Transcript of Ofc of Investigations Investigative Interview of Wh Jens on 850723 in Glen Ellyn,Il Re 850702 Reactor Operator Error at Plant.Pp 1-21ML20237K263 |
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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 8708270121 |
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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
c ;
l I-OR'GINAL l UN11ED STATES NUCLEAR REGULATORY COMMISSION l l
l IN THE MATTER OF: DOCKET NO: ;
0FFICE OF INVESTIGATION INVESTIGATIVE INTERVIEW i
CLOSED i
I 4
LOCATION: GLEN ELLYN, IL PAGES: 1 - 21 l
, 23, 1985 DATE:
. . . . (
l Wm '
1 ACE-FEDERAL REPORTERS, INC.
M a ters 444 rth Capitol Stztet Washington, D.C 20001 (202)347-3 7 9 {8-] j' y 8708270121 870819 NATIONWIDE COW i 1~~
PDR F01A f PUNTENN86-245 PDR ( ~'g. y }; ,
.I '
1 UNITED STATES NUCLEAR REGULATORY COMMISSION
< l
-- 2
]
1 3 l IN THE MATTER OF: Investigative Interview, l 4 Closed Meeting. ]
5 INTERVIEW OF: Wayne H. Jens. l 6 :
7 I 1
8 Report of proceedings taken at the interview in j l
9 the above-entitled cause on Tuesday, July 23, 1985, l 10 at 799 Roosevelt Road, Glen Ellyn, Illinois. I
)'
11 1
1 12 , i PRESENT: )
( 13 MR. JAMES N. KALKMAN, Investigator l 14 MR. TERRANCE LANG, Reactor Engineer !
U.S. Nuclear Regulatory Commission l 15 Office of Investigations Field Office Region III 16 799 Roosevelt Road Glen Ellyn, Illinois 60137; 17 I' 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
k 1 MR. KALKMAN: For the record, this is an i
- - 2 interview with Dr. Wayne'Jens, J-e-n-s, who is i
3 employed by Detroit Edison Company. The location 4 .of this interview is NRC Region III, Glen Ellyn, ,
5 Illinois. Present at the interview are Mr.'Jens; I i
6 Detroit Edison general attorney Mr. Marquardt; NRC f i
7 reactor engineer Terrance Lang; and NRC investigator ]
d 8 James Kalkman. As agreed, this interview is being 9 transcribed by agreement by court reporter Lisa l 10 Selepa. The subject matter of this interview 11 concerns a reactor operator error at the Fermi II 12 Power Station on July 2nd, 1985.
I 1 13 Mr. Jens, would you please stand and
)
l 14 raise your right hand.
15 (Witness sworn.)
16 WAYNE H JENS, 17 called as a witness herein, having been first duly 18 sworn, was examined and testified as follows:
19 EXAMINATION j 20 BY l
21 MR. KALKMAN:
22 Q. What is your capacity with Detroit Edison?
23 A. I'm vice president of nuclear operations.
-- 24 Q. And how long have you been employed in that 25 capacity?
2
1 A. Sinco.lato 1979._
e 2 O. 'Have you been employed or worked.at any 3 other nuclear facility?
4 A. Yes, at Fermi I.
5 O. So you've spent a few years with Detroit 6 Edison?
7 A. I'm a full time --
I was a full-time 8 Detroit Edison employee _since 1972; although I'was 9- on the payroll since 1964, but on loan to Atomic 10 Power Development Associates.
11 And prior to that, from 1957 to 1964, 12 I was an APB employee, Atomic Power Development. I 13 Q. Could you relate for us the --
your first
( .
14 recollection of the rod pull error, operator. error i 15 incident that occurred on July 1 s t' or 2nd of '857 l 16 A. As I recall, and again, I a:m not 100 17 percent certain, that on July 3rd Bob Lenart 18 mentioned it to me as I was leaving his office area.
19 He indicated he had several things to tell me, one 20 was this; and I can't recall what the other item was.
21 O. Do you remember the discussion?
22 A. It was very brief. He just mentioned that 23 the reactor operator had made a mistake in pulling
,-- 24 some rods, that was one item, and he felt there was 25 a fuss being made whether or not criticality had I 3 l M" er mnh e
\
i l
l' been achieved; and there was argument between the j
' 1
-- 2 operating group .and the reactor engineers.
j 3 O. How did you --
how did you come away from 1
4 that discussion,.what was your perception?
l 5- A. I guess I was -- he impressed upon me the l
l 6 arguments that were going on, and I think in my own 7 mind I was not impressed particularly with what he 8 said, that it was a major error that had been 9 committed. In other words --
I didn't recall the 10 number of rods that had been mispulled and how far 11 they had been notched out.
12 Q. Did you give any advice to Mr. Lenart? i i
[ 13 A. No.
14 O. Any direction?
15 A. No.
16 Q. So if you had been asked right after that 17 discussion whether the plant had gone critical 18 during the rod pull incident, what would you have
'l 19 responded? J l
20 A. Probably not, but that it wasn't 100 f
l 21 percent clear.
22 O. There was some review taking place?
23 A. Uh-huh.
c- 24 O. Did the incident trigger anything in,your 25 mind as far as a significant enough event or j i
4
+mL M m em J
{ -
\
4 1 incident to report the incident to the NRC7 ;
i 2 A. No. Normally that's not a function that I l i 3 feel I have to take. Up to the present time the 1
4 plant has been doing that very capably. j 5 O. Is there --
I didn't ask anyone else this, 6 but is there a DECO procedure on who the responsible 7 corporate officer is for reporting deficiencies or 8 nonconformances to the NRC under Part 21, Part 21 9 Deportability?
10 A. There is a compilation of directives and 11 procedures that the licensing engineer put together 12 that identifies who is responsible for these type of ,
1 1
13 activities. '
14 0 Are you the responsible corporate officer? l l
15 A. Ultimately I would be, clearly; but it's 16 more or less delegated down to plant superintendent 17 and shift supervisor.
18 O. I understand.
19 A. In other words, if they are deficient, I
~~
20 feel I am responsible.
21 O. But normally there is a single responsible 22 corporate officer who is held --
who's responsible 23 for reporting a Part 21 issue.
,i- - 24 A. In Part 21 that would be me, according to 25 those procedures.
5
- i
7.
1 O. Not that this is a --
my curiousity --
2 A. Part 21 --
I was little confused. Part 21 1
3 ultimately comes to me.
4 0 Did you at any time prior to the Commission 5 meeting become aware of the fact that the plant had 6 indeed gone critical as a result of the --
the July 7 let or 2nd rod pull incident?
8 A. Not to my recollection.
9 o. When did in fact you become aware --
10 A. I was made partially aware of that in a i i
11 phone call from Leo Lessor on Saturday. Prior to !
l l
12 the phone call from Ed Greenman, it was kind of a 13 key indicent --
that I had talked to Frank Agosti 14 prior to his going on vacation, that I planned to 15 call Leo to talk to him about general conditions in 16 the plant. And what I was mainly interested in 17 seeking was that --
I had talked to Leo occasionally, 18 and I don't like to do it very often because he's 19 actually a consultant to the superintendent.
20 But one of my conversations must have 21 been months ago. He mentioned he didn't feel 22 engineering was responsive enough to the problems in 23 the plant. And I thought that recently the 23 engineering people were really responding very well.
25 So I wanted to talk to him, and I felt 6
6 e met W
--mm_ ._____m__
1 I better talk to Frank about that before I did it; I
- - 2 and that I would also tell Bob Lenart that I was 3 going to do it. And so it was a key incident that 4 Leo called me on Saturday indicating that he'd like 5 to talk to me. And when he called, he indicated 6 that about, he said about a couple incidents in the 7 plant. And two of the incident that I was 8 particularly interested in speaking to him about, 9 which Bob had mentioned to me at the time, one was i
10 the rod pull. And he said, " Yeah, that was one of i 11 the them." And I said, "Well, that's an incident I l I
12 was concerned about because of operator error."
( 13 And he said, "What about criticality?"
14 And I said, "Well, it didn't go critical, did it?"
15 And he said, "Well, you better find out more about 16 that." So that was one of them, and the other one 17 was the incident that occurred just prior to the 18 Commission meeting, which was the water level trip.
19 And so I set up a meeting on Monday 20 with him; but before I could have the meeting, Ed 21 Greenman called me and asked me personally to 4 22 investigate the rod withdrawal incident, which I 23 launched into at that time.
l ,--- 24 And in doing that I called Leo plus l 25 Bob over to the office, and so I had part of my k 7
M m l
d 1 meeting with him.
2 O.
You weren't aware of the fact that Leo had
. - i 3 already or was in the process of conducting an 4 investigation?
i 5 A. Well, I was, after I called Bob and found 6 out that Leo was investigating. And that was one of 7
the reasons he probably talked to m? on Saturday. !
8 But that was prior --
or after the Commission ' '
9 !
hearing. I've got to remember the actual --
see if 10 k I can get the date so you'll have that.
11 It would have been July 13 when he I 12 called me, and Ed Greenman called me on July 15. )
i 13 0 Did you know that --
before the Commission I 14 meeting, that one of the agenda items at the 15 Commission meeting was operator error?
16 A. Could you repeat the question, please.
17 Q. Did you know before the Commission meeting 18 that one of the agenda items at the Commission 19 hearing for licensing was going to be operator error ;
j 20 at Fermi? l l
21 A. Well, about one hour before --
and it was a l 1
22 number of items that were discussed. What had 23 happened was that Burt Davis and -
let me think. !
{
24 Joe Youngblood was in the meeting. I 25 I'm just trying to remember who 1
,. ee n "
I replaced Harold Benton (phonetic).
- - 2 O. Jim Taylor?
3 A. No. I know him, I just can't remember his 4 name. He was in the meeting. And what they wanted 5 to do was go over a rough outline of what they were 6 proposing to say at the briefing one hour later to 7 see if we had any comments.
8 And operator error was one of those 9 that was discussed. Specifically, again, I can't 10 recall the number at the time. It didn't make much 11 of an impression on me at the time, but'it'was one 12 of the items.
[_ 13 O. Did you know that the NRC_was going to --
14 or that Mr. Davis was going to brief the Commission F i l 15 on the incident that occurred the night before the j l
i 16 Commission hearing, the water level. incident? l 17 A. Now, what you're talking about'is kind of --
18 I don't remember that that was a specific item. I 19 think it was more of how many operator errors were 20 encountered. I guess I can't recall that_they 21 discussed that. But I do remember once the briefing 22 started, that Commissioner Zeck brought that 23 particular item up. And again I'm trying to 24
--- remember how many operator errors they were talking 25 about. It was something like two.
9 T
____________________-O
1 O. It's a very small number, I think.
t
-- 2 A. Right.
3 O. I think the NRC was fairly complimentary in 4 the --
5 A. Right.
1 6 0 -- operations of Fermi.
7 A. But again, how many were reported -- if you ;
8 talk about how many operator errors there are, there i
9 are a lot of operator errors. As I-mentioned i
10 downstairs today, you know, to get operator errors 11 Giuch below one percent is very, very difficult. . )
12 You have to use other devices to do-I 13 that, and what you have to get is independent 14 verification, rod worth minimizer blocking, movements, 15 whatever. And so I think to take that out of 16 context, how many operator errore are there, is not 17 something easy to handle.
18 O. If you're talking about significant 19 operator errors --
I am wondering if you would 20 categorize the rod pull incident with -- is that any 21 more or less significant than what Commissioner Zeck 22 brought up, the water level incident?
23 A. Had I, I guess, fully understood the fact 24 that we pulled 11 rods, you know, to get to the 1
25 criticality point in error -- today that's
- 10. ;
I significant to me. I didn't know that at the time.
, -- 2 All I know was that the operator had .
3 got close to critical through a rod manipulation 4 that was incorrect. I am not even sure I would have 5 appreciated that rods were manipulating. It could 6 have been one4 So I don't know if that would be 7 significant to me with my bankground.
8 I think to -- my background came out 9 of Fermi I. It wouldn't have been significant 10 there. I think the water reactor experience makes 11 it much more significant main 3y because of the worth 12 of --
remember, you 't. a v e a lot of reactivity worth 13 in all of the rods, so you have to be careful.
{
14 But take something like Fermi I, there j 15 was less in the dollar in the two operating rods --
16 manipulating that rod in error is not as significant.
17 So it's a matter of context, the background of the i
18 person that's evaluating it, how much information he 1 19 has.
20 O. Well, do you think that if the Commission 21 had the information, the commissioners had the 22 information about the inadvertent criticality 23 incident, that it would have affected their r- 24 licensing decision --
25 A. I don't know.
11
+.
7-1 0.- --
at the time? <
- l. - 2 A. I don't know how to answer that because 3 it's a subjective kind of a question.
4 O. Sure it is. .
5 A. In view of the way people have put the 6 importance on it today in today's environment, yeah.
l l
7 Today it would have have had an effect.
8 I never expected the kind of' reaction 'I 9 we're getting to the incident.
10 0 Let me ask you a more direct question. ,
11 Was there a co ris cio u's effort on anyone's '
12 part that you're aware <of to keep the NRC or the
\
l 13 commissioners from becoming, fully. aware of the 1 :,
c,
- 14 inadvertent criticality prior'to li enbing at Fermi, f
15 full power libensing? <
,} , 5'l J g 16 A. No, not in the way you' phrase the question.. ;
I \ ,
i 17 O. Was there in some other way that I d i d ri ',t /
- . 1 18 phrase? J' 1 19 A. Well, again, I mean I d$n't knoM o,f any.
, ,e '
l _ ,.
20 '0.,, You're not. ja ware of --
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t at l3 21 A' . 4 No, I ' m nc,t t 'awa r e of anybo'dy s9ppressing
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22jthis information. >
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i -7 j .* 's 23 '
0 ' Fio.a wh a t I understand, Mr s-Bregn!J/at Fcrmi i
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c- 24 was asked'tt.o compile some statistics for th'e
_I L
lx , .. .,.
25 commissiori briefing relating tAi operator -4 relating
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I to operator error.
- - 2 .
Are you aware of that?
3 A. I don't believe I am. I can't recall it.
4 O. At any time during the Commission hearing, 5 in any of the discussions about operator error or.
6 the the incident, the water level incident that j 7 occurred the day before the hearing, did this other 4 i
1
! 8 matter come to your mind? i j
l 9 '
A. No, it didn't come to my mind or did t
10 anybody indicate to me that it came to their mind. l 11 O. What was your understanding or what is your i I
12 understanding of the rod worth minimizer system in j
]
13 relation to this rod pull incident?
14 Was it your understanding --
do you l!
il 15 know the system well enough to know it would have or {
16 should have prevented this incident?
{
17 A. Are you --
are you asking whether I know it i i
18 now or I knew it some time ago?
19 O. In either case.
f 20 A. Well, I didn't know much about the e 21 limitations of it until the last week; 's o in that 22 sense it didn't have much significance to me. I 23 guess at the present time in the sense of what it's
-- 24 intended to be used for fundamentally, I don't think 25 it is a significant item.
13 6
, .e w 9
t 1 In view of the apparent sensitivity
- - 2 that this particular. situation has, it's unfortunate 3 that it wasn't programmed to protect the operators J
l 4 from getting into this kind of difficulty. I I
5 And if people knew of the sensitivity 1 i
6 of this at the time, they should have done something I 7 to account for the fact that it wasn't protecting l l
8 against this and employed independent verification, 9 which is a directive that I have out to all the 10 people.
11 Q. Speaking of the sensitivity of this issue 12 at the present time, wouldn't you think that if the 13 NRC had --
if the resident inrpectors had been fully 14 aware of this incident when it occurred, that they 15 may have had some involvement or some contact with 16 yourself relating to this incident?
17 A. Yeah, I guess --
state the question over 18 again.
19 Q. Based on your working relationship with Mr.
20 Byron and Mr. Parker --
21 A. Okay. l 22 O. --
and what you know now of how the NRC
]
l 23 perceives this incident, wouldn't it seem reasonable 24 that if --
assuming Mr. Byron and Mr. Parker did not l l
25 understand the issue when it occurred for whatever j 14 1 1
i a
. i 1 reason, miscommunicati'on, if they had understood the
(
-- 2 significance of the problem, don't you think they 3 would have been more -- there would have been more 4 involvement on their part with yourself or with'the 5 corrective actions -- which would lead one -- lead '
~
6 me to believe that the NRC was not fully aware of i
7 the incident.
8 MR. MARQUARDT: I guess'I only have a problem --
~l 9 there's about three different questions strung .q 1
10 together with a couple of assumptions.
11 THE WITNESS: I still have trouble with the l
1 12 question. Can you simplify it into single items?
l( 13 MR. KALKMAN: O. Let me break it down. I 14 MR. LANG: Maybe I can help you out.
l 15 How did you perceive the NRC, meaning 16 like Paul Byron and Mike --
17 MR. KALKMAN: Parker.
18 MR. LANG: --
Parker.
19 How did you perceive them to be aware 20 of the situation? In other words, did you think l
21 they took it seriously?
22 THE WITNESS: Well, until the last week, I was 23 unaware of the fact that Gregg had discussed it with r-- 24 them. I mean until I --
until today I was unaware 25 of the details of that conversation which came out 15
___________._____m_________ _ _ _ _ _ _ _ _ _ _ _ _ . _
1 today in the presentation when Gregg indicated that
(
-- 2 he expressed --
made the kind of statement he did to 3 Mike Parker about the seriousness that-he viewed the 4 situation. That was news to me.
5 And I guess under those circumstances l
6 I would have expected No. 1, that'they wou.1d have 7 had made a greater issue of it with me; and No. 2, 8 that either of the residents would have made an 9 issue of it with me. If that's --
and if'that --
10 they probably would have --
t i
l 11 MR. KALKMAN: O. The way I understand it, I'm '
i l
12 assuming that had Mike Parker or Paul Byron been
( 13 fully aware of this incident, they would have 14 brought it to your attention, which leads me to 15 believe that they were not notified --
I 16 A. I wouldn't --
I don't come to that 17 conclusion. There are several other options there-18 that, you know, that you would have to be thoroughly 19 familiar with. No. 1, were they so occupied with 1
20 other activities that they were not fully impressed 1 21 with what Gregg told them; and No. 2, were they 22 under some pressure to not bring up matters of this 23 kind. So I'm not --
I'm not prepared to'say that ,
.-- 24 you-know, they're going to react certain ways.
25 There could be other --
other options there.
16
~ ^ ^ ~
k i
l 1 O. What type of pressure would they
- 2 experiencing not to bring up a plant problem? -
I 3 A. Well, I just don't know what kind of j 4 pressures they're put under --
5 O. Well, licensing of Fermi should not be the 6 resident inspector's interest. It should be safe 1
7 operation of the plant. I i 8 A. I agree. I mean I'm not implying anything 9 by my inference. On the other hand, I don't think l
10 that you could infer what you did either, you know. )
l l 11 There's too many possibilities out there I think 12 under normal circumstances. -
13 I would have expected out of -- now, I i
14 don't have too much to do with Mike Parker; I mean Ji 15 he very seldom would bring anything to my office.
16 Paul Byron, on the other hand, does on many.
17 occasions. So under normal circumstances, yes, I 18 would think that they would have brought that to my 19 attention, asked me what am I doing about that, j 20 That would be the way it.would come 21 into me from Paul; that did not happen, but there 22 could be circumstances that would have prevented ;
i I
23 that.
l
~- 24 Q. Well, just f p o,m our discussion here today, ;
25 I don't get the impression that you felt this was a 17
- w. m + m l
_______.__________J
1 very significant incident, not from the way it was
.- 2 related to you.
3 A. That's right. That's certainly correct.
4 No one expressed the level of concern about it that 5 I now think they should have. I mentioned 6 downstairs, however, that there was tremendous 7 pressure put on us and the residents to investigate 8 Save Team activities, not necessarily from you, you 9 know, from your office, but in general.
10 And I had to -- it was a decision I 11 made, but I was asked to do whatever I could to get 12 that investigated. And so I took the best man I h a d ,'
13
( Mr. Agosti, and said, "You're going to spend full 14 time doing that until it's done."
15 And he did that and --
I don't know --
16 that had no effect, I don't think, on this 17 particular event. But I also know that Mike Parker 18 was spending full time on that activity and under 19 pressure to get it done by a certain time, which we 20 did. And Paul was not on the site very much during 21 this period of time.
22 Q. Did you ever relate this incident to Mr.
23 Heidel or anyone in the management chain above you?
24 A. Yes, but I can't recall exactly when. I 25 know I related the call from Mr. Greenman. Whether 18
___--_..m_ _ _ - . _ . - - . . - . . .
1 I indicated anything to him about Bob Lenart's
-- 2 comment to me on the 3rd, I don't remember.
3 And I probably didn't because I wasn't 4 really --
I didn't feel it was that important at i
S that time. j 6 O. When you talke.d to Mr. Lenart on or about l
j l
7 July 3rd about relate --
relating to this issue, did 8 he indicate that there may be a public concern about 9 this issue or you may be contacted if the 10 information were to get out of the --
out of Detroit 11 Edison to the newspaper or intervener group, that 12 you may be -- you should be prepared to -- prepared 13 to comment on the issue?
(
14 A. No, I don't think he would have --
I don't 15 think he would have indicated that, although he may 16 have expressed some concern about whether 17 criticality had occurred or not; and that's why he 18 wanted to make sure that whatever the arguments were 19 between the two, that the matter was settled, 20 because that --
and I don't recall it, but it could 21 have entered his conversation that -- whether it's 22 critical or not col 1d be a public affairs issue.
23 Again, I have a vague recollection
-- 24 that something like that may have occurred.
25 O. Based on that comment, did you ever see --
19
- - - a
4 1 feel the necessity to get back with Mr. Lenart to 2 find out how the problem resolved, was resolved?
3 A. No. What I did do, I talked to the head of 1
4 our nuclear engineering department and I asked him ,
l 5 to see if he could get the matter resolved because I l
6 the reactor engineer reported to him.
7 I asked him to make sure that the 1
'i 8 people weren't talking about an issue like the j 9 angels dancing on a head of a pin, whether it was a l
10 trivial issue or whether it was significant.
l 11 But I never heard back on that either, 12 and in retrospect I probably should have followed up i 13 more on the matter.
14 O. Who was tha nuclear engineering person? j 15 A. Bill Colbert.
1 16 O. Colbert? '
17 A. Colbert.
l 18 MR. LANG: How does he connect or interface with 19 Hari Arora?
20 THE WITNESS: The way we were organized at that 21 time, that's before we received the full power 22 license, we made on organizational change. But the 23 reactor engineers reported to nuclear engineering.
.- -- 24 And then on a day do day basis --
it.was very 25 similar to the STA's. STA's report to nuclear 20 u_______.__________ _ _ . _ _ _ _ . _
l I
1 engineering and are assigned to the shift.
(
. - 2 MR. LANG: Okay.
3 THE WITNESS: So that it's the responsibility of 4 nuclear engineering to train the reactor engineers, l 5 to make sure that they're qualified for what their.
I 6 job is, then assign them to'the shift. .l l
Then they take day to day directives
_7 8 from the shift supervisor.
! 9 MR. KALKMAN: Do you have anything else?
l 10 MR. LANG: No.
11 MR. KALKMAN: Mr. Jens, have I or any other NRC.
. 12 representative here threatened you in any way or I 13 l (_ offered you any reward in return for this s t a t em erit ?
14 THE WITNESS: No.
s 1 15 MR. KALKMAN: Have you given- this statement-1 16 freely an voluntarily? i 17 THE WITNESS: Yes, I have.
18 MR. KALKMAN: Is there anything further you care 19 to add for the record?
20 THE WITNESS: No, I don't.
21 MR. KALKMAN: Okay. Thank you very much.
22 l
23 iq 24
\
25 1
21
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L____._.______________.--- _ . - . _ _ _ _ _
i NO PAGE NUMBER l
CERTIFICATE OF' OFFICIAL' REPORTER I i
i l j
I>
This is to certify that the attached proceedings before the UNITED STATES NUCLEAR REGULATORY COMMISSION in the matter of: ,
NAME OF PROCEEDING: OFFICE OF INVESTIGATION INVESTIGATIVE INTERVIEW CLOSED 1
i DOCKET NO.:
1 I
1 1 1
l PLACE: GLEN ELLYN, IL l i
K DATE: . Tuesday, July 23, 1985 * '
) \
were held as herein appears, and that this is the original transcript thereof for the file of the United States Nuclear d Regulatory Commission.
1 (siet) s - / ,Wa (TYPED)
Lisa Jo.Selepa !
Official Reporter Sullivan Reporting' Company Reporter's Affiliation l
l 4
,4 m.
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