Transcript of Ofc of Investigations Investigative Interview of Rs Lenart on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-23ML20237K193 |
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Fermi |
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07/23/1985 |
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NRC OFFICE OF INVESTIGATIONS (OI) |
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ML20237J518 |
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FOIA-86-245 NUDOCS 8708270089 |
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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
-_- _
OTGWAL i
(
UN11ED STATES l NUCLEAR REGULATORY COMMISSION I
1 IN THE MATTER OF: DOCKET NO: l l
! 0FFICE OF INVESTIGATIONS INVESTIGATIVE INTERVIEW 1
l l
1 l
CLOSED 1 1
I
( .
LOCADON: GLEN ELLYN, IL PAGES: 1 - 23 DATE: TUESDAY, JULY 23, 1985 I
r ACE-FEDERAL REPORTERS, INC.
444 Mann CapitolStreet Nhington, D.C. 20001
'f M #3D - ' -*
[g 8708270009 870819 hTEN 6-245 PDR NAMONWIDE COVDACE ,
~[ h( If
i :
1 UNITED STATES NUCLEAR REGULATORY COMMISSION
- 2 3
IN THE MATTER OF: Investigative Interview, 4 Closed Meeting.
5 INTERVIEW OF: Robert S. Lenart.
6 7
- 8 Report of proceedings taken at the interview in:
9 the above-entitled cause on Tuesday, July 23, 1985, 10 at 799 Roosevelt Road, Glen Ellyn, Illinois.
11 12 <
PRESENT:
( 13 MR. JAMES N. K A LKM A.W , Investigator 14 MR. TERRANCE LANG, Reactor Engineer U.S. Nuclear Regulatory Commission 15 office of Investigations l Field Offices Region III i 16 799 Roosevelt Road Glen Ellyn, Illinois 60137; 17 MR. PETER A. MARQUARDT, General Attorney 18 Detroit / Edison 200 Second Avenue 19 Detroit, Michigan 48226.
20 21 Glen Ellyn, Illinois
- 22 July 23, 1985 23 24 /,
25 1
4 e e . ,
I i
i' 1 MR. KALKMAN: For the record, this is an
-- 2 interview with Robert Lenart, L-e-n-a-r-t, who is 3 employed by Detroit Edison Company. The location of 4 this interview is NRC Region III, Glen Ellyn 5 Illinois. Present at this interview are Mr. Lenart; 6 Detroit Edison general attorney Mr. Marquardt; NRC l
7 reactor engineer Terrance Lang; and NRC investigator ;
-1 8 James Kalkman. The subject matter of this interview 9 concerns a reactor operator error at the Fermi II 10 operator Station.on July 2, 1985.
11 Mr. Lenart, would you please stand and 12 raise your right hand.
13 (Witness sworn.)
l 14 ROBERT S. LENART, 15 called as a witness herein, having been first duly 16 sworn, was examined and testified as follows:
17 EXAMINATION
- 18 BY 19 MR. KALKMAN 20 O. Mr. Lenart, you're the plant manager or --
21 which title do you hold?
22 A. Assistant manager, nuclear production.
23 O. And how long have you been employed in that 24 capacity?
25 A. Well, let,'s see, we made a transition; but 2
. _ _ . . . ~ . _ _ . _ _ . _ - _ . _ _ _ . . . _. _ -.._.._-.___.-_-__.______-.___.-.____._._____m_-_-_-__ J
1 the capacity -- the equivalent capacity,-
- - 2 approximately two years.
3 Q. Have you been with Detroit Edison for --
4 A. Almost 25 years. ,
5 Q. Is --
so Fermi II is your only nuclear I l
1 6 experience?
7 A. Yes. 1 8 Q.. What do you recall of the --
of your being-9 made aware of the operator error that occurred on 10 July 1st or 2nd --
11 A. 2nd.
1 12 Q. -- 19857
~
l 13 A. The first time I can recall being aware H 14 that there was an operator error would have been on ]
l 15 the -- sometime in the early morning of July the 2nd, 16 early morning someplace between 6:00 and 8:00 17 o' clock. I normally get in around 6:00, and it was i
18 before the staff meeting at 8:00; so_that's the best-19 I can do in terms of time frames.
l 20 And that was, I believe, via ,
t 21 information received from Gene Preston, the j 22 operation engineer; but I am not absolutely sure.
23 There was someone at the plant that made me aware of
/,- 24 the incident. And the -- at'that point I had not 25 much detail with regard to the incident other than-3 I
1 it was corrected on shift. Whatever the error was, 2 it was evaluated, that it was not reportabler and 3 therefore the shift supervisor made a decision to l
4 continue with the startup.
5 O. How much did you know of the incident? j 6 A. Just about what I told you, that was the i
7 extent of it. ] 1 8 Q. You knew it was a rod pull --
9 A. Yes. j i
i 10 Q. -- error?
j . 1 l
11 A. Yes.
l -
12 Q. And did the matter of whether the plant ,
i 13 went critical come up in that first discussion?
14 A. Not to my knowledge.
15 O. Did you think --
16 A. No, I didn't.
17 0 --
of that issue occurring?
18 A. No.
l 19 0 Are you a degreed engineer?
20 A. Yes.
21 Q. In what --
22 A. Mechanical engineer.
l 23 Q. You're a mechanical engineer.
24 Following the --
that initial .
25 notification on July 2nd, what was your next 4
1 in<nL>ement with this incident?
-- 2 A. Let's see, that was the 2nd -- I should 3 know. I just went over it. It was the evaluation, 4 the first evaluation meeting which was held, I 5 believe, on the 3rd of July. It was at I believe 6 10:00 o' clock in the morning.
7 That was the next time the subject 8 came up. There was other dialogue during --
during 9 the course of the afternoon of the 2nd and first 10 part of the 3rd, but that was all focused around 11 that we should set up a meeting with the reac ir 12 engineering group, operations, myself, Gregg 13 overbeck', Leo Lessor, and Preston, get the people in 14 a room and start evaluating this thing.
15 So there was dialogue, but it was all 16 not in detailed to the event other than getting 17 ready to discuss the event with the appropriate ,
18 people.
19 Q. When was the first time that you were aware 20 of the fact that the plant had in fact gone critical?
21 A. That would have been late in the afternoon 22 of the 5th, after the second meeting, at which time l
23 I was passing through the lobby area of where my 24 office is and where Gregg Overbeck's office is; and 25 the conference room is just around the corner.
5 t
L
I l
l 1 And lue was either just coming out of l l
1
- - 2 that meeting -- but it was fresh on his mind because 3 he stopped by and said, " Bob, we just had the second 4 meeting, and we have finally come to a resolution:
5 and all parties agree that the reactor did go 6 critical." I acknowledged the fact that I had heard 1
7 him, and that was the extent of it.
8 Q. Did you --
did you give Mr. Overbeck any 1
9 instructions on how to -- how to respond to the NRC 10 or to notify the NRC of this' incident?
l 11 A. After the fir.st --
12 0 After that. l 13 A. After the first meeting or second meeting?
14 O. In either case.
15 A. In the first meeting, because there was --
16 out of the first meeting, what was got out of that I 17 meeting was that there was indeed a violation of the 18 procedures; that event that occurred would require 19 additional investigation; that we weren't certain 20 with regard to whether or not we went critical; and 21 there were really two decisions that came -- at 22 least to my knowledge --
two decision or directivec 23 that came out of that meeting.
24 One was that we were to put in place 25 the two-man operator verification for groups three i 6
l 1
1 1 and four. That came out of that meeting, that any
- 2 subsequent startups would have the two-man rule.
3 MR. LANG: What was the -- why was that decision --
4 what was that decision based on, to do this 5 verification?
6 THE WITNESS: It was mainly based on the fact 7 that until we straightened out what at that . time
. 8 appeared to be a conflict o r -- not a conflict, but 9 a potential for misinterpreting the pull sheet, we 10 put that into effect.
11 MR. LANG: Okay.
12 MR. KALKMAN: Q. So did --
~~
13 A. And then the other thing that came out of 14 that meeting --
I said there were two things. If I 15 recall correctly, I asked Gregg and Gene Preston --
16 I don't know if I asked both. Well, it was probably 17 Gregg, and he said Gene and him would take care of 18 it, to inform the NRC resident inspector.
19 Those were the two -- well, then the 20 third action, I don't mean there were three -- then
, 21 nuclear engineering, reactor engineering, was to l
, 22 take and do a more thorough analysis of the event to 23 determine whether or not criticality had been 24 attained or not. So those were really the'three --
25 the three action items, if I recall, that came out.
7 L _________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _
4 1 of that meeting. That was first time that any .
3
- 2 acknowledgment was made, to my knowledge, that we 3 should take some steps to informing NRC.
4 To my knowledge that was carried out.
5 I did not witness it, I did not see it, and I wasn't i l
6 present at it.
7 Q. Did Mr. Overbeck' contact you later and say, 8 "Yes, we did in fact" --
9 A. I believe he did, yes, sir. ,
10 Q. Did you personally have any discussions or 11 any contact with any NRC representatives relating to 12 this inadvertent criticality?
13 A. No, sir.
14 Q. Did you notify any of your management --
15 any people that yoy report to of this incident?
16 A. I reported to them -- now again, I want to 17 clarify the incident, the incident Deing the mistake 18 in the rod pull, and that was on the -- that would 19 have been the afternoon of the 3rd that Wayne Jens 20 was over in the -- in my area.
21 His office is in another building, but-22 he happened to be over there that day for another 23 meeting, and I can't recall the meeting; but when 24 the meeting broke up, there were two things that I.
25 wanted to bring.Dr. Jens to speed on, and one of 8
L____________._____________________________.______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1 them was to inform him that many -- I don't know if 1
2 it the first time I informed him of the fact we had 3 the mispull. But I am sure at that time I repeated 4 the fact there was a mispull.
5 .And we had~ earlier in the morning had
')
6 a meeting in which this subject was discussed with 7 regard to whether the reactor did or didn't go l 8 critical. There were difference's of opinion in that 9 meeting, and that I wanted him to be aware of that 10 fact; and I basically told him because,-you know, I 11 thought it would be --
oh, from a PR stand point, a i
12 sensitive issue --
and told him what the game plan i 1 --
l 13 was: reactor engineering was to go back and do ;
l 14 another analysis, and that there would be further j
)
15 results. That, to my knowledge, is at least the 16 only time, to my knowledge, that sticks in my mind 17 that I had a face to face or over the phone, any 18 kind of direct communication with him on that 19 specific subject, was that one incident.
20 Q. So you left him with the with the l 21 information, at least from what I gather, that the j . 22 plant --
it was still undecided or undetermined '
l l 23 whether the plant had in fact gone critical?
24 A. That's correct.
l t
25 O. So at that point he would not have known?
. 9
1 A. . No, sir.
2 Q. And you don't recall a later discussion 3 where you would have related to him the outcome of 4 the engineering group findings?
5 A. That's correct.
6 Q. What about any other -- Mr. Agosti or any 7 other management, Fermi management?
8 A. Not to my knowledge.
9 Q. So this incident was kept within two people 10 subordinate to yourself?
11 A. The incident -- well, I guess it depends on 12 how you look at it. The incident was known to Mr.
13 Jens. The one place that -- in fact, we talked 14 about it at the time we had the brief discussion, if 15 the real incident was the abnormality with regard to 16 the pull sheet and the error in the pull sheet.
17 And other than -- and we determined --
18 we had a little dialogue saying whether it went 19 critical or didn't go critical. The deportability 20 issue really wasn't a factor. And I guess that was, 21 yes, the extent of the entire incident as such, not 22 necessarily focusing in on the criticality issue.
23 That -- I have to admit, I guess I 24 wasn't as sensitive as to whether it did or didn't 25 go critical. The whole issue boiled down to an 10
~ ~ . _ _ _ _ _ . . _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ . _ . _ _ _ . . _ . _ _
1 operator error. And whether.it did or didn't go
- - 2 critical really didn't change -- at least from a 3 reportable incident -- an issue which I think, if
-4 that would have been the case, it would have been 5 pursued further with management.
6 But it didn't change any of that.
7 The --
I made him aware of what I believed to be the-8 other significant thing, that if the information had' 9 left the plant via any people including whatever the 10 discussion was with the NRC, that possibly the ;
1 11 reactor could have gone-critical, he would have been l 12 aware of that. From that standpoint he would not I 13 have been -- he would not have been caught offguard.
14 And therefore if a call had come in i
15 the next day, two days later, or three days later, I
16 he would have been aware of the incident that took 17 place. If someone said, "I heard that the plant 18 went critical at such and such a time over an 19 incident," he would have been aware of the incident.-
i 20 And that was my primary purpose-for j 21 informing him, so he~wouldn't --uif he were to get a 22 call from someplace and if he. felt appropriate, he 23 could. inform the public affairs or'whatever it may 24 be of it. That was really the. purpose and my intent i 25 of informing. And when we found out that it did go 11'
1 critical, l' guess it didn't change my rationale at
- - 2 all for why I had initially informed him. So I 3 didn't --
4 O. You didn't think it was --
5 A. --
Purcue it.
6 O. -- important to let him know that the plant 7 had in fact gone critical for the same reasons: in 8 case he was called, he could verify; or in case some 9 intervener or some newspserson got wind of this, he 10 could respond?
l 11 A. Well, I guess in hindsight that may have 12 been the appropriate thing do do. I have to 13 honestly say I didn't do it.
14 c. Were you present at the Commission hearing l 1
1 15 for full power license? l 16 A. Yes, sir.
I 17 0 Were you aware of the agenda item of !
18 operator error that was to be discussed at the 19 Commission hearing? ,
f 20 A. No, sir.
21 0 That was one of the --
one of the things
}
22 discussed at the Commission hearing, was it not?
23 A. The first time I saw the presentation was f l
-~ 24 at the time it was presented at the Commission ,
25 hearing. l 12 j j
l
1 Q. But that was -- was that an item discussed
- - 2 at the meeting, at the hearing;. do you recall?
3 A. I remember a comment being made in that 4 regard, yes.
5 Q. By whom?
6 A. I believe it was one of the commissioners l
7- during one of his statements with regard to operator --
l l 8 operator error.
L 9 O. Do you recall the assistant regional 10 manager, Burt Davis, responding to the Commission 11 that Fermi or Detroit Edison had a very good-12 performance record relating to operator --
operator 13 actions, very minimal operator error or anything 14 like-that? I wasn't at the meeting, so --
15 A. Well, there were several that I would 16 classify as complimentary comments made, and I l
17 would --
I can't recall all of them. But,I would 18 assume there was ones such as that made.
0 19 O. There was an operator error that occurred, 20 I think it was discussed at the meeting, at the 21 Commission meeting, that occurred just,before the 1
i 22 Commission meeting, a day before'or'the'same day.
a 23 A. That's true, that's right. iThe night l
24 before the hearing, that's correct.
1 .
, 25 O. And I think:that was the only operator *
<13 1
/
l.
.n . -
1 error that was'related to . th'e Commission.
. - 2 A. That's correct, but it's not the only 3 operator error that's been made.
4 Q. No, but did you -- did you perceive that 5 Mr. Davis or the commissioners were not aware of the 6 inadvertent criticality error?
7 A. No, sir. No, sir. As far as I knew, when 8 the resident was informed -- and I assumed he was 9 informed because I wasn't there, but I have no 10 reason not --
to doubt that Mr. Overbeck and Preston 11' carried out the directive that was asked of them; 12 that the NRC was informed.
WOU 13 It was not --
it was not ~ reportable.
14 And we have in the past in many, many instances -- l l
15 not exactly similar to this, but abnormal plant i 16 operations have occurred -- have sat down across the 17 table from either Paul Byron or Mike Parker and have 18 discussed the issue and have.aseumed that whatever 19 the normal channels are for that information to be 20 communicated take place.
21 And they have not hesitated in the 22 past when there have been questions with. regard to l l
l 23 an incident to come back and ask or on their own 24 continue'toslook into it.
l 25 This one really -- really --'really, l
14 l
l
i 1 nothing happened. I had no -- I.had no clues that
.. 2 there was interest in the Commission anyplace with 3 regard to this incident. It was absolutely quiet.
4 Q. Did that surprise you? I mean you just 5 related that Mr. Byron --
6 A. It surprises me now.
7 Q. -- and Mr. Parker, in the normal course of 8 their -- of events, they would come to you and ask 9 about an incident such as that.
10 A. Only if they had questions, you know.
I 11 0 Wouldn't that lead you to believe that 12 maybe they were misinformed or didn't know about 13 the --
didn't understand the significance of the 14 incident?
15 A. It didn't enter my mind, to be honest with 16 you. I guess I had a lot of other -- a lot of 17 things on my mind at the time, and it was an 18 incident that took care -- that took place.
19 We were working on it internally as a 20 problem and dealing with it, along with other things 21 that we had to take care of, in the course of 22 running the facility. And it never entered my mind.
23 I knew Paul was --
right after that, '!
i 24 right after the SALP meeting -- he wasn't at the
, 25 station. He got tied up then on a Monday and 15
1,