificate of Svc.Served on 990326.Re-serve on 990330 ML20202B1561999-01-28028 January 1999 Memorandum & Order (Required Filing for Sp O'Hern).* Petitioner Should Document,With Citations to Record, Precisely Where He Disagrees or Agrees with Staff by 990219. with Certificate of Svc.Served on 990128 NRC-98-0154, Comment Supporting Proposed Rules 10CFR50,52 & 72 Re Changes,Tests & Experiments.Detroit Edison Fully Supports Comments Being Submitted on Proposed Rule by NEI1998-12-21021 December 1998 Comment Supporting Proposed Rules 10CFR50,52 & 72 Re Changes,Tests & Experiments.Detroit Edison Fully Supports Comments Being Submitted on Proposed Rule by NEI ML20198B1131998-12-17017 December 1998 Memorandum & Order (Request for an Extension of Time).* Orders That Staff May Have Until 990115 to File Written Presentation.With Certificate of Svc.Served on 981217 NRC-98-0184, Comment on Proposed Rule 10CFR50.65, Monitoring Effectiveness of Maint at Npps. Expresses Concern That Proposed Rule,As Drafted,Will Impose Significant Regulatory Burden on NPPs Which Have Already Developed Risk Programs1998-12-14014 December 1998 Comment on Proposed Rule 10CFR50.65, Monitoring Effectiveness of Maint at Npps. Expresses Concern That Proposed Rule,As Drafted,Will Impose Significant Regulatory Burden on NPPs Which Have Already Developed Risk Programs ML20197J8971998-12-14014 December 1998 NRC Staff Request for Extension of Time to File Response to Sp O'Hern Written Presentation.* Staff Requests That Motion for Extension of Time Until 990115 to File Written Presentation Be Granted.With Certificate of Svc ML20154M8281998-10-20020 October 1998 Federal Register Notice of Hearing.* Grants Sp O'Hern 980922 Request for Hearing Re Denial of O'Hern Application to Operate Nuclear Reactor.With Certificate of Svc.Served on 981020 ML20154M9471998-10-19019 October 1998 Memorandum & Order (Establishing Schedule for Case).* Grants Request for Hearing Filed on 980922 by O'Hern & Orders O'Hern to Specify Exam Questions to Be Discussed at Hearing by 981103.With Certificate of Svc.Served on 981019 ML20154K8601998-10-14014 October 1998 NRC Staff Response to Request for Hearing Filed by Applicant Sp O'Hern.* Request Re Denial of Application for Senior Operator License Filed in Timely Manner.Staff Does Not Object to Granting Request.With Certificate of Svc ML20154F0551998-10-0808 October 1998 Designation of Presiding Officer.* Pb Bloch Designated as Presiding Officer & Rf Cole Designated to Assist Presiding Officer in Hearing Re Denial of Sp O'Hern RO License.With Certificate of Svc.Served on 981008 NRC-98-0035, Comment on Draft RG DG-5008 (Rev 2 to Reg Guide 5.62), Reporting of Safeguards Events. Util Endorses Industry Comments Submitted by NEI1998-03-0909 March 1998 Comment on Draft RG DG-5008 (Rev 2 to Reg Guide 5.62), Reporting of Safeguards Events. Util Endorses Industry Comments Submitted by NEI NRC-98-0010, Comment Supporting Draft RG DG-1070, Sampling Plans Used for Dedicating Simple Metallic Commercial Grade Items for Use in NPP1998-02-17017 February 1998 Comment Supporting Draft RG DG-1070, Sampling Plans Used for Dedicating Simple Metallic Commercial Grade Items for Use in NPP NRC-98-0030, Comment Opposing PRM 50-63A by P Crane Re Prophylactic Use of Potassium Iodide for General Public1998-01-16016 January 1998 Comment Opposing PRM 50-63A by P Crane Re Prophylactic Use of Potassium Iodide for General Public NRC-98-0012, Comment Opposing Proposed Rule 10CFR50 & 70 Re Exemption from Criticality Accident Requirements. Detroit Edison Concerned That Proposed Changes Will Not Provide Sufficient Flexibility Meeting Regulations to Criticality Monitoring1998-01-0202 January 1998 Comment Opposing Proposed Rule 10CFR50 & 70 Re Exemption from Criticality Accident Requirements. Detroit Edison Concerned That Proposed Changes Will Not Provide Sufficient Flexibility Meeting Regulations to Criticality Monitoring NRC-97-0096, Comment on Draft Reg Guides DG-1061,1062,1064 & 1065,draft SRP Chapter 19 Rev L ,chapter 3.9.7 Rev 2C ,chapter 16.1 Rev 13 & Draft NUREG-1602 Dtd June 19971997-09-29029 September 1997 Comment on Draft Reg Guides DG-1061,1062,1064 & 1065,draft SRP Chapter 19 Rev L ,chapter 3.9.7 Rev 2C ,chapter 16.1 Rev 13 & Draft NUREG-1602 Dtd June 1997 NRC-97-0078, Comment on Draft Reg Guides DG-1061,1062,1064 & 1065,draft SRP Chapter 19 Rev L ,chapter 3.9.7 Rev 2C ,chapter 16.1 Rev 13 & Draft NUREG-1602 Dtd June 19971997-08-0606 August 1997 Comment on Draft Reg Guides DG-1061,1062,1064 & 1065,draft SRP Chapter 19 Rev L ,chapter 3.9.7 Rev 2C ,chapter 16.1 Rev 13 & Draft NUREG-1602 Dtd June 1997 ML20112G8451996-06-11011 June 1996 Comment Opposing Proposed Rule 10CFR50, Reporting Reliability & Availability Info for Risk-Significant Sys & Equipment NRC-96-0024, Comment on Proposed Rule 10CFR20 Re Reporting Requirements for Unauthorized Use of Radioactive Matl.Util Supports Need for NRC to Be Promptly Informed of Incidents Involving Intentional Misuse of Licensed Matl1996-02-28028 February 1996 Comment on Proposed Rule 10CFR20 Re Reporting Requirements for Unauthorized Use of Radioactive Matl.Util Supports Need for NRC to Be Promptly Informed of Incidents Involving Intentional Misuse of Licensed Matl NRC-96-0010, Comment Opposing Petition for Rulemaking PRM-50-63 Re Use of Potassium Iodide1996-02-12012 February 1996 Comment Opposing Petition for Rulemaking PRM-50-63 Re Use of Potassium Iodide NRC-95-0131, Comment on Petition for Rulemaking PRM-50-62 Re Changes to QA Program.Agrees That Changes Needed in Process for QA Program Revs1995-11-28028 November 1995 Comment on Petition for Rulemaking PRM-50-62 Re Changes to QA Program.Agrees That Changes Needed in Process for QA Program Revs NRC-95-0107, Comment Supporting Proposed Rules 10CFR2,50 & 51 Re Decommissioning of Nuclear Power Reactors1995-10-12012 October 1995 Comment Supporting Proposed Rules 10CFR2,50 & 51 Re Decommissioning of Nuclear Power Reactors NRC-95-0103, Comment on Draft Reg Guide & NRC Bulletin, Potential Plugging of ECCS Strainers for Debris in Bwr. Supports Points That Bulletin Should Include Option of Justifying Operability of Currently Installed Passive Strainers1995-10-0202 October 1995 Comment on Draft Reg Guide & NRC Bulletin, Potential Plugging of ECCS Strainers for Debris in Bwr. Supports Points That Bulletin Should Include Option of Justifying Operability of Currently Installed Passive Strainers 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 NRC-95-0080, Comment on Proposed Generic Communication Re Testing of safety-related Logic Circuits1995-07-21021 July 1995 Comment on Proposed Generic Communication Re Testing of safety-related Logic Circuits NRC-95-0078, Comment Supporting Proposed Generic Communication Re Process for Changes to Security Plans W/O Prior NRC Approval1995-07-14014 July 1995 Comment Supporting Proposed Generic Communication Re Process for Changes to Security Plans W/O Prior NRC Approval NRC-95-0079, Comment Supporting Pr 10CFR50 Re Changes in Frequency Requirements for Emergency Planning & Preparedness Exercises from Annual to Biennial1995-07-13013 July 1995 Comment Supporting Pr 10CFR50 Re Changes in Frequency Requirements for Emergency Planning & Preparedness Exercises from Annual to Biennial NRC-95-0073, Comment Supporting Proposed Rule 10CFR70 Re Change to NPP Security Requirements Associated W/Containment Access Control1995-06-0909 June 1995 Comment Supporting Proposed Rule 10CFR70 Re Change to NPP Security Requirements Associated W/Containment Access Control NRC-95-0056, Comment Supporting Proposed Rule 10CFR50 Re Primary Reactor Containment Leakage Testing1995-05-0808 May 1995 Comment Supporting Proposed Rule 10CFR50 Re Primary Reactor Containment Leakage Testing NRC-95-0042, Comment Supporting Draft Policy Statement Re Freedom of Employees in Nuclear Industry to Raise Safety Concerns W/O Fear of Retaliation1995-04-10010 April 1995 Comment Supporting Draft Policy Statement Re Freedom of Employees in Nuclear Industry to Raise Safety Concerns W/O Fear of Retaliation NRC-95-0047, Comment on GL, Pressure Locking & Thermal Binding of Safety Related Power-Operated Gate Valves. Draft GL Should Be Revised to Permit Some Use of Plant Operating Experience as Basis for Engineering Judgement1995-03-27027 March 1995 Comment on GL, Pressure Locking & Thermal Binding of Safety Related Power-Operated Gate Valves. Draft GL Should Be Revised to Permit Some Use of Plant Operating Experience as Basis for Engineering Judgement NRC-95-0007, Comment Supporting Proposed Rule Re Proposed Policy Statement on Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities1995-02-0707 February 1995 Comment Supporting Proposed Rule Re Proposed Policy Statement on Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities NRC-94-0145, Comment Supporting Proposed Rule 10CFR50 Re Shutdown & Low Power Operations for Np Reactors.All Util Outages Currently Controlled by Defense in Depth Philosophy Implemented by Operations & Work Control Group1995-01-11011 January 1995 Comment Supporting Proposed Rule 10CFR50 Re Shutdown & Low Power Operations for Np Reactors.All Util Outages Currently Controlled by Defense in Depth Philosophy Implemented by Operations & Work Control Group NRC-95-0001, Comment Supporting Proposed Rule 10CFR21 Re Procurement of Commercial Grade Items by NPP Licensees1995-01-0909 January 1995 Comment Supporting Proposed Rule 10CFR21 Re Procurement of Commercial Grade Items by NPP Licensees NRC-94-0130, Comment Supporting Proposed Rule 10CFR2,51 & 54 Re NPP License Renewal1994-12-0909 December 1994 Comment Supporting Proposed Rule 10CFR2,51 & 54 Re NPP License Renewal NRC-94-0128, Comment Supporting & Opposing Sections of Proposed GL Re Reconsideration of NPP Security Requirements for an Internal Threat,1994-12-0707 December 1994 Comment Supporting & Opposing Sections of Proposed GL Re Reconsideration of NPP Security Requirements for an Internal Threat, NRC-94-0106, Comment Supporting NUMARC Responses Re Reexamination of NRC Enforcement Policy1994-11-30030 November 1994 Comment Supporting NUMARC Responses Re Reexamination of NRC Enforcement Policy NRC-94-0100, Comment on Pilot Program for NRC Recognition of Good Performance by Nuclear Power Plants.Endorses NEI Response to Ref 2 Submitted to NRC on 9410031994-10-13013 October 1994 Comment on Pilot Program for NRC Recognition of Good Performance by Nuclear Power Plants.Endorses NEI Response to Ref 2 Submitted to NRC on 941003 NRC-94-0074, Comment on Proposed Rule 10CFR26 Re Consideration of Changes to fitness-for-duty Requirements.Recommends That Random Testing Scope Remain Same1994-08-0909 August 1994 Comment on Proposed Rule 10CFR26 Re Consideration of Changes to fitness-for-duty Requirements.Recommends That Random Testing Scope Remain Same NRC-94-0070, Comment Supporting Petition for Rulemaking PRM-50-59 Re Changes to Security Program & Safeguards Contingency Plan Independent Reviews & Audit Frequency.Util Believes Further Rule Changes Should Be Made1994-07-19019 July 1994 Comment Supporting Petition for Rulemaking PRM-50-59 Re Changes to Security Program & Safeguards Contingency Plan Independent Reviews & Audit Frequency.Util Believes Further Rule Changes Should Be Made ML20070P1161994-04-18018 April 1994 Comments on DE LLRW Onsite & Radwaste Disposal NRC-93-0149, Comment Supporting Proposed Rule 10CFR73 Re Protection Against Malevolent Use of Vehicles at NPP1993-12-17017 December 1993 Comment Supporting Proposed Rule 10CFR73 Re Protection Against Malevolent Use of Vehicles at NPP NRC-93-0145, Comment on NUMARC Petition for Rulemaking PRM 21-2, Commercial Grade Item Dedication Facilitation. Concurs W/ Petition1993-12-15015 December 1993 Comment on NUMARC Petition for Rulemaking PRM 21-2, Commercial Grade Item Dedication Facilitation. Concurs W/ Petition NRC-93-0144, Comment on Draft NUREG/BR-0058,Rev 2, Regulatory Analysis Guidelines of Us Nrc. Concurs W/Comments Submitted by NUMARC1993-12-0606 December 1993 Comment on Draft NUREG/BR-0058,Rev 2, Regulatory Analysis Guidelines of Us Nrc. Concurs W/Comments Submitted by NUMARC ML20059L3211993-11-24024 November 1993 Exemption from Requirements of 10CFR50.120 Re Establishment, Implementation & Maintenance of Training Program NRC-93-0068, Comment Supporting Petition for Rulemaking PRM-50-58 Re VEPCO Petition to Change Frequency of Emergency Planning Exercises from Annual to Biennial1993-05-0505 May 1993 Comment Supporting Petition for Rulemaking PRM-50-58 Re VEPCO Petition to Change Frequency of Emergency Planning Exercises from Annual to Biennial DD-92-08, Director'S Decision DD-92-08 Re Enforcement Actions to Be Taken Against Util Due to Allegations Presented by Gap. Petition Denied1992-11-25025 November 1992 Director'S Decision DD-92-08 Re Enforcement Actions to Be Taken Against Util Due to Allegations Presented by Gap. Petition Denied 1999-09-13
[Table view] Category:TRANSCRIPTS
MONTHYEARML20151S0961986-09-17017 September 1986 Transcript of 860917 Investigative Interview of J Piana in Detroit,Mi.Pp 1-38 ML20151S1011986-09-17017 September 1986 Partially Deleted Transcript of 860917 Investigative Interview W/W Hastings in Detroit,Mi.Pp 1-63 ML20151S1251986-09-17017 September 1986 Transcript of 860917 Investigative Interview of J Pipis in Detroit,Mi.Pp 1-46 ML20151S2631986-09-17017 September 1986 Transcript of 860917 Investigative Interview of C Cody in Detroit,Mi.Pp 1-42 ML20151S2131986-08-13013 August 1986 Partially Withheld Transcript of 860813 Investigative Interview W/S Thompson in Monroe,Mi.Pp 1-33 ML20202C7951986-07-0707 July 1986 Transcript of 860707 Discussion/Possible Vote on Restart in Washington,Dc.Pp 1-93.Viewgraphs Encl ML20141P0011986-03-12012 March 1986 Transcript of Commission 860312 Briefing in Washington,Dc Re Status of Fermi.Pp 1-74.Supporting Documentation Encl ML20237K3451985-10-0303 October 1985 Partially Deleted Statement of Me Parker on 851003 Re 850702 Reactor Operator Error at Plant ML20237K1751985-09-26026 September 1985 Transcript of 850926 Investigative Interview of Jp Thorpe in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237K2901985-09-26026 September 1985 Transcript of 850926 Investigative Interview of ML Batch in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237K3041985-09-26026 September 1985 Transcript of 850926 Investigative Interview of Wf Colbert in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237J9481985-09-26026 September 1985 Partially Deleted Transcript of Investigative Interview W/ J Flint on 850926 in Newport,Mi ML20237K2181985-08-20020 August 1985 Transcript of 850820 Investigative Interview of G Overbeck in Newport,Mi Re 850702 Reactor Operator Error at Plant. Pp 1-32 ML20237K2381985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview of L Lessor in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-28 ML20237K2501985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-18 ML20237K1991985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview of R Lenart in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-19 ML20237J9911985-08-20020 August 1985 Partially Deleted Transcript of Investigative Interview of E Preston in Newport,Mi.Pp 1-26 ML20237J9731985-07-31031 July 1985 Partially Deleted Ofc of Investigations Investigative Interview (Closed Meeting) W/S Burt on 850731 in Newport,Mi ML20237J9111985-07-31031 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/E Duda on 850731 in Newport,Mi ML20237J8391985-07-31031 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/B Myers on 850731 in Newport,Mi ML20237J8101985-07-31031 July 1985 Partially Deleted Transcipt of Ofc of Investigation Investigative Interview (Closed Meeting) W/J Dewes on 850731 in Newport,Mi ML20237J9791985-07-30030 July 1985 Transcript of Ofc of Investigations Investigative Interview of E Preston on 850730 in Newport,Mi ML20237J9201985-07-30030 July 1985 Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/T Dong on 850730 in Newport,Mi ML20237J7971985-07-30030 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) on 850730 in Newport,Mi ML20237K1931985-07-23023 July 1985 Transcript of Ofc of Investigations Investigative Interview of Rs Lenart on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-23 ML20237J8481985-07-23023 July 1985 Partially Deleted Trancript of Ofc of Investigations Investigative Interview W/D Aniol on 850723 in Glen Ellyn, Il.Pp 1-35 ML20237K2121985-07-23023 July 1985 Transcript of Ofc in Investigations Investigative Interview of G Overbeck on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-41 ML20237J5421985-07-23023 July 1985 Partially Deleted Transcript of Ofc of Investigations Investigative Interview of G Overbeck on 850723 in Glen Ellyn,Il Re Reactor Operator Error on 850702 ML20237K2261985-07-23023 July 1985 Partially Deleted Transcript of Ofc of Investigations Investigative Interview of LC Lessor on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-23 ML20237K2631985-07-23023 July 1985 Transcript of Ofc of Investigations Investigative Interview of Wh Jens on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-21 ML20129J4741985-07-10010 July 1985 Transcript of 850710 Discussion/Possible Vote in Washington, DC on Full Power OL for Facility.Pp 1-95.Supporting Documentation Encl ML20054C6281982-04-19019 April 1982 Proposed Corrections to 781218 & 810722 Prehearing Conferences & 820331-0402 Hearing Transcripts.Certificate of Svc Encl ML20041E2831982-03-31031 March 1982 Testimony of F Kuron on Contentions 4(a),(b),(c),(d) & (E) & 7 Re QA & Stoney Pointe Area Evacuation Route.Certificate of Svc Encl.Related Correspondence ML20049H5901982-03-31031 March 1982 Testimony of Sh Leach Re Contention 4(a) on Security at Plant.Prof Qualifications Encl ML20049H5911982-03-31031 March 1982 Testimony of Ta Alessi Re Contentions 4(b)(c) &(E).Qa Program Effectively Implanted & Prescribed Insps Instrumental in Finding Deficiencies Subsequently Documented.Prof Qualifications Encl ML20049H5921982-03-31031 March 1982 Testimony of Wj Fahrner Re Contention 4(d).Actions Taken to Establish Better Const Mgt Were in Util Best Interests & Were Not Results of Util Efforts to Compromise Qa.Prof Qualifications Encl ML20049H5941982-03-31031 March 1982 Testimony of Ef Madsen Re Contention 8 Re Feasible Escape Route for Stoney Point Area.Present Road Sys Adequate to Evacuate Residents on Timely Basis.Prof Qualifications Encl ML20009G5661981-07-24024 July 1981 Testimony of Tm Mckelvey at ACRS 810724 Subcommittee Meeting in Washington,Dc to Discuss Facility Electrical Sys, Including Station Blackout.Pp 192-210.Diagrams Encl ML19345G8661980-10-31031 October 1980 Testimony of Hc Bhatia (PSC of Mi) Filed 800430 Before PSC of Mi.Exhibits Encl ML19345G8681980-10-31031 October 1980 Testimony of Tq Smith (PSC of Mi) Filed 800430 Before PSC of Mi.Util Historical Data & Analysis of Revenue Deficiency for Forecasted 1981 Test Yr Encl ML19345G8691980-10-31031 October 1980 Testimony of Gr Stojic (PSC of Mi) Filed 800430 Before PSC of Mi.Exhibits Re Capital Structure & Costs,Related Financial Data & Rate of Return Encl ML19345G8651980-04-30030 April 1980 Testimony by E Grove,Cf Loeher,Jl Welch,C Tinker, R Viinikainen,J Mcgillivary & LS Reis (Detroit Edison Co) on 800430 Re Util Application for Authority to Amend Rate Schedule ML20148A8371978-12-18018 December 1978 Transcript of a Morning 781218 Hearing in Detroit Mi Re Subj facil.Pp.1-179 1986-09-17
[Table view] Category:DEPOSITIONS
MONTHYEARML20151S0961986-09-17017 September 1986 Transcript of 860917 Investigative Interview of J Piana in Detroit,Mi.Pp 1-38 ML20151S1011986-09-17017 September 1986 Partially Deleted Transcript of 860917 Investigative Interview W/W Hastings in Detroit,Mi.Pp 1-63 ML20151S1251986-09-17017 September 1986 Transcript of 860917 Investigative Interview of J Pipis in Detroit,Mi.Pp 1-46 ML20151S2631986-09-17017 September 1986 Transcript of 860917 Investigative Interview of C Cody in Detroit,Mi.Pp 1-42 ML20151S2131986-08-13013 August 1986 Partially Withheld Transcript of 860813 Investigative Interview W/S Thompson in Monroe,Mi.Pp 1-33 ML20202C7951986-07-0707 July 1986 Transcript of 860707 Discussion/Possible Vote on Restart in Washington,Dc.Pp 1-93.Viewgraphs Encl ML20141P0011986-03-12012 March 1986 Transcript of Commission 860312 Briefing in Washington,Dc Re Status of Fermi.Pp 1-74.Supporting Documentation Encl ML20237K3451985-10-0303 October 1985 Partially Deleted Statement of Me Parker on 851003 Re 850702 Reactor Operator Error at Plant ML20237K1751985-09-26026 September 1985 Transcript of 850926 Investigative Interview of Jp Thorpe in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237K2901985-09-26026 September 1985 Transcript of 850926 Investigative Interview of ML Batch in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237K3041985-09-26026 September 1985 Transcript of 850926 Investigative Interview of Wf Colbert in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237J9481985-09-26026 September 1985 Partially Deleted Transcript of Investigative Interview W/ J Flint on 850926 in Newport,Mi ML20237K2181985-08-20020 August 1985 Transcript of 850820 Investigative Interview of G Overbeck in Newport,Mi Re 850702 Reactor Operator Error at Plant. Pp 1-32 ML20237K2381985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview of L Lessor in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-28 ML20237K2501985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-18 ML20237K1991985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview of R Lenart in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-19 ML20237J9911985-08-20020 August 1985 Partially Deleted Transcript of Investigative Interview of E Preston in Newport,Mi.Pp 1-26 ML20237J9731985-07-31031 July 1985 Partially Deleted Ofc of Investigations Investigative Interview (Closed Meeting) W/S Burt on 850731 in Newport,Mi ML20237J9111985-07-31031 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/E Duda on 850731 in Newport,Mi ML20237J8391985-07-31031 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/B Myers on 850731 in Newport,Mi ML20237J8101985-07-31031 July 1985 Partially Deleted Transcipt of Ofc of Investigation Investigative Interview (Closed Meeting) W/J Dewes on 850731 in Newport,Mi ML20237J9791985-07-30030 July 1985 Transcript of Ofc of Investigations Investigative Interview of E Preston on 850730 in Newport,Mi ML20237J9201985-07-30030 July 1985 Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/T Dong on 850730 in Newport,Mi ML20237J7971985-07-30030 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) on 850730 in Newport,Mi ML20237K1931985-07-23023 July 1985 Transcript of Ofc of Investigations Investigative Interview of Rs Lenart on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-23 ML20237J8481985-07-23023 July 1985 Partially Deleted Trancript of Ofc of Investigations Investigative Interview W/D Aniol on 850723 in Glen Ellyn, Il.Pp 1-35 ML20237K2121985-07-23023 July 1985 Transcript of Ofc in Investigations Investigative Interview of G Overbeck on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-41 ML20237J5421985-07-23023 July 1985 Partially Deleted Transcript of Ofc of Investigations Investigative Interview of G Overbeck on 850723 in Glen Ellyn,Il Re Reactor Operator Error on 850702 ML20237K2261985-07-23023 July 1985 Partially Deleted Transcript of Ofc of Investigations Investigative Interview of LC Lessor on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-23 ML20237K2631985-07-23023 July 1985 Transcript of Ofc of Investigations Investigative Interview of Wh Jens on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-21 ML20129J4741985-07-10010 July 1985 Transcript of 850710 Discussion/Possible Vote in Washington, DC on Full Power OL for Facility.Pp 1-95.Supporting Documentation Encl ML20054C6281982-04-19019 April 1982 Proposed Corrections to 781218 & 810722 Prehearing Conferences & 820331-0402 Hearing Transcripts.Certificate of Svc Encl ML20041E2831982-03-31031 March 1982 Testimony of F Kuron on Contentions 4(a),(b),(c),(d) & (E) & 7 Re QA & Stoney Pointe Area Evacuation Route.Certificate of Svc Encl.Related Correspondence ML20049H5901982-03-31031 March 1982 Testimony of Sh Leach Re Contention 4(a) on Security at Plant.Prof Qualifications Encl ML20049H5911982-03-31031 March 1982 Testimony of Ta Alessi Re Contentions 4(b)(c) &(E).Qa Program Effectively Implanted & Prescribed Insps Instrumental in Finding Deficiencies Subsequently Documented.Prof Qualifications Encl ML20049H5921982-03-31031 March 1982 Testimony of Wj Fahrner Re Contention 4(d).Actions Taken to Establish Better Const Mgt Were in Util Best Interests & Were Not Results of Util Efforts to Compromise Qa.Prof Qualifications Encl ML20049H5941982-03-31031 March 1982 Testimony of Ef Madsen Re Contention 8 Re Feasible Escape Route for Stoney Point Area.Present Road Sys Adequate to Evacuate Residents on Timely Basis.Prof Qualifications Encl ML20009G5661981-07-24024 July 1981 Testimony of Tm Mckelvey at ACRS 810724 Subcommittee Meeting in Washington,Dc to Discuss Facility Electrical Sys, Including Station Blackout.Pp 192-210.Diagrams Encl ML19345G8661980-10-31031 October 1980 Testimony of Hc Bhatia (PSC of Mi) Filed 800430 Before PSC of Mi.Exhibits Encl ML19345G8681980-10-31031 October 1980 Testimony of Tq Smith (PSC of Mi) Filed 800430 Before PSC of Mi.Util Historical Data & Analysis of Revenue Deficiency for Forecasted 1981 Test Yr Encl ML19345G8691980-10-31031 October 1980 Testimony of Gr Stojic (PSC of Mi) Filed 800430 Before PSC of Mi.Exhibits Re Capital Structure & Costs,Related Financial Data & Rate of Return Encl ML19345G8651980-04-30030 April 1980 Testimony by E Grove,Cf Loeher,Jl Welch,C Tinker, R Viinikainen,J Mcgillivary & LS Reis (Detroit Edison Co) on 800430 Re Util Application for Authority to Amend Rate Schedule ML20148A8371978-12-18018 December 1978 Transcript of a Morning 781218 Hearing in Detroit Mi Re Subj facil.Pp.1-179 1986-09-17
[Table view] Category:NARRATIVE TESTIMONY
MONTHYEARML20151S0961986-09-17017 September 1986 Transcript of 860917 Investigative Interview of J Piana in Detroit,Mi.Pp 1-38 ML20151S1011986-09-17017 September 1986 Partially Deleted Transcript of 860917 Investigative Interview W/W Hastings in Detroit,Mi.Pp 1-63 ML20151S1251986-09-17017 September 1986 Transcript of 860917 Investigative Interview of J Pipis in Detroit,Mi.Pp 1-46 ML20151S2631986-09-17017 September 1986 Transcript of 860917 Investigative Interview of C Cody in Detroit,Mi.Pp 1-42 ML20151S2131986-08-13013 August 1986 Partially Withheld Transcript of 860813 Investigative Interview W/S Thompson in Monroe,Mi.Pp 1-33 ML20202C7951986-07-0707 July 1986 Transcript of 860707 Discussion/Possible Vote on Restart in Washington,Dc.Pp 1-93.Viewgraphs Encl ML20141P0011986-03-12012 March 1986 Transcript of Commission 860312 Briefing in Washington,Dc Re Status of Fermi.Pp 1-74.Supporting Documentation Encl ML20237K3451985-10-0303 October 1985 Partially Deleted Statement of Me Parker on 851003 Re 850702 Reactor Operator Error at Plant ML20237K1751985-09-26026 September 1985 Transcript of 850926 Investigative Interview of Jp Thorpe in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237K2901985-09-26026 September 1985 Transcript of 850926 Investigative Interview of ML Batch in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237K3041985-09-26026 September 1985 Transcript of 850926 Investigative Interview of Wf Colbert in Newport,Mi Re 850702 Reactor Operator Error at Plant ML20237J9481985-09-26026 September 1985 Partially Deleted Transcript of Investigative Interview W/ J Flint on 850926 in Newport,Mi ML20237K2181985-08-20020 August 1985 Transcript of 850820 Investigative Interview of G Overbeck in Newport,Mi Re 850702 Reactor Operator Error at Plant. Pp 1-32 ML20237K2381985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview of L Lessor in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-28 ML20237K2501985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-18 ML20237K1991985-08-20020 August 1985 Partially Deleted Transcript of 850820 Investigative Interview of R Lenart in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-19 ML20237J9911985-08-20020 August 1985 Partially Deleted Transcript of Investigative Interview of E Preston in Newport,Mi.Pp 1-26 ML20237J9731985-07-31031 July 1985 Partially Deleted Ofc of Investigations Investigative Interview (Closed Meeting) W/S Burt on 850731 in Newport,Mi ML20237J9111985-07-31031 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/E Duda on 850731 in Newport,Mi ML20237J8391985-07-31031 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/B Myers on 850731 in Newport,Mi ML20237J8101985-07-31031 July 1985 Partially Deleted Transcipt of Ofc of Investigation Investigative Interview (Closed Meeting) W/J Dewes on 850731 in Newport,Mi ML20237J9791985-07-30030 July 1985 Transcript of Ofc of Investigations Investigative Interview of E Preston on 850730 in Newport,Mi ML20237J9201985-07-30030 July 1985 Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/T Dong on 850730 in Newport,Mi ML20237J7971985-07-30030 July 1985 Partially Deleted Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) on 850730 in Newport,Mi ML20237K1931985-07-23023 July 1985 Transcript of Ofc of Investigations Investigative Interview of Rs Lenart on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-23 ML20237J8481985-07-23023 July 1985 Partially Deleted Trancript of Ofc of Investigations Investigative Interview W/D Aniol on 850723 in Glen Ellyn, Il.Pp 1-35 ML20237K2121985-07-23023 July 1985 Transcript of Ofc in Investigations Investigative Interview of G Overbeck on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-41 ML20237J5421985-07-23023 July 1985 Partially Deleted Transcript of Ofc of Investigations Investigative Interview of G Overbeck on 850723 in Glen Ellyn,Il Re Reactor Operator Error on 850702 ML20237K2261985-07-23023 July 1985 Partially Deleted Transcript of Ofc of Investigations Investigative Interview of LC Lessor on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-23 ML20237K2631985-07-23023 July 1985 Transcript of Ofc of Investigations Investigative Interview of Wh Jens on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-21 ML20129J4741985-07-10010 July 1985 Transcript of 850710 Discussion/Possible Vote in Washington, DC on Full Power OL for Facility.Pp 1-95.Supporting Documentation Encl ML20054C6281982-04-19019 April 1982 Proposed Corrections to 781218 & 810722 Prehearing Conferences & 820331-0402 Hearing Transcripts.Certificate of Svc Encl ML20041E2831982-03-31031 March 1982 Testimony of F Kuron on Contentions 4(a),(b),(c),(d) & (E) & 7 Re QA & Stoney Pointe Area Evacuation Route.Certificate of Svc Encl.Related Correspondence ML20049H5901982-03-31031 March 1982 Testimony of Sh Leach Re Contention 4(a) on Security at Plant.Prof Qualifications Encl ML20049H5911982-03-31031 March 1982 Testimony of Ta Alessi Re Contentions 4(b)(c) &(E).Qa Program Effectively Implanted & Prescribed Insps Instrumental in Finding Deficiencies Subsequently Documented.Prof Qualifications Encl ML20049H5921982-03-31031 March 1982 Testimony of Wj Fahrner Re Contention 4(d).Actions Taken to Establish Better Const Mgt Were in Util Best Interests & Were Not Results of Util Efforts to Compromise Qa.Prof Qualifications Encl ML20049H5941982-03-31031 March 1982 Testimony of Ef Madsen Re Contention 8 Re Feasible Escape Route for Stoney Point Area.Present Road Sys Adequate to Evacuate Residents on Timely Basis.Prof Qualifications Encl ML20009G5661981-07-24024 July 1981 Testimony of Tm Mckelvey at ACRS 810724 Subcommittee Meeting in Washington,Dc to Discuss Facility Electrical Sys, Including Station Blackout.Pp 192-210.Diagrams Encl ML19345G8661980-10-31031 October 1980 Testimony of Hc Bhatia (PSC of Mi) Filed 800430 Before PSC of Mi.Exhibits Encl ML19345G8681980-10-31031 October 1980 Testimony of Tq Smith (PSC of Mi) Filed 800430 Before PSC of Mi.Util Historical Data & Analysis of Revenue Deficiency for Forecasted 1981 Test Yr Encl ML19345G8691980-10-31031 October 1980 Testimony of Gr Stojic (PSC of Mi) Filed 800430 Before PSC of Mi.Exhibits Re Capital Structure & Costs,Related Financial Data & Rate of Return Encl ML19345G8651980-04-30030 April 1980 Testimony by E Grove,Cf Loeher,Jl Welch,C Tinker, R Viinikainen,J Mcgillivary & LS Reis (Detroit Edison Co) on 800430 Re Util Application for Authority to Amend Rate Schedule ML20148A8371978-12-18018 December 1978 Transcript of a Morning 781218 Hearing in Detroit Mi Re Subj facil.Pp.1-179 1986-09-17
[Table view] |
Text
= -
OR G NAL . !
U.N ntu STATES NUCLEAR REGULATORY COMMISSION j 1
\ ?
l IN DE MATTER OF: DOCKET NO:
L8 214 ,
0FFICE OF INVESTIGATION .
l INVESTIGATIVE INTERVIEW 1 J
.. \
(CLOSED MEETING) .
LOCADON: NEWPORT, MICHIGAN PAGES: 126 DATE: WEDNESDAY,-JULY 31, 1985 in' formation in this d ofrecord Information was delet in accordance wit {th I fe';'[MEr ,
ace-FEDEFiREPORTERS, INC. I OfficktReportm I 444 North CyitolStres )'
Washington, D.C.20001 (2d'2) 347-3700 F; j
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NATICNWEE COVERACE l
g e2 g 4 e70e19 j fUNTENNB6-24S PDR DotA6s36e -_. _____-_ _ _ - _ a
1
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i
, UNITED STATES OF AMERICA
)
2 NUCLEAR REGULATORY COMMISSION 1
3
______________ i 4 l In the Matter of:
)
. ) Case No. LB-85-214 5 OFFICE OF INVESTIGATION )
INVESTIGATIVE INTERVIEW )
6
) )
J 7
The Deposition of EDWARD DUDA, taken pursuant to Notice before me, Elizabeth Diann Ferguson, Notary 9 j Public in and for the County of Wayne (acting in Monroe County), I 10 !
lat6400DixieHighway, Newport, Michigan,onWednesday, July 31, 11 j j1985, commencing at about 10:05 a.m.
12 p .
I3 APPEARANCES:
l UNITED STATES NUCLEAR REGULATORY COMMISSION l i Field Office Region III I
'S '
799 Roosevelt' Road l Glen Ellyn, Illinois 60137 16 ! (By: James N. Kalkman, Esq.) ,
- i
'7 8
! Appearing on behalf of the Nucinar Regulatory Commission
! l 1 y
'8 ' JOHN H. FLYNN, ESQ.
i 5
! 2000 Secon9 Avenue
- '9 h Detroit, Michigan 48226 i ll 20 l 0 Appearing on behalf of Detroit Edison I
- 21 h i ,
22 ' ,
i 23 2'
(continuing)
I i 25 I J l
l 1
i l
l l
q 3 APPEARANCES: (continued)
! i PETER A. MARQUARDT, ESO. ':
2 2000 Seoond Avenue 1 Detroit, Michigan 48226 l 3
4 Appearing on behalf of Detroit Edison t j
1 5
6 ALSO PRESENT:
7 Terrence Land and Thomas Randazzo 8 - . .
9 l
l to f I l 33 l Elizabeth Diann Ferguson, CSR-1347 i Court Reporter 12 i!
c 13
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2 pag, Witness 3 Edward Duda
- Examination by Mr. Kalkman 5 ,
)
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l 9 l 1l 10 11 12 il
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i 22 l 23 1 24 !
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3
Newport, Michigan.
3 Wednes' day, July 31, 1985 2
at about 10:05 a.m.
3 MR. KALKMAN For the record, this is 5
6 the interview of Edward Duda, D-u-d-a,.who-is employed by 7 the Detroit Edison Company. The location of this 8 interview is the Fermi II Nuclear Power Station.
g Present.at this interview are 10 Mr. Duda, Detroit Edison Counsels, Peter Marquardt and 11 John Flynn; NRC Reactor Inspector, Terrence Lang, and 12 NRC Investigator, James Kalkman.
l i
I 33 !, As agreed this interview is being 34 li transcribed by the Court Reporter Elizabeth Ferguson.
U 3s The subject matter of this interview c
16 f concerns a reactor operator error that occurred on l 37 July 1, 1985, at the Fermi II Nuclear Power Station.
., 18 Mr. Duda, will you please stand and 39 raise your right hand?
I li - - -
! 20 11 '
a EDWARD DUDA,
! 21 l i i
- I after having first been duly sworn to tell the truth, 22 23 the whole truth and nothing but the truth, testified 24 upon his oath as follows:
2s 1 4
--______________.,_______.____._____.]
W EXAMINATION 1
l BY MR. KALKMAN:
2 i
O Sir, did you --
3 MR. MARQUARDT I think you ought to l correct the record, James, and perhaps ask him whether he 5
is employed by Detroit Edison Company, f 6
A Yes, that would probably be a good idea.
7 l
8 g BY MR. KALEMAN:
,g O Are you amployed by Detroit Edison?
3, A No, I am not. I am a contractor.
Q Y u are e ntracted to Edison through who?
12 A R.T.S.
13 i
! ,, j Q And that stands for what? j l l l
A Resource Tt::hnical Services; and I am employed by myself ,
35 33 my own company.
- [ 37 0 You are a sub-contractor?
't jg A Right.
'i*
3g MR. MARQUARDT We just want to keep the record straight.
20
~ ~ ~
f 21
'r i BY MR. KALKMAN:
22 0 What is your function at the Fermi Plant as a contractor, 23 as a contract employee?
24 A My j b is the shift operations advisor.
25 5
1 O And what are your responsibilities? ;
,- A Well, as I know it, my responsibilities are, that to the 3 best of my ability and experience, that I help the 4 operations group maintain safe and proper operations and 5 are accurate.
6 Q What is your experience in nuclear operations?
7 A Well, I have a Bachelor's and Science Degree in Nuclear e Engineering; senior reactor operator's license Unit I; t
9 and I was subsequently licensed here as senice reactor ;
i Ic operator, licensed here. j I have done reactor engineering work 11
)
12 at the Nine Mile, and I was assistant shift supervisor j 13 l there. ,
14 Is the Nine Mile Point a boiling reactor unit? l Q
l 15 iA Yes.
1 i
1E i O Is it similar to the Fermi Plant as far as generation of a
l6 17 boiling water reactor? J h I 4
18 A Yes.
- 19 0 Is it a GE reactor?
II i 5 20 l A Yes. )
!!=
i
[ 21 MR. LANG: Unit four? a 4 J 22 A No.
l 23 MR. LANG: What is Nine Mile? I l
24 A Two. ;
n 5
~ ~ ~
l M ! l 3
l 6 l t
i
__ _- --__ A
i l
. i
]
1 BY MR. KALKMAN: 1 1
2 0 .You were present on the shift on the evening of July 1, j i i 3 1985, when the reactor operator erred in the sequence pull, J l
l 4 the rod pull sequence, correct?
5 A Yes.
6 Could you describe for us what you recall of that incident, 1
Q 1
7 when you became aware of the incident, and any functions I l
8 you performed in resulting from that rod pull error? i I,
9 A Well, on the first that I knew of it, the reactor operator I 10 at the 603 panel was saying to someone who I don't know, )
11 who he was talking to, that it was out-of-sequence. l I
12 I was standing next to the STA and -- !
I 1
13 Q Is that Mr. Dong? I l l l
14 gA Ye s , Mr . Dong .
15 We decided that the rod-worth-minimizer 16 should have caught our problem. l l
i 17 Following up on that, we decided to I
18 find out why the rod-wortheminimizer did not catch our
{a
- 19 problem.
3 j 20 0 Okay.
- l 21 A Mr. Dong, I eventually found out, minutes afterwards, had t
22 talked to the reactor engineer on the shift and found out 23 that the rod-worth-minimizer is not programmed to catch 24 our reduced notch-worth pulls; and we discussed that for 25 some short period of tbme.
7
1 That was pretty much the extent of our 2 l involvement in the situation. l 3
O So you were standing near the 603 panel when the event i .
l occurred?
5 A Probably about eight feet away.
6 Q And you heard -- who did you overhear --
A The operator at the 603 panel, e
u /
Q He was telling someone that you are not sure who it was?
8 A Right.
'O 1 Q That he was out-of-sequ.ence? ,
l
l A That is correct. l l
12 O Did you observe the shift supervisor?
'3 A At Which time?
'# i Q Enter the Control Room area of the 603 panel? j ;
'6 A I did not myself observe him come into the area, if that i
'6 1 l is what you mean.
- l 3 " 1
. Q Yes.
t l
'8 h
3 A I saw him once he was in there, yes, I guess is the i
- '9 <
!) answer to that question. I i 1 !
j 20 MR. LANG: Did you ever observe the f
p 21 ,
e, shift supervisor roll back the charts, the SRM charts? ,
22 fA Nc, I did not. '
23 t I cannot say that he did or did not.
24 '
MR. LANG: So you are saying that the 25 first time you were aware of it was af ter they pulled the
/
1
- j 1
1 rods and inserted in or as they were -- ;
2 A No, I cannot really say when it was.
3 I believe it was sometime -- I know d it was sometime after they found he was out-of-sequence 5 because he was saying that he was in the evolution. It i 6 was like -- l 7 MR. LANG: Did he say that directly 8 to you?
9 A No. As I just stated, it was --
10 -MR. LANG: Did the shift-supervisor 11 get you involved in,the situation, or did you just choose 12 to work on the rod-worth-minimizer? l I
s' 13 l A Well, usually when this is a situation like this and there
'd i! is a problem, we try to work on' what you are able to 0
15 ; at the moment.
16 When it happened, the shift supervisor 17 was not right at the panel, so he did not try to get me l
18 involved with anything, g
s
- 19 . . .
i 20 BY MR. KALKMAN:
l l 21 What is the difference between your function in the i t lQ 22 control Room and, say, the STA?
23 A Well, I guess it is just what the name implies. The STA 24 is there for technical advise; and the operations advisor, i
25 the shift operations advisor is there for operations advice.
9
. 1 j
The actual function is pretty similar. ]
3
)
2 They are both advisory roles. J l
I MR. LANG - As far as you can tell us 3
on the shif t at night, were .you ever aware of the SRM l charts being increasing? l 5 i i
6 A No.
MR. LANG: Were you aware of the out-7 g
of-sequence -- what does that mean to you, essentially?
g A To me, it means that the rods are not being pulled in accordance with the pull sheets.
to MR. LANG: Were you aware of the number of rods that he had pulled out-of-sequence? l 12 13 A No.
MR. LANG: How do you function with 9
the shift organization? ;
5 ..
I am having a tough time. j 16 1 l
- n Do you take your orders directly from f f
I* the shif t supervisor or --
. 18 I*
39 My orders, could you --
- [l A Your directions or any l MR. LANG:
20 n
- 21 l requests for assistance?
- A well, if the shift supervisor directly reauests my 22 23 attention, I definitely get involved with the situation.
Other than that, it is pretty much 24 25 lef t up to,the individual advisor to get involved as ha 10
3 feels necessary, MR. LANG ' Were you requested to get 2
3 involved?
4 A No. '
5 s BY MR. KALKMAN: ;
7 Q Do you keep a log of your activities?
A Unofficially, yes. )
8 9 0 Do you have an unofficial log for the event of July 17 )
A Yes. l 10 u MR. LANG: Did you mention the out-of- '
l 12 sequence in the 1997 13 ! A No, I did not.
I 14 i
MR. LANG: Do you have a reason why you 15 did not?
16 A Well, it did not seem important for me from other events I
s 17 of the night.
I' MR. LANG: So you were, I take it,
., is
- 19 investigating what you perceived to be the failure of the t
20 rod-worth-minimizer?
l .
21 A Yes, t
- MR. LANG: Did you log it in the log?
22 23 A No.
24 25 11
1 BY MR. KALKMAN:
2 0 What did you log that evening?
3 A The only thing I remember logging is the reactor when 4 we finally pulled in the correct sequence and the reactor 5 operator declared the reactor critical.
6 It was on the f airly long period of 7 time.
. e I did log in my log that period.
9 There were other things that I logged, but I don't. recall i
10 them offhand. 1 11 0 Did you get involved in a water level fluctuation problem 12 that evening?
1 13 [A Yes.
I 14
!j Q Was this in your log?
15 A No.
16 Q What was the situation with the water level?
s i 17 A Basically as I remember it, the instrument was swinging I
'. 18 up and down and I believe at one time we got -- it may l even have been a low-level trip from that instrument.
- 19 l
i j 20 l'l 0 What was the cause of --
21 A No cause.
I' 22 It was no cause. No cause was found 23 that I know of.
24 MR. LANG: Discussions involving the 25 rod-worth-minimizer, when you started investigating what 12
1 l
e i
1 you perceived to be the failur'e, did you make any
(
2- recommendations as to the operability of the rod-worth- ]
(
3 minimizer to the shift supervisor?
A No, because before I ever saw the shif t supervisor, we 5 had the word inom the reactor engineer on the shift that 6 the rod-worth-minimizer was not programmed to do this..
7 In your experience at MR. LANG:
8 Nine Mile, would the rod-worth-minimiser had blocked on 9 I that same circumstance?
10 y,,,
A il MR, LANG: .If at'Nine Mile a reactor 12 engineer told you it would not block, would you have
' declared the rod-worth-minimizer inoperable? j l
- A Well, that is a very hypothetical point, and one that is <
15 I sort of academic since our rod-worth-minimizer was l 16 required to be operable except the first --
' MR. LANG: At Nine Mile? l t* l 18 ygg,ggy,,
i 3
- 19 It makes it sort of a --
,I '
'i 20 MR.'LANG: I guess the point I am 21 trying to get at is when the reactor engineer told you l
22 that the rod-worth-minimizer would not block --
23 A The STA.
24 The STA in training or --
MR. LANG:
25 A No, the STA.
13
MR. LANG: Tom Dong?
i l
2 A Tom Dong.
3 MR. LANG: Okay.
1 4 Tom Dong, did you assume he was correct !
l 5 automatically? Did you question his statement? !
1
.1
~
6 A Well, we did discuss it.
7 Whether I actually asked him, "Are 1
8 you sure?" I don't remember that. l 1
l 9 I did not feel at the time that it l
'l' 10 would be a big, you know, event; so I don't remember my 11 axact words to him, or exactly what we discussed.
l 12 ,! It was not a quick, "It won't block o
13 i you, okay, we will see you," it was -- what-exactly we 14 said, we said -- it was something. What exactly we said,
!i I am not sure, j 15 q 16 MR. LANG: Other than the conversation i 17 you had with the STA, did you have any other conversations l 1
'. 18 with the shift supervisor or the RO or anyone?
- 19 A During the event?
i j 20 MR. LANG: During the whole shift.
! 21 A During the whole shift, yes. .
I
- MR. LANG: Can you paraphrase or -- f 22 i
23 A one conversation I do remember was that the ho at the 603 f I
24 panel, when we went critical in sequence, I remember !
I 25 someone saying something to him about it being a slow j 14 l
l i
'l 1
]
1 period, and I felt it was kind of slow myself. ;
l .
2 He asked me whether it was all right !
3 and I said to him, do you feel comfortable with it?"
~ /
4 And he said yes. And I said, then, it is a good period.
1 5 That is pretty much the extent of it. );
I 6 MR. LANG: You must have been talking I f ' f 7 to puring the second Plant criticality? I L ; l 8 A Yes. )
9 MR. LANG: Did you do any discussions j to of this order in the first one?
1 11 A No.
12 MR. LANG: When were you actually 13 i aware of the criticality, the first one?
14 A Are we assuming that we were critical?
15 MR. LANG: Well, what do you assume?
16 Were you or were you not?
i 17 A well, can I have a definition on it?
I l 18 KR. LANG: Well, use your own I
{
- 19 definition.
l i l[ 20 A Well, if we are arguing whether K effectively equals one or l 21 not, possibly; but if we are arguing whether or not the r
22 Plant had time to declare the reactor critical per the r 23 definition that was in the procedure, nog he did not.
24 MR. LANG: So the first time that you ,
25 saw the actual SRM charts -- and I am not even sure whether 6i16 '
. I l
I i that was -- did you assume you were critical or not, 1 I based on your own judgment, whatever method of criticality i
J you want to use?
d Well, we were not. ,
A i 5 MR. LANG: You were not critical?
6 g go, 7 MR. LANG: When was the first time 8 you saw the charts?
9 A On the next shift the next night, my next midnight shift. !
10 I would come in on the second.
11 MR. LANG: Ware there any discussions .
1 12 ! during the event of the shift or shortly thereafter where h
13 maybe three or four of you were involved with the shift !
supervisor?
[
15 A I don't remember if there were any.
16 . . .
2
' 17 BY MR. KALKMAN i I.
j 18 Q Did Mr. Aniol ask you if you had logged the out-of-sequence
- 19 pull event?
i l j 20 g yo, 21 MR. LANG: Did he discuss it with you?
i 22 The out-of-sequence pull event?
A 23 MR. LANG: Yes.
24 A Like I said, if he did, I don't remember.
25 MR. LANG: Did he come to you and say 16
A
'this is what occurred? i I
I A Not that I remember.
3 . . .
l BY MR. KALKMAN:
5 0 Was there any analysis performed after the rods were l
i 6 re-inserted on any review on your part of the reactor i 7 before the okay was given to re-pull the rods in sequence?
8 A Well, about the first part, analysis, what type of ,
9 analysis?
10 Q From the type of rods.
11 A Well, you don't mean --
12 Q The out-of-sequence rods were re-inserted, the time" 13 between that period and when the approval was given to ,
i*
re-pull the rods in sequence, did you have any involvement 15 in any analysis if whether the Plant was -- if there was 16 any damage to the fuel or any Corp or anything?
17 3
A I do not remember my exact discussions during that period i
g 18 of time, but I would imagine that I was talking to someone s
- 19 about the event, s
20 l I know I was talking with the STA,
- 21 Tom Dong. I cannot imagine talking about something else t
22 at the time; so I guess I would have to say there probably 23 was some sort of talk about it.
2d O I am not asking about any discussion, I an asking you if 25 you did anything, if you reviewed any procedure or did 17
l' l .
i i
i 1 anything to make a determination if it was okay to re-2 start the Plant.
3 Do you have any functional repsonsibiliy 4 to check anything?
l 5 A Did I do any analysis to determine whether it was --
6 Q Whether the out-of-sequence pull had caused any damage 7
or -- !
8 A It is my experience that this kind of event would not have 9 caused the damage.
1 10 I don't know at the time whether I 1
11 had analysed it that extent or not.
12 MR. LANG: Was your opinion even i
13 requested prior to the -- ;
[
I $
14 iA No. I i l 15 MR. LANG: Pr.ior to..the start-up again? l 16 A No. j
- l U MR. LANG: When you went home that l
18 next morning, the end of the shift --
g
- 19 A Can I continue on that last statement?
I j 20 l MR. LANG: Okay.
- 21 A It was not requested; however, had I felt it was warranted, t
22 I would have given it.
23 MR. LANG: Was it given that night?
24 A No.
2s - - -
18
' BY MR. KALKMAN:
2 Q You are probably the most experienced person on that 3 shif t, as f ar as operating a reactor, correct?
A Possibly, yes.
8 Q And during that whole period, that shif t that you were 6 not involved in an advisory capacity, I mean, were you 7 there as an advisor, but you were not asked to do any --
i 8 for any advice by the operationa people? )
l I
8 A That is not true.
'O I have already stated I was asked by q
when the reactor did eventually go critical
. 1
,2 1 in sequence.
13 You are saying the whole shif t?
O Okay.
'S That is just not true.
jA 16 Q Relating to the out of sequence pull, you were not asked f
' '7 to give any advice?
'8 No, not that I remember.
j A
- 19 MR. LANG
- During the course of a
! 20 typical shift, first of all, do you rotate with that shift?
21 g yo, E
22 MR. LANG: You are on a different shift?
23 A That is correct.
24 MR. LANG: IN the course of your shif t, 25 then, a typical shift, how much involvement do you get or 19 ,
/9 o b
i 1 request for assistance usually frors the shift supervisor, 2 typically?
3 A Typically, the shif t supervisor will discuss a few 4 test specs related questions; I am not sure that everytime l 5 ve get involved we have been asked to get involved.
6 That is obviously not chc case. ;
7 Mr. Lang, you have been on shift a yourself. Would you ask an advisor for help when you get 9 into a problem? That is pretty much when they do request 10 our assistance when they have a problem or they have a 11 test spec-related question or technical question that they bellave our experience can help them with.
12 .
I; 13 That, is not cut and dry when they 14 have to ask us, if that is what you are asking.
I 15 , MR. LANG: In your own opinion, do l
16 you feel like you have been fully utilized in your
=
l 17 experience, fully utilized to the best advantage?
t
- 18 A Well, that is sort of a leading question.
- 19 MR. LANG
- Well, I am an examiner.
T l 20 A Well, in my opinion, we have been told that any time ;
1
~
21 we don't agree with the shif t supervisor and we disagree l
22 etrongly enough or feel strongly enough about the issue, 23 we have been told by two individuals, Leo Lesser and i 24 Eugene Preston, that they are available any time for us l 25 to call them.
i 20 l
u i
3 There has not yet been a situation 2 where that has come to pass.
3 MR. LANG: Were you on shift -- I 4 un trying to get an idea of what you actually do on shift.
5 Do you follow the shift engineer?
6 A The shift engineer?
7 MR. LANG: The shift supervisor.
i 8 A Oh, okay.
9 MR. LANG: Do ycu follow him around to and watch his judgment call?
11 A No.
12 MR. LANG: So it is strictly up to him I
13 I as to -- as f ar as when he feels he needs your assistanen? ,
14 A That is pretty much true.
15 I wonid like to point out that it is 16 not only the shift supervisor that we give assistance to. l i 17 KR. LANG: Well, one other question: l l'
. 18 At the end of the shift, who do you ]
I
- 19 know was actually aware of the out-of-sequence rod pull 1
1 70 and how many rods -- I mean, who in your mind do you think l
21 actually knew there were 11 rods in this position?
22 A 23 MR. LANG: Well, let's talk actually 24 first.
25 A That I actually knew?
i
- 21
.. 1 MR. LANG: Yes. ]
J 2
A That is a hard question to answer since I did not know i 3 how many rods had been pulled out-of-sequence until the q
! following shift.
5 MR. LANG: Okay.
6 A It would be an opinion. It would not be an actual j statement.
8 MR. LANG: Well, in your opinion, l
then.
'U In my opinion, I Lalieva the shift -- at least the A
reactor operator pulled the rods, I believe knows most 2
i i
likely the SRO on shift, Dave Aniols the shift supervisor, 1 3 ' others would be guesses on my part, even in an opinion.
MR. LANG: All right. !
'5 . . . 1 BY MR. KALKMAN
" How many people knew of these out-of-sequence pulls? !
l Q 8
j A Actually, an opinion or --
I " Q No. .
]i 20 A My opinion?
l 21 O No, who do you know.
- f 22 A Who do I know knew about it?
23 g y,,,
t \
24 A The operator at the 603 panel, the STA in 25 training, John Dewes; the shif t supervisor, Dave Aniol: the
/
. l 3
STA, Tom Dong; and myself.
Q Did the reactor engineer, Barry Myers,did he know? J 2
3 A That would be an opinion. 1 i
4 I believe he did know about the out-At that time, I did not know whether or l 5 of-sequence.
6 not he knew about it.
7 O So you did not have any discussion with Mr. Myers?
l 8 A I did not personally, no.
MR. LANG: Did you overhear the 9
to discussion at all between the shif t supervisor and anyone 11 else in regards to whether or whether or not the thing 12 actually went critical?
13 A No.
14 I
15 BY MR. KAIJRAN :
16 Q Did you ever experience a rod pull incident, an out-of-i 17 sequence pull at the Nine Mile Point?
'l I 18 A Myself?
- 19 Q Yes.
- ) 20 A No. j
's !
21 Q Did they have an incident such as this occur at the Nine l!*
l j
22 Mile Point?
23 A Not that I am aware of.
24 Q Okay.
MR. LANG: As far as DECO goes, does 25 j
23 l
J DECO have a specific procedure or anything as far as how 2
to interface with a shift?
A WEll, it is -- in the shif t conduct -- the conduct of the 3
4 shift operations or --
1 MR. LANG: Is there anything more i 3 j 6
specific than that that just really says what your l I
J 7
responsibilities for the legal --
. g A There may be.
MR. LANG: As far as you know, there )
g 30 is no procedure that says that the shift should check with the SOA when certain types of events occur?
33 12 A Not that I know of.
I could be incorrect on that, though.
13 il ll l 34 l! MR. LANG: Okay. l 15 16 BY MR. KALKMAN:
l 37 0 would you say that this sequence pull event was a I- I ig significant event during the -- as far the particular i
19 shift goes?
. )
j 3 A well, you are going to have to clarify that statement.
3 I mean, was it physically a significant i 21 r
event? was it politically a significant event? j 22 1
What are we talking about? l 23 0 No, just how do you perceive that event? How did you at 24 the time or if you take into consideration everything tha*.
25 24 i l
. l
____ ___________-__-_ D
j occurred on that particular shift, forget about what has 3 l 2
happened since that shift, but in your own mind, that ]
I )
3 particular shift, was this sequence pull, this out-of 4
sequence pull a significant event? i I
A Not really. j 5 1 It was handled the way it should have 6
7 been handled.
g It was one of the things that did not g lead me to further investigation was the lack of panic.
10 It did not seem to be significant at all, as far at that 11 went.
12 Q Would you say the rod-worth-minimizer problem was 13 significant?
34 A Was it at the time or now?
15 Q No, on that particular shift.
16 A Well, I personally would have liked it to have been
} n programmed differently.
1 3g MR. LANG: If the rod-worth-minimizer i
39 had been programmed the way you assumed it to be, and I I l l
s 20 acted as it did, would you have' declared it inoperative? l<
21 A Well, that is another hypothetical question, but probably.
s i
r MR. LANG: Also, on the evening that 22 23 they had the spurious block, were you aware of that?
]
A No.
24 )
i 25 MR. LANG: Were you aware of any 25 l
I spurious blocks?
2 A No.
3 MR. LANG: Not even that night, perhaps 4 a night or two before?
I 5 A well, you know --
~
6 MR. LANG: As far as you know.
7 A Not that I know.
8 MR. LANG All right.
I 9 10 BY MR. KALKMAN:
11 Q Mr. Duda, have I or any other NRC representatives l
12 threatened you in any manner or offered you any reward in 13 ,
return for this statement?
I 14 ll g go, 15 O Have you give this statement freely and voluntarily?
16 A Yes.
)
i " O Is there anything further that you care to add for the l
18 record?
i 19 A Just that I believe that all of the individuals involved 20 working for Detroit Edison did their job safely and 21 although there was an error, the error was corrected in a ;
22 timely manner, and control of the reactor was never lost.
23 Thank you.
24 MR. KALKMAN: Thank you. l 25 (Despostion concluded at 10:40 a.m.)
26 ,
!