Partially Deleted Transcript of 850820 Investigative Interview in Newport,Mi Re 850702 Reactor Operator Error at Plant.Pp 1-18ML20237K250 |
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Fermi |
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08/20/1985 |
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NRC OFFICE OF INVESTIGATIONS (OI) |
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ML20237J518 |
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FOIA-86-245 NUDOCS 8708270116 |
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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
_
. ORIGINAL
- T UhllEU STATES NUCLEAR REGULATORY COMMISSION i
IN THE MNITER OF: DOCKET NO: ;
INVESTIGATIVE INTERVIEW l OF i BARI ARORA i
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'i LOCATION: NEWPORT, MICHIGAN PAGES: 1 - 18 i
DATE: TUESDAY, AUGUST 20, 1985 l
Information In this reced was deleted l in accordance wit the fyr m of Intermatlp Act, exemptions M NU la F01A. h-W5~
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1 0394 90 01 1 l WRBeb 1 UNIT,ED STATES OF AMERICA ,
2 NUCLEAR REGULATORY COMMISSION-3- Office of Investigations
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4 __________ _________________________ .
l 5 In the matter of: : 1 1
6 DETROIT EDISON.. COMPANY a 7 (Fermi Nuclear Power Station No. 2) :
g ;___________________________________:
I 9 Room 164,
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10 Nuclear Operations Center, 11 Fermi-2 Nuclear Power Station, I i
12 Newport, Michigan. j 13 Tuesday, 20 August 1985 l 14 Investigative interview of HARI ARORA was
- 15. conducted in closed conference beginning at 4:20 p.m., when i 16 were present: I 17 JAMES N. KALKMAN, NRC Investigator 18 CARL LANG, NRC Reactor Inspector-19 f PETER MAROUARDT, Esq., Detroit Edison Company <
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20 SUSAN BEALE, Esq., Detroit Edison Company 21 l
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23 4 l
24 25
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ACE FEDERAL REPORTERS, INC.
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l 9394 01 el 2 WRBeb 1 PROCEEDI NGS 2 MR.-KALKMAN: For the record, this is an 3 interview of Hari Arora, who is employed by Detroit Edison 4 Company. The location of this interview' is the Fermi 2 5 Nuclear Power Statiori in Newport, Michigan.
6 Present at this interview are Mr. Arora, Detroit 7 Edison Counsel, Mr . Marquardt and Ms. Beale, NRC Reactor 1 l l l 8 Inspector, Mr. Lang, and NRC Investigator James Kalkman.
l 9 The subject matter of this interview concerns a 10 reactor operator error which occurred at-Fermi'2 Nuclear 11 Power Station on. July 2nd, 1985.
12 Mr. Arora, would you please stand and raise your 13 right hand?
14 Whereupon, 15 HARI ARORA 16 was called as a witness and, having been first duly sworn, 17 was examined and testified as follows: l
\
18 EXAMINATION 19 BY MR. KALKMAN:
20 0 Mr. Arora, what is your position?
21 A I am Reactor Engineer.
22 0 Reactor Engineer?
23 A Yes.
24 O Are you a management person? !
25 A Yes.
1 l
ACE FEDERAL REPORTERS, INC. :
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0 Do you head up the Reactor Engineering Section I 2 here?
3 A Section head.
l 4 0 Do you supervise Mr. Thorpe? !
i i
5 A Yes. ;
6 Q How long have you been employed by Detroit !
7 Edison?
8 -A Nine years.
9 0 Are you a degreed engineer? I 10 A Yes.
i 11 O What-- j i
12 A B. S. Mechanical. i 13 0 Do you have other nuclear experience?
14 A Yes.
15 0 Where?
16 A I worked in India for eleven years at Tarapur 17 , Atomic Power Station. i 18 0 When did you first become aware of the 19 out-of-sequence rod pull error that occurred in July 2nd?
20 A July 2nd, the morning. j i
l 21 O And how did you become aware of that? ;)
4 22- A I went to the control room. l i
23 0 Who notified you of the error?
25 0 Which log? l l
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2 0 Did you ask thh, reactor engineer who lujged that, 3 Mt ..Myers, did you ask him about the incident?
4 'A He had left at'the change of' shift. .
5 , O He was alrdady off?
1 6 A- Yes .
7 0 What'was your reacti~on to having read the log? )
8 A I felt that the operator had pulled rods more 9 than what they are required to be pulled.
10 0 Did you assume from reading the Reactor 11 Engineering log that the plant had gone critical because of 12 the rod pull error?
l 13 A No, there was no determination made at that time 1
14 whether the reactor did go critical or not.
15 0 No, but the log states that the reactor had gone ]
16' critical. .
17 , A As you see, the-log has been changed. The. log 18 initially had-- Again, the information on criticality or 19 not was passed on to the shift nuclear engineer by STA in l i
20 training.
21 0 How often do the reactor engineers cross out an )
22 entry, or how often do they change their entries in the log? !
23 A Normally it should not happen. 'There has been 24 one other incident. We do the thermal accumulation for the 25 day, and there'has been a time when that calculation is in '
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'394 01 04 5 WRBeb 1 error, and they have, been crossed out and new information i
2 added. J 3 0 Did you discuss this log entry with Mr. Myers at 4 a later date?
5 A Yes. Barry and I talked on July 2nd.
6 0 on the next shift when he came in?
7 A Yes.
4 8 0 What was the discussion?
9 A Basically the discussion was about where was l
10 Barry. Actually he explained where he was at the time he. '
11 was informed by the STA in training, and that is basically i
12 what he asserted to be what is in the log book.
13 0 Why did he make the change in this?
t' 14 A Why did he make the change? l l
15 0 Yes.
16 A I'm told by Barry Myers that that is the 17 information the STA in training wanted to convey to him, 18 that he did not mean the reactor went critical, he meant 1
19 that-- What exactly the words are, I can't tell you what !
20 the words are. l 1
21 0 According to Mr. Myers, the STA in training gave 22 him the specific information that he logged originally into 23 this reactor engineer's log,--
24 A Yes.
25 0 --
specific as to what steps they went critical ACE FEDERAL REPORTERS, INC.
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WRBeb 1 and the position of,the rods.
2 A So he told me. So Barry Myers told me.
3 0 So Mr. Myers didn't do any type.of evaluation on 4 his own?
5 A I understand no.
6 0 And then the STA in training came back later and 7 said that was incorrect?
8 A I don't know exactly as to what transpired in 9' time, the sequence.
10 0 Is this the reactor engineer's log or is'this the 11 STA in training's log?
12 A This is the reactor engineer's log.
13 'O Then why is the reactor engineer reporting what 14 the STA in training.is telling him rather than putting down 15 his own information? I mean shouldn't the reactor engineer l i
16 be cognizant of what is taking place rather than having-a l 1
17 , second party telling him what information.to put in his log?
18 A I can't answer that.
19 0 Well, normally is that the situation?
20 BY MR. LANG:
l 21 0 You asked Barry hyers where he'was. What did he 22 have to say? '
23 A As he indicated in the log, that he was sitting 24 on the reactor engineering desk, reviewing'the startup test i 25 phase engineering log.
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ACE-FEDERAL REPORTERS, INC.
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'394 Ol'06 7 WRBeb 1 There are, two dif ferent positions that BarryL l 1
2 Myers was working, one is called the. shift nuclear j i
3 engineer; the second is called the startup t.est phase.
4- 0 Which position was he doing on the shift? j 5 A Both. Our organization is set up-such that Barry 6 Myers was shift nuclear engineer and also that he was 7 startup test phase engineer.
8 0 Do all reactor engineers do the same thing? - j 9 A No.
i 10 0 Just Barry? !
11 A Barry Myers and John Thorpe. )
l 12 0 Those two gentlemen?
13 A Yes.
I 14 BY MR. KALKMAN: i 15 0 When did you find out that Mr. Myers' original l 16 assessment was correct, that the reactor had in fact gone 17 , critical?
18 A I was called by John Thorpe at home on the 19 afternoon of July 4th.
20 0 By John Thorpe?
21 A By John Thorpe.
22 0 were you involved in the Reactor Engineering 23 review process to determine the criticality issue?
24 A To the extent that we did work on July 2nd, and ;
25 we did have a meeting on July 3rd. The July 4th work was l
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" 94 01. 07 8
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WRBeb 1 done independently by.' John Thorpe.
2 0 How did ' Reactor Engineering get involved? Did i 3 Mr. Overbeck or someone direct or ask that you people 4 perform an analysis?
5 A Yes. That was as a result of disposition of DER !
6 on July 2nd afternoon. Reactor Engineering was assigned l 7 responsibility for reviewing that incident. ,
i 8 0 Did you have some personal involvement in this 9 review process, or were your people taking care of it'for. I 10 you?
11 A I personally had involvement in it.
12 0 You had involvement in it?
13 A Yes.
14 0 What was th'e outcome of your analysis?
. A As the outcome of the analysis we had a meeting 16 on July 3rd.
17 0 July 3rd?
18 A Yes.
19 And that was in the morning of July 3rd. And in 20 the meeting we, Reactor Engineering, presented our findings 21 of the incident.
22 0 And what was the result? What were the findings?
f 23 A The finding was-- The final determination of was 24 criticality reached or.not was left undecided because it was 25 decided that we need to look at SRM recorder charts which l .
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W RBeb 1 shows actual rod movements time-wise. We did not have on .{ .
2 July 3rd those moves put together of the SRM logs. l 3 0 At the July 3rd. meeting didn't John Thorpe i
4 express his opinion that the reactor had gone critical?
i 5 A Yes.
- 6 0 What did he base that opinion on?
7 A Based on the SRM logs. .
l 8 0 So Thorpe had looked at the SRM charts. ]
9 A Yes.
10 0 Then why did Reactor Engineering-have to do a i
11 second analysis?
12 A -Basically the reason being that you see the whole l 13 log rod pulls were done at such a short time interval that I 14 some people felt that it could be an indication of 15 suberitical multiplication rather.than actual criticality.
16 So that is why the direction was given to do that.
17 Q Did you personally agree with Mr. Thorpe that the 3 18 reactor had gone critical?
19 A No.
20 Q Did anyone else from Reactor Engineering agree t 1
21 with Mr. Thorpe? l i
22 A I don' t recall.
23 0 When you came to the meeting as a group, Reactor 24 Engineering, did you have -- had you conceptualized that the 25 reactor was in fact critical and, as a result of the l
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l WRBet . 1 meeting, you changed your mind and went back to do a second j l
2 analysis? i 3 A No, I had not made a final determination at the l
4 meeting of July 3rd.
5 Q And Mr. Thorpe had.
,6 Did anyone else in Reactor Engineering-- Who 7 else was at the meeting from your group? j 8 A Myself and John Thorpe from Reactor Engineering. !
l 9 Q And who was the other dissenting party?
10 MR. MARQUARDT: Dissenting from whom?
11 MR. KALKMAN: From Reactc' Engineering.
12 MR. MARQUARDT: From Thorpe?
13 MR. KALKMAN: From Reacror Engineering.
14 THE WITNESS: Maybe you're talking aoout Mel l
15 Batch. Mel Batch is a member of Nuclear Fuel Engineering, 16 and not Reactor Engineering.
17 BY MR. KALKMAN:
18 0 Do you know if Mr. Thorpe discussed hir analysis 19 with Barry Myers?
20 A I'm not aware of whether he did or not.
21 0 Do you recall Mr. Lessor expressing his opinion 22 that he thought the reactor had gone critical?
23 A Yes.
24 0 Which concurs with-Mr. Thorpe?
25 A Yes. Leo's feeling was that the reactor had-gone J
ACE-FEDERAL REPORTERS, INC. ~
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94 (- 10 11 I WRBeb 1 critical. ,
2- 0 Was there anyone else at the meeting on July 3rd 3 that expressed an opinion that the reactor had gone critical l
4 or had not gone critical?
5 A The one mentioned, Mel Batch. )
l 6 O Mel Batch. 1 I
7 A Yes.
<i 8 0 What.was his--
l l 9 A His feeling was no. d 10 Q Did you express a position or an opinion at that' [
11 meeting? j 1
12 A No. l 13 0 Were you told at the July 3rd meeting that 14 Detroit Edison's position was that the reactor had not gone j 15 critical?
16 A No.
17 0 Did you get that impression from the meeting'that 18 that's what the company position was?
19 A No.
20 I think I remember Mr. Lenart saying that it is l 1
21 not clear whether it is critical or not critical, and'we 22 need to do more work on it. But there was no Detroit Edison 23 position saying that the reactor did not go critical.
24 I'm speaking from what Mr. Lenart said.
25 O Shortly or some time after the July 3rd meeting
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WRBeb 1 on the same date, July 3rd, did you receive a phone call '
2 from the NRC resident inspector, Mike Parker? !
3 A On. July 3rd afternoon, I was in the control room 4' when Gene Preston, the_ operations engineer, told me that 5 Mike Parker wants to talk to me. .
6- Q And you called Parker?
7 A That's right.
8 Q And what questions did he have?
9 A His question was whether the reactor did go 10 critical as a final determination. I said a final determination had not been made, that we have been asked to 12 do more work to confirm that.
13 The second question was the shif t nuclear 14 engineer, he said " reactor engineer" but he meant " nuclear 15 engineer," was he in the control room. I said yes he was in ;
16 l' the control room, but he was not in the control area.
17 0 Was that the extent of the conversation?
18 A I can't think of anything else.
19 I did ask him if he wanted to talk to Barry 20 Myers, and he said No.
21 Q So you advised Mr. Parker that you could not make 22 the determination whether I- at that point whether the 23 reactor was critical.
24 A I told him we had been given action 'to perform 25 more work.
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1 ACE-FEDERAL REPORTERS, INC.
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l ' '94 01 12 13 WRBeb 1 O Did he ask you to get back to him when you had 2 the results? ;
3 A No.
4 BY MR. LANG:
5 0 Did you discuss the event at all with anybody on l
6 shift?
7 A Myself?
8 0 Yes.
9 A On the shift? Yes. ,
10 John and I talked to \thereactor 11 operator, on July 1st. e l 12 0 On July 1st.
'l 13 Did you do anything on the 3rd? !
14 A No. I talked with people on the same shift. I 15 We're talking about the July 1st shift? l
{
16 0 No. l k
17 , Actually on July 3rd, the night of July 3rd, did )
18 you go up to the control room and discuss the 1
19 out-of-sequence events with anybody?
20 A No.
21 0 Did John Thorpe?
l 22 A I don't know.
23 BY MR. KALKMAN:
24 0 What about the 2nd, July 2nd, the evening of July 25 2nd, the shift following the event, the rod pull sequence A
ACE. FEDERAL REPORTERS, INC. /
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2 A I have talked t<f on July 2nd night at i 3 11:30 when he came on shift.L / I 4 BY MR. LANG:
5 0 Was that in the control room? '
6 A No, it was in the office next to the shift
)
7 supervisor. I 8 BY MR. KALKMAN:
9 0 And what was your discussion?
i 10 A Basically John was there, and myself. My 11 objective was to find out from him as to what really 12 happened concerning the rod pull.
13 0 And what did he tell you? )
I
, 14 A Well, he said that it was misleading on this i 15 part, that it was an error on his part to pull the rods !
I 16 .instead of 00 to 04, he pulled them to 0014.
17 ,
BY MR. LANG:
18 0 So neither on the 2nd, late on the 2nd, nor on i 19 the 3rd, you never met with the reactor engineer on shift.?
20 A I met Barry Myers on July 2nd.
l 21 O In the control room? l 22 A Yes.
23 BY MR. KALKMAN: l y-24 0 '
IsthatthesametimethatyoutalkedtoL 25
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94 01 14 15 l W RBeb 1 A Yes.- John was there., Barry Myers was there.
2 0 Did [ )tell you that he thought j the u j 3 reactor went critical?
4 A No, I don' t recall. No, I don't recall him l
l 5 saying that. .
e i 6 0 Did you mention to that Reactor J \
7 Engineering may have some thoughts on whether the plant had l 1
8 gone critical or the reactor had gone critical?
(
9 A No, I don't think we said that. I think we told r
10 that we were doing this talking as a result of the DER, l 11 Tb he understands why we're talking to him.
12 There was no mention made at that time that the .
13 reactor did go critical or not go critical.
14 0 The actions that \took once he
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15 discovered that he had mispulled the rods, was that typical?
16 The fact that he immediately started to reinset the rods 17 ,
that he had mispulled, is that the type of action that he 18 would have taken if he had not been critical? I 19 A I don' t know. I can't say. g 20 0 Well, if he had not been critical he could have 21 just stopped his -- what he was doing and analyzed the j 22 situation rather than reinserting the rods. Correct?
23 A I can't say for him.
24 0 Shouldn't he have contacted the reactor engineer 25 first before he started taking corrective action, before he
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(. 94.01 15 16- I WRBeb 1 started reinserting .the rods?.
2 A I would say yes.
3 0 After your telephone conversation with !
4 Mr. Parker, did you have any subsequent conversations with 5 Mr. Parker?
6 A Yes.
7 Q When were they?
8 A July 5th, in the cafeteria.
9 Q What was that discussion?
10 A I told him.that we are going to have a meeting j 11 this afternoon to discuss the further analysis which w~e have 12 made on the incident.
13 0 And did you tell him what your analysis was at
(
14 that point?
15 A No. )
16 0 You didn't tell him it had gone critical?
17 A No.
18 0 Did he ask?
'1 19 A No.
20 0 was he interested? Did he seem interested?
21 A I can't make any comment.whether he was 22 interested or not. i 1
23 0 Okay. 1 1
24 You related to him that a meeting was to take I place, and that meeting was where your group would make a 25 l
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.WRBeb- 1 presentation indicating that the reactor was in fact 2 critical.
3 A Yes, that's right.
4 0 Did Mr. Parker attend that meeti.ng?
No.
5 A 6 0 Did you have any discussions with Mr. Parker 7 after that meeting?
8 A No.
Do you know if Mr. Parker contacted anyone else 9 Q 10 in your group?
11 A I'm not aware of it.
12 O Mr. Arora, the STA log of July 3rd indicates that 13 you had -- yourself and John Thorpe had conducted a I l
14 debriefing apparently of the shif t personnel relating to the 15 previous night's criticality, j 16 A July 2nd I mentioned before.
17 ,
BY MR. LANG:
18 0 That was on shift then up in control?
19 A No.
20 BY MR. KALKMAN:
21 0 You went around and individually discussed the 22 matter with these people?
23 A No. I, with John Thorpe, were in the office next 24 to the shift supervisor. I did not go into the control 25 room, was the one we were talking to. I i
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WRBeb 1 remember John Dooz came in, and the SOA on shift. He was in 2 there, too.
3 0- Mr. Arora, have I or any other NRC representative 4 here threat'ened you in any manner, or offered you any 5 ' rewards in return for this statement?
l 6 A No.
7 0 Have you given the statement freely and !
.l l 8 voluntarily?
1 9 A Yes.
10 0 Is there anything further you. care to add'for the 1'
11 record?
12 A No.
13 0 okay. Thank you.
(
14 (Whereupon, at 4:55 p.m., the interview was 15 concluded.)
16 ,
8 \
17 I l
18 l 19 20 21 22 23 24 25 1
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____m_____--___
i CERTIFICATE OF OFFICIAL REPORTER
,(
l I
l This is to certify that the attached proceedings before the UNITED STATES NUCLEAR REGULATORY COMMISSION in the !
matter of:
NAME OF PROCEEDING: INVESTIGATIVE INTERVIEW OF HARI ARORA i I
i l
DOCKET NO.:
PLACE: NEWPORT, MICHIGAN t
DATE: TUESDAY, AUGUST 20, 1985 were held as herein appears, and that this is the original transcript thereof for the file of the United States Nuclear Regulatory Comunission.
<.-a);#629?/
! TYPED)
WILLIAM R. BLOOM Official Reporter ACE _ FEDERAL REPORTERS, INC.
Reporter's Affiliation
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