Transcript of Ofc of Investigation Investigative Interview (Closed Meeting) W/T Dong on 850730 in Newport,MiML20237J920 |
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Fermi |
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Issue date: |
07/30/1985 |
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NRC OFFICE OF INVESTIGATIONS (OI) |
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ML20237J518 |
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References |
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FOIA-86-245 LB-85-214, NUDOCS 8708260369 |
Download: ML20237J920 (24) |
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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
m---- -- -- - - - - - - - - - - -
a OR/GnyA_;
UN11EU STATES
)
1 NUCLEAR REGULATORY COMMISSION l
)
IN THE MATTER OF: DOCKET NO:
LB-85-214 '
0FFICE OF INVESTIGATION l 1
INVESTIGATIVE INTERVIEW I
(
(CLOSED MEETING) l l
l t .
\
LOCATION: NEWPORT, MICHIGAN PAGES: 128 i DATE: TUESDAY,-JULY.30, 1985 l i
O e g e-i e e
. ACE-FEDERAL REPORTERS, INC.
. 444 Capi Strtet whington,b.C.2coci /
(202)347-roo ,
_; . . . . _ w 8708260369 870019 ,,
' MN #N JTEh 86-245 PDR 9wsMi
a 1 UNITED STATES OF AMERICA 2 NUCLEAR REGULATORY COMMISSION i
1 3 (
I
)-
d In the Matter of: )
) Case No. LB-85-214 l 5 OFFICE OF INVESTIGATION )
1 INVESTIGATIVE INTERVIEW )
6 )
7 The Deposition of TOM DONG, taken 8
pursuant to Notice before me, Elizabeth Diann Ferguson, Notary l I
9 Public in and for the County of Wayne, (Acting in Monroe County),
10
{
at 6400 Dixie Highway, Newport, Michigan, on Tuesday, July 30, l 11 I 1985, commencing at about 5:05 p.m.
l n
?3
!l APPEARANCES:
J 14 UNITED STATES NUCLEAR REGULATORY COMMISSION Field Office Region III 15 jj 799 Roosevelt Road )
f Glen Ellyn, Illinois 60137 i 16 (By: James N. Kalkman, Esq.)
1 3 1? Appearing on behlaf of the Nuclear Regulatory Commission lI
.~. 18 JOHN H. FLYNN, ESO.
!! 2000 Second Avenue
- 19 Detroit, Michigan 48226 l 20 Appearing on behalf of Detroit Edison l ]
l 2i f
.t 22 23 24 (continued) i I i 2s i I
i i
1 APPEARANCES: -(continued) 2 PETER A. MARQUARDT, ESQ, 2000 Second Avenue 3 Detroit, Michigan 48226 4 pr.. waring on behalf of Detroit Edison 5
1 6 ALSO PRESENT: 1 7 Terrence Lang and Thomas Randazzo ;
8 9 '$
Elizabeth Diann Ferguson, CSR-1347 10 Court Reporter 11 12 13 14 15 16 E 17 l
18
- 19 i =
- 2 1
- 22 23 24 2S 2
l
-- _ - _ _ _ _ - _ - _ _ _ _ _ _ _ - - _ _ _ - l
4 i
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- .D_ E._ X__
Page 2 Witness l 3 Tom Dong 5
4 Examination by Mr. Kalkman 1
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5 6
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23 24 25 3
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1 1 Newport, Michigan l 2 Tuesday, July 30, 1985 ;
i 3 at about 5:05 p.m. l 4 _ . - !
5 MR. KALKMAN: For the record, this-6 is the interview with Tom Dong, D-o-n-g, who is employed I
7 by the Detroit Edison Company. The location of this i i
1 interview is the Fermi II Nuclear Power Station.
(
8 9 Present at this interview are Mr. Dong, 10 the Detroit Edison Counsels, Peter Marquardt and John Flynn; 11 Detroit Edison Director of Reactor Af fairs, Thomas Randazzo; 12 NRC Reactor Inspector, Terrence Lang; and NRC Investigator' 13 >
J unes KaIkman, I
'd As agreed, this interview is being 15 transcribed by Court Reporter Elizabeth Ferguson.
16 The subject matter of this interview 9
l 17 concerns the reactor operator error which occurred on g
18 July 1,1985, at the Fermi II Nuclear Power Station.
- 19 Mr. Dong, would you please stand and 20 raise your right hand?
l
.; 2, . . .
t
- 22 TOM DONG, 23 after having first been duly sworn to tell the truth, 24 the whole truth, and nothing but the truth, testified 25 upon his oath as follows:
4
1
=
1 2 EXAMINATION j
(
3 BY MR. KALKMAN:
1 4 Q Mr. Dong, how are you employed by Detroit Edison? )
5 A Do you want my title?
6 Q Yes, please.
7 A. I am a shift technical advisor.
I B Q And what are your responsibilities as a shift technical 9
}1 advisor?
10 A I provide technical advice to the operations' group on a 11 shift basis.
12 i 0 Could you give us an example of the type of technical t:
13 advice you may be asked to provide?
14 Well, it varies.
L ll A i
I
! 15 ' It could depend on the situation that i
16 is involved, 17 Well, give me one example of that.
I 0
I
- 18 A Well, valve interlocks.
f i
- 19 O Could you explain? Could you expand on that?
! I
- j. 70 A Well, if a valve does not open when it is required to,
- 21 f and they ask me to determine what the interlocks are, i
t 22 and advise them as to what to do to get them open.
23 0 Is that a licensed position?
24 3 .No, sir.
25 Q What qualifies you to be a shift technical advisor?
1 5 !
(~
l l
i e :
1 A well, I have attended and am qualified through the liccnsing i 2 program.
3 0 What licensing program is that?
- d. A One that they have here at Fermi II. ;
5 0 Are you required to have an engineering degree?
6 A Yes.
7 Q What type of degree do you have? ]i 8 A I have a Bachelor's of Science, Engineering; my major is !
9 thermo-mechanics.
! l 10 0 Where did you obtain that?
11 A The UniverJity of Illinois, Chicago.
12 Q Mr. Dong, how long have you been employed in the 13 Nuclear Industry?
I
'4 IA 1972, I was hired by Sergeant Alundy (phonetically), as h
15
'l mechanical draf tsman designer; and for the Byron Bragewood 16 (phonetically) project through 1974.
3 17 Okay. I began working at Detroit --
I g
18 well, as f ar as Nuclear experience, I picked it back up, 8 l
- 19 resumed that in 1980 at the Fermi Plant; but I was s
l 20 internally employed as a designer with a floor pioneer, l I i 21 j and I did some design work.
I 22 I worked on two fossile units.
23 Is Fermi II the first reactor experience, operating reactor Q
24 experience?
2s 6
I A Well, we took a short course while at Fermi at the l
. i
- University of Michigan Test reactor; and I'took a reactor I l l l 2 operator short course, and I don't know the title of the 1 .
4 course.
5 0 Okay. q 6 A Then we participated and attended the reactor start-up 7 system; also I spent a week at the Brownsville simulator E in the STA program there.
9 COURT REPORTER: I am sorry, sir.
I l to you will-have to speak up.
11 A Oh, I am sorry.
i 12 I am involved in the licensed operator
(
l 13 ji recall program here at Fermi; and we conduct start-ups II 12 !! on the simulators there. i l
15 I have been in the recall program for 16 over a year and a half, I believe.
i 17 - - -
I 18 BY MR. KALKMAN: !
I h 19 Q You were the shift technical advisor on the evening shift i :
j 20 on July 1, is that correct?.
- 21 A Yes.
22 Q The shift that started at 11:00 p.m.?
23 A Yes.
24 0 What do you recall from that particular shif t relating to 25 the operator error that we are here discussing?
7
1 A Well, where do you want me to begin?-
2 Q From the time you came on the shif t.
Well, I took relief. I went down to the shift supervisor's 3 A 4 office and attended a relief.
5 Q Pardon me?
6 A They give a turnover also.
7 Q Is there a meeting or something?
8 A Yes, a turnover meeting.
9 I don't recall right now what was- 1 to discussed at the turnover meeting, but I attended that.
11 After that, I toured the control services in the -- I l
12 was aware that they were beginning a -- continuing a start- )
l l
13 i up.
14 Sometime during the night, I took a 15 position behind the reactor operator, approximately eight 16 feet, six or eight feet behind, next to the shift
! 17 operational advisor.
$8 18 0 Who was that?
- 19 A Ed Duda.
j 20 0 Is that D-u-d-a? .)
'! 21 A Yes
,i 22 O okay.
23 A When I was made aware of -- I don't know what happened ;
24 between that and the time I was informed of the incident; 25 so I will just start with the incident:
8
~
I was watching various Plant parameters when John Dewes informed me that the operator had -- I 2 don't know the exact words, but it was -- he may have been out of sequence or the reactor operator was out of sequence.
- I asked him to explain, and he said j 8 that he had pulled some rods beyond position that was 7
required. Then he left.
8 Q Mr. Dewes left?
A Right.
Q Okay.
" I discussed that matter with Ed Duda the shift operational A
12 advisors and I believed we asked -- I think we looked over i
?3 to see what Group he was in or which rod Group he was in, l
u ! and Ed was familiar with the reduced notchworth procedure, l 15 i
and we discussed the matter -- well, let me back up.
I 16 I asked John if he was running rods 17 E
back to pattern, and be said yes. Then I went into a g
l discussion with Ed. We talked about t.he basis for the 19
" reduced notchworth procedure and if we had any problems with fuel damage or the possibility of any unusual safety
~
21 j concerns.
22 O okay.
A or the significance of the safety concerns, 2a Q Okay.
25 '
A And we concluded that it was none.
9 i
1 I was also surprised that I did not 2 notice any rod blocks were pulled;.and I went to look 3 for the reactor engineer to question him about that 4
situation. .
I 5 And who was-that, Barry Myers?
0 .)i 6 A 'Yes.
7 Q Okay.
8 A .That Group programs -- their Group programs the rod-worth-l 9 minimizer, which I expected to pull the rod block in that !
I
'O We discussed it with'him, it was determined situation. _ )
l 11 that it was not programmed in for that feature.
12 Q Let me stop you at this point then, and ask you some more )
'3 specific questions relating to that time frames i
.]
Apparently, you were not aware of is the rod pull error while it was occurring; is that correct?
j 18 A Well -- !
E 5 " Q You became aware of it abortly after?
18 A Yes, sir.
g 19 0 While they were re-inserting the Group III rods? j 20 l A I am not really sure of the time frame.
21 I Q It was shortly thereafter, though?
r 22 A Yes, sir, i 23 Okay, 0 j 24 And Mr. Dewes made you aware of that?
25 3 y,,,
10 I
l 3
MR, LANG: At any time durisg the 2 shif t, were you ordered or sent out of the Contr ol Room?
3 A No.
4 MR. LANG: Were you anywehre in the 5
Control Room on control area all evening?
l Not the whole evening. j 6 A 7
We went upstairs to make out my logs.
l 8 MR. LANG: Wehre is upstairs? l I
l 9 A That is where my office is above the research tagging {
i 10 center.
11 MR. LANG: During the evening after the 12 rods were re-inserted, was there any discussion at all 13 i between yourselves and the STA in training or the shif t 14 supervisor, of criticality?
15 A No, I did not discuss criticality with them.
16 MR. LANG: How about the SOA?
8 6 17 A No, I cannot say, because I don't know.
6'
. 18 MR. LANG: Would you say there was
- 19 any major discussions going on at all during the evening?
j zo A Concerning what?
21 MR. LANG: The rod pull and criticality
- and the possibility of criticality.
22 23 A Well, can you be more specific?
24 MR. LANG: I mepn, any discussion 25 involving more than, say, two people?
11
)
' Well, there were some discussions -- we were in such A
2 close quarters, that some discussion overflowed into .
1 others.
1
' I I was standing next to Ed Duda 6
discussing the notchworth basis, and to my right, Ed Duda --
6 no,.not Ed Duda, but Ed Dewes was discussing with 7
Barry Myers.
8 i And that is when I posed the question 8 about the rod-worth-minimizer to Barry Myers.
'O You posed a question?
MR. LANG:
' What was the question?
' About the ennstriints of the program and why it did not A
block and things like that. I don't know.if you can say-1 14 '
that it was created through a discussion between the two 15 participants, we were in such close quarters, individuals-16 are discussing different things. J
=
3 17 _
'g BY MR. KALKMAN: !
19 Q Did you overhear a discussion between Mr. Dewes and i
i Mr. Myers relating to whether the Plant had gone critical?
21 l A No.
22 Q To your knowledge, that question did not come up during the shift?
24 A It did not come up.
25 Q Okay. ,
12
~ _ - - - - - _ _ _ - _ _ _ _ _ _ _ _
i i
' Did you ever have any discussion with i
{
l 2 the STA in training that evening? l 3 A Just about when he informed me that the rod pull was out 1
4 s equence.
of .. l 5
0 What individual -- who is the STA in training again?
6 A John Dewes.
i 7
O Did John Dewes relate that he thought the Plant had gone 8 critical? )
9 A Not to me.
l 10 MR. LANG: During the shift, did the l
'l RO or the NSO as you call them or the NSS, ever show you 12 the rod pull sheet and inform you of the error and the l
'3
- number of rods -- .
i
" A I don't recall.
15 I remember glancing over. We were so 16 close, I remember glancing over and seeing it.
t
' '7 MR. LANG: So you say that you were
'8 aware of the number of rods that were pulled out of l
- 19 sequence?
20 A No.
t
- 21 MR. LANG: You were not?
r 22 A No.
23 MR. LANG: Okay.
24 Not the exact numbers, no.
> A 25 MR. LANG: All right.
13
I.
3 But you ware aware of same of them?
'2 A Yes.
3 MR. LANG: Okay.
4 Thank you.
5 6 BY MR. KALKMAN:
7 Q Were you asked for any technical advice that evening, !
l B the evening of July 17 l
9 A By whom?
10 Q By anyone.
11 A That entire evening?
i 12 O Yes. j 13 A Well, we had a problem with the water level, and I went 14 to investigate that problem.
15 Q A problem with the water level, what was the problem with 16 the water level?
i 17 A Well, af ter the Start-up, we had some indication that the j lI .
18 water level was fluctuating greatly.
- 19 Well, we had some, I think 10-inch swings s
20 on the narrow edge, swings of level, fluctuations, and I l
21 went to investigate that.
22 O What did you find out?
23 A Are you asking me if I discovered the root cause?
24 0 Yes.
25 A No, I did not discover the root cause.
14
t I made a best guess.
2 Q What was your best guess? ,
3 A Control problems with the. start-up of the control valve, 4 control problems with a level control valve, possible 5 piping, which was, I think --
6 Q Did you report this in your log?
7 A Yes.
B Q Is this similar to the problems that occurred the water 9 level problem that occurred a week or so later, where 10 they had a reportable event?
11 A I don't believe so.
12 Q Are you aware of that later event that I am referring to?
13 A No.-
l 14 I don't know the specific date, but I think it was --
l 0 15 A I don't believe it was the some. It was not the same 16 sechanism.
3 17 0 Who asked your advice regarding the water level fluctuation?
- 18 A I don't recall.
- 19 Q Did you have any discussion with shift supervisor, i
j 20 David Aniol, on the evening of July 1, or the early morning
- 21 of July 27 r
22 ' A I had a brief discussion with him about -- just to make 23 sure that he was aware that the out-of-sequence problem 24 did occur as I understood it.
75 Q And what did he say?
. 15
1 A He said that he waa aware of it.
2 O That was it, the conversation was that brief or that to 3 the point? .,
1 4 A Yes.
5 0 Did you ask him if he knew of the rod pull sequence error 6 as you understood it?
7 A Yes, 8 0 How did you understand it?
I 9 A I asked him if he was aware that some rods were pulled l 10 out of sequence, and ha said yes.
11 0 Is there some reason,-- do you feel reluctant to be 12 candid with us at this interview?
13 ,A I don't understand.
14 0 I get the impression that you are reluctant to be open i 15 in this discussion. I feel like I am prying answers out 16 of you.
a 17 A Well, can you be more specific?
I' 18 Q No, but if I do come up with something specific, I will
- 19 let you know.
20 Okay.
21 A Okay.
i 22 Q So you checked out a water level fluctuation that evening.
23 Did you know anything else during that 24 shift that you might want to tell us about?
25 Why don't you just summarize the events 16
1 that -- your actions that evening, just briefly summarize 2 what you did during that shift.
3 A well, I observed the start-up, the Plant start-up.
d Q Could you speak up a little bit? We are having a hard l
5 time hearing you.
j 6 A Okay.
J 7 I observed the Plant start-up. I 8 think also that night the instrument man had some problems f 9 with a cable problem, and the water level problem. i 10 That is all I recall. l I
11 O Okay. ]
l 12 Let me make sure that I understand )
13 what you said from our discussion. 1 14 You first became aware of the rod 15 sequence pull error, that was when Mr. Dewes advised you l
16 of the error? )
3 17 A Yes.
1 18 Q And this was sometime af ter the error occurred? j
- 19 A Yes.
l 20 0 Sometime af ter the re-insertion of the Group III rods or i 21 during the re-insertion of the Group III rods?
! 22 A Yes.
23 Q And you had a brief discussion with Mr. Duda relating to i 24 the rod pull sequence arror?
25 A Yes.
I 17
1 O And that was -- ,
2 Just tell me about those conversations 3
that you had with Mr. Dewes and Mr. Duda, i
A Well, Mr. Dewes, he informed me -- I asked him if he was l 5
getting rods back into the pattern and he said yes, or 6
he nodded. I got an affirmative.
7 Then he left. In the. discussion with 1
8 Mr . D ewes , it was concerning the basis with the notchworth 8
procedure and his experience over at Nine Mile Point.
10 MR. LANG: At any time during the evening M
did you or anybody else that you know of, ' Pull back the 12 charts and take a look at the charts?
13 A I did not.
14 MR. LANG: Do you know of anyone else 15 that did?
16 A No, I don't. I don't know.
5 17 MR. LANG: Did you or the SOA, Mr. Duda, I
18 g discuss criticality?
- 19 g yo, t
20
{' MR. LANG: Okay. Thank you.
2, '
l . . .
s r
22 BY MR. KALKKAN:
23 O Did the issue of whether the Plant went critical, did that 24 cross your mind at all because of the rod pull error?
25 A No, it was never --
18
_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ ]
I i
1 Q And in your discussion with the shift supervisor, 2
Mr. Aniol, it was merely to find out if he knew of the- ]
)
3 rod pull error? l l
l 4 A Yes. 4 l 5 Q And there was no discussion at that point of criticality? l l
6 A Right. i 1
l 7 Q Was anyone else surprised that the rod-worth-minimizer a did not block this rod pull error, other than yourself? l l 9 A Ed Duda -- well, I don't know.
l l
io o Well, why did you think that t.he rod-worth-minimizer should 11 i have blocked -- are you familiar with rod-worth-minimizers 12 from other plants, or did you just think that --
13 !A From my training.
I 14 00 The simulator training here? 3 i
h 15 A Well, no, not simulator training, but the systems training.
16 Q Should it have been programmed to stop that error, block
- i I E 17 k that error?
l I
18 A I don't know.
.h
- 19 0 Okay, I MR. LANG
- During the evening, the j 20 21 discussions about the out-of-sequence pull, did you feel l
' i
- that it was a fairly significant error?
22 l 23 A Not at that time, no.
24 MR LANG: Not at that time?
25 A No.
19 l
l j
1 MR. LANG: Did you feel like it was 2 something that you should have logged?
J 3 A No, not at that time.
4 MR. LANG: Okay. Thank you.
3 l
Y 6 BY MR. KALKMAN:
7 Q Does your 109 reflect the rod pull error? j 8 A P' No, it does not.
9 Q Did .you have any input to the DER that was initiated? s i
10 A No.
11 O You did not have any input? j 12 A No.
13 I would like to add that our logs, 14 the type of material that we put in our logs are not 15 necessarily the type of material that -- sometimes it is 16 not the type of situation that NSS would place in its 109 i 17 We used it as a turnover mechanism. l I
18 We have some specificity with the operational issue, some i !
- 19 other things that might be used for the future.
I Were you present when the rod-worth-minimizer alarm went off?
j 20 Q f 21 A No.
i r
. 22 Q Did you become aware of that occurring?
23 A Yes.
24 O Do you;know why that alarm want off?
25 A No.
20
1 1
q
'i
[
l
, f0 That was at the end of the Group II, the rod group?
2 A I don t know.
i 3
O Who made you aware of the alarm? l d
A I saw the alarm.
5 You were.present then?
0 6 A No, I walked into the room and saw the alarm, it was still on .
7 Q It was still there?
8 g y,,,
9 0 Did you investigate that problem?
10 A Well, I asked the operator'if he was out of sequence, if
'I he was giving the rods out of sequence, and he said no.
12 O Is that normally what would have sounded that alarm?
13 A Yes, if you pull a rod out of sequence.
14 He was pulling from 0 to 48 in Group II, Q
i 15 Is there any reason why the rod-worth-f d
16 minimizer would block that pull?
17 I don't know.
l ;A g
18 0 Well, if he pulled the rods too fast or something like that,
- 19 would that cause the rod-worth-minimizer to block it?
I !
j 20 ]A Can you repeat that question again? I l 21 g yes,
! 22 l The Group II rods that the operator 23 was pulling from 0 to 48 continuous, if he was pulling 24 the rods too fast, would that activiate the rod-worth-25 minimizer?
I 21
1 A No.
2 Q And that has nothing to do with it? i 3 A That is correct.
4 0 Did anyone else in the Control Room investigate the reason 5 for the rod-worth-minimizar alarm?
6 A I don't know.
7 0 Do you know if the rod-worth-minimizer was de-activated 8 after the alarm?
9 A Af ter the alarm, I don't know.
10 0 who is responsible for investigating a problem or an 11 indication of a rod-worthmsinimizer block?
12 A The Control Room operator.
I !
l 13 I And if a Control Room operator needs some technical advice, lQ 14 6 would he go to you or the reactor engineer?
l U
1 15 A well, it would depend on his choice, 16 Q His choice?
s i 17 A Well, what he decides to ask.
'! 18 He may ask me, he may ask the reactor 19 engineer, I don't know.
l 20 Q So you were not present when it occurred, so do you know
- 21 if the operator asked someone else about it?
22 A No, I don't.
23 MR. KALKMAN: I don't have anything 24 else for you at the mament, but we may want to talk to 25 you again, based on information we obtain from your 22 w________-_________
---,=m a. n I co-workers.
2 But I will close with, Mr. Dong, have l
l 3 I or any other NRC representative either threatened you l-4 in any mEnner Of Offered you any reward iD return for your l
5- statement?
l 6 A No.
7 MR. KALKMAN: Have you given the jl 8 statement freely and voluntarily?. i i
9 A Yes.
I 10 MR. KALKMAN: Is there anything further l
11 you care to add for the record? l I
l 12 A No. j 13 MR. KALKMAN: Thank you.
14 (Deposition concluded at 5:45 p.m.)
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16 l l 2
17 18
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22 23 24 25 23
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