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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M0721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Pass Dates ML20217D8361999-10-11011 October 1999 Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999 ML20217F8271999-10-0707 October 1999 Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L0061999-10-0101 October 1999 Discusses GL 97-06 Issued by NRC on 971231 & Gpu Response for Three Mile Island .Staff Reviewed Response & Found No New Concerns with Condition of SG Internals or with Insp Practices Used to Detect Degradation of SG Internals ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212K8771999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Three Mile Island on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Provides Historical Listing of Plant Issues & Insp Schedule ML20212K8551999-09-30030 September 1999 Informs That During 990921 Telcon Between P Bissett & F Kacinko,Arrangements Were Made for Administration of Licensing Exams at Facility During Wk of 000214.Outlines Should Be Provided to NRC by 991122 ML20216J6581999-09-28028 September 1999 Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212J0011999-09-27027 September 1999 Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A2101999-09-13013 September 1999 Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2 ML20216G4151999-09-0909 September 1999 Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans ML20211M5861999-09-0202 September 1999 Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld ML20211M6591999-09-0101 September 1999 Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates ML20211H3731999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl ML20211H4001999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211H5041999-08-20020 August 1999 Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld 05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999 Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface ML20211A4261999-08-19019 August 1999 Forwards Insp Rept 50-289/99-04 on 990606-0717.Two Severity Level 4 Violations Occurred & Being Treated as Noncited Violations ML20211H3571999-08-19019 August 1999 Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019 ML20211A3931999-08-12012 August 1999 Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports ML20210R4691999-08-11011 August 1999 Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages ML20210N7601999-08-10010 August 1999 Informs That NRC Staff Reviewed Applications Dtd 990629, Which Requested Review & Approval to Allow Authority to Possess Radioactive Matl Without Unit Distinction Between Units 1 & 2.Forwards RAI Re License Amend Request 285 ML20210N7191999-08-0606 August 1999 Forwards Notice of Partial Denial of Amend to FOL & Opportunity for Hearing Re Proposed Change to TS 3.1.12.3 to Add LCO That Would Allow Continued HPI Operation ML20210L3831999-07-30030 July 1999 Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage ML20210K7371999-07-30030 July 1999 Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46 ML20210L1151999-07-28028 July 1999 Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1 05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999 Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section ML20216D4001999-07-22022 July 1999 Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999 ML20210B8231999-07-21021 July 1999 Forwards Exemption from Certain Requirements of 10CFR50.54(w) for Three Mile Island Nuclear Station,Unit 2 in Response to Licensee Application Dtd 990309,requesting Reduction in Amount of Insurance for Unit to Amount Listed ML20210G9471999-07-15015 July 1999 Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl ML20209H9401999-07-15015 July 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Application for Exemption Dtd 990309. Proposed Exemption Would Reduce Amount of Insurance for Onsite Property Damage Coverage as Listed ML20209G2451999-07-15015 July 1999 Advises That Suppl Info in Support of Proposed License Transfer & Conforming Adminstrative License Amends,Submitted in & Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident ML20216D9861999-07-12012 July 1999 Forwards RAI Re 981019 Application Request for Review & Approval of Operability & SRs for Remote Shutdown Sys. Response Requested within 30 Days of Receipt of Ltr ML20209G5861999-07-0909 July 1999 Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted ML20209F2571999-07-0909 July 1999 Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1 ML20209D8451999-07-0808 July 1999 Forwards Insp Rept 50-289/99-06 on 990608-11.No Violations Noted.Overall Performance of ERO Very Good & Demonstrated, with Reasonable Assurance,That Onsite Emergency Plans Adequate & That Util Capable of Implementing Plan ML20209D6291999-07-0808 July 1999 Forwards Notice of Withdrawal & Corrected TS Pages 3-21 & 4-9 for Amend 211 & 4-5a,4-38 & 6-3 for Amend 212,which Was Issued in Error.Amends Failed to Reflect Previously Changes Granted by Amends 203 & 204 ML20209D5141999-07-0808 July 1999 Forwards RAI Re 981019 Application & Suppl ,which Requested Review & Approval of Revised Rc Allowable Dose Equivalent I-131 Activity Limit with Max Dose Equivalent Limit of 1.0 Uci/Gram.Response Requested within 30 Days 05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999 Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public ML20196J3981999-07-0101 July 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl ML20209C1131999-07-0101 July 1999 Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D8361999-10-11011 October 1999 Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999 ML20217F8271999-10-0707 October 1999 Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans ML20216J6581999-09-28028 September 1999 Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A2101999-09-13013 September 1999 Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2 ML20216G4151999-09-0909 September 1999 Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans ML20211M5861999-09-0202 September 1999 Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld ML20211M6591999-09-0101 September 1999 Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error ML20211L2401999-09-0101 September 1999 Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates ML20211H3731999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl ML20211H4001999-08-27027 August 1999 Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj 05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999 Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface ML20211H5041999-08-20020 August 1999 Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld ML20211H3571999-08-19019 August 1999 Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019 ML20211A3931999-08-12012 August 1999 Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports ML20210R4691999-08-11011 August 1999 Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages ML20210L3831999-07-30030 July 1999 Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage ML20210K7371999-07-30030 July 1999 Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46 ML20210L1151999-07-28028 July 1999 Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1 05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999 Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section ML20216D4001999-07-22022 July 1999 Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999 ML20210G9471999-07-15015 July 1999 Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl ML20212K1701999-07-13013 July 1999 Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident 05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999 Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public ML20196J3981999-07-0101 July 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl ML20209C1131999-07-0101 July 1999 Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License ML20196J7651999-06-29029 June 1999 Provides Updated Info Re Loss of Feedwater & Loss of Electric Power Accident Analyses to Support TS Change Request 279 Re Core Protection Safety Limit,As Discussed at 990616 Meeting ML20196J7701999-06-29029 June 1999 Forwards LAR 285 for License DPR-50,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls May Continue to Be Moved Between TMI-1 & TMI-2 Units ML20209C0391999-06-29029 June 1999 Forwards LAR 77 to License DPR-73,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-2 License to Amergen,Radioactive Matl May Continue to Be Moved Between TMI-1 & TMI-2 Units ML20196G2061999-06-23023 June 1999 Requests That NRC Update Current Service Lists to Reflect Listed Personnel Changes That Occurred at TMI 05000289/LER-1999-006, Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements1999-06-23023 June 1999 Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements ML20196D2171999-06-17017 June 1999 Forwards Pmpr 99-9, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508- 0604.New Summary Personnel Table Was Added to Rept Period.Matl Scientist Joined Staff Period ML20196A0431999-06-15015 June 1999 Providess Notification That Design Verification Activities Related to Calculations Supporting Analytical Values Identified in Gpu Nuclear Ltr to NRC Has Been Completed 05000289/LER-1999-004, Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT1999-06-0909 June 1999 Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT ML20212K2541999-06-0808 June 1999 Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident ML20212K2671999-06-0808 June 1999 Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident ML20195E2751999-06-0404 June 1999 Informs That PCTs & LOCA Lhr Limits Submitted in Util Ltr for LOCA Reanalysis Performed in Support of TMI-1 20% Tube Plugging Amend Request Have Been Revised.Revised PCT & LOCA Lhr Limit Values Are Provided on Encl Table 1 ML20195E3281999-06-0404 June 1999 Forwards Application for Amend to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20195C5721999-06-0202 June 1999 Forwards Description of Gpu Nuclear Plans for Corrective Actions for 1 H Fire Barriers in Fire Zones AB-FZ-3,AB-FZ-5, AB-FZ-7,FH-FZ-2 & Previous Commitments for Fire Zones CB-FA-1 & FH-FZ-6 ML20207E2561999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Change in ECCS Analyses at TMI-1 ML20195B2461999-05-21021 May 1999 Forwards Itemized Response to NRC 990506 RAI for TS Change Request 279 Re Core Protection Safety Limit ML20206R6461999-05-13013 May 1999 Forwards Rev 39 of Modified Amended Physical Security Plan for TMI 05000289/LER-1999-003, Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC1999-05-0707 May 1999 Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC ML20206K6301999-05-0707 May 1999 Provides Addl Info Re TMI-1 LOFW Accident re-analysis Assumptions for 20% Average SG Tube Plugging as Discussed on 990421 ML20206H0781999-04-30030 April 1999 Forwards Rev 0 to 1092, TMI Emergency Plan. Summary of Changes Encl ML20206J4811999-04-30030 April 1999 Provides Summary of Activities at TMI-2 During First Quarter of 1999.TMI-2 RB Was Not Inspected During Quarter.Routine Radiological Surveys of Auxiliary & Fuel Handling Bldgs Did Not Identify Any Significant Adverse Trends ML20206E4121999-04-27027 April 1999 Requests That TS Change Request 257 Be Withdrawn ML20206C5211999-04-23023 April 1999 Requests Mod to Encl Indemnity Agreement Number B-64,on Behalf of Gpu & Affiliates,Meed,Jcpl,Penelec & Amergen Energy Co,Llc.Ltr Supersedes & Withdraws 990405 Request Submitted to NRC ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 1999-09-09
[Table view] Category:LEGAL/LAW FIRM TO NRC
MONTHYEARML20245D6071989-03-27027 March 1989 Forwards Endorsements 113 & 114 to Nelia Policy NF-220, Endorsements 133 & 134 to Nelia Policy NF-164,Endorsement 143 to Nelia Policy NF-1 & Endorsement 86 to Nelia Policy NF-195 ML20245D3421989-03-20020 March 1989 Forwards Listed Endorsements,Including Endorsements 14,163, 144,94,75,39 & 31 to Nelia Policies NF-295,NF-100,MAELU Policy MF-29,NELIA Policy NF-182,MAELU Policy MF-61,NELIA Policy NF-281 & Maelu Policy MF-112,respectively ML20235T8911989-01-18018 January 1989 Forwards Endorsements 130 & 131 to Nelia Policy NF-164, Endorsements 107 & 108 to Maelu Policy MF-44,Endorsements 94 & 95 to Nelia Policy NF-107,Endorsements 110 & 111 to Nelia Policy NF-220 & Endorsements 97 & 98 to Maelu Policy MF-73 ML20155F3881988-10-0505 October 1988 Forwards Endorsements 108 & 109 to Nelia Policy NF-220 & Endorsements 95 & 96 to Maelu Policy MF-73 ML20155A2501988-06-0303 June 1988 Forwards Endorsements 4 & 4 to Nelia Certificate NW-78 & Maelu Certificate MW-18 & Endorsements 3 & 3 to Nelia Certificate NW-125 & Maelu Certificate MW-46,respectively ML20154K8561988-05-18018 May 1988 Forwards Endorsements 93 & 94 to Maelu Policy MF-73 & Endorsements 106 & 107 to Nelia Policy NF-220 ML20148N5151988-03-30030 March 1988 Forwards Endorsements 1 & 2 to Maelu Certificate MW-46 & Nelia Certificate NW-125 ML20148K1111988-03-22022 March 1988 Forwards Listed Endorsements to Listed Policies,Including Endorsement 102 to Maelu Policy MF-26,Endorsement 123 to Nelia Policy NF-76,Endorsement 71 to Maelu Policy MF-56 & Endorsement 89 to Nelia Policy NF-189 ML20236N8881987-11-0606 November 1987 Forwards Joint Motion for Approval of Settlement Agreement & for Termination of Proceeding,Per Discussions Between Util & NRC in Response to 871002 Order.Svc List Encl ML20236A0041987-10-13013 October 1987 Forwards Usc Comment on Proposed Rule 10CFR50 Re Proposed Rev of Backfitting Process for Power Reactors ML20235J0031987-09-21021 September 1987 Forwards Endorsements 122 & 123 to Nelia Policy NF-164, Endorsements 99 & 100 to Maelu Policy MF-44,Endorsements 100 & 101 to Nelia Policy NF-220 & Endorsements 87 & 88 to Maelu Policy MF-73 ML20236E6991987-07-28028 July 1987 Forwards Consent Motion & Proposed Order & Affidavit of Nondisclosure Agreed to by G Johnson & Jp Hickey by 870728 Telcon.Mod Incorporated Subsequent to 870723 Version Included.Served on 870729 ML20235N7431987-07-0707 July 1987 Forwards Endorsements 98 & 85 to Nelia Policy NF-220 & Maelu Policy MF-73,respectively ML20235D6741987-07-0606 July 1987 Forwards Rev of Recipient Proposed Stipulations to Obviate Need for Appearance of AB Beach as Staff Witness,Per Request.Desire to Explore Subj Expressed.W/O Stated Encl. Service List Encl.Related Correspondence ML20215D6311987-06-11011 June 1987 Requests That NRC Identify,By Name,All Individuals to Whom Request for Admission Number 102 Refers & Identify Basis for Making Such Allegation.Related Correspondence ML20215D6551987-06-11011 June 1987 Forwards Affirmation for Util Partial Response to NRC Staff First Request for Admissions.Certificate of Deponent & Transcript Corrections for J Barton 870407 Deposition Encl. Related Correspondence ML20215J6731987-06-10010 June 1987 Forwards Payment to Meeks Which Represents Allowable Witness Travel & Subsidence Fees.Related Correspondence ML20214R9871987-06-0101 June 1987 Forwards Notice of Deposition of Rd Parks,Inadvertently Omitted from Friday Transmittal.Related Correspondence ML20214S1231987-05-29029 May 1987 Confirms 870528 Conversation Re Agreement to Postpone Beach Deposition,Previously Noticed for 870601,to Enable Further Consideration of Stipulated Testimony Which May Obviate Need for Beach to Appear.W/Svc List.Related Correspondence ML20234F3251987-05-27027 May 1987 Appeals Denial of FOIA Request for Bb Hayes on Individual Operator Actions Re Falsification of Leak Rate Test Data at Facility ML20214E3101987-05-11011 May 1987 Forwards Endorsements 120 & 97 to Nelia Policies NF-164 & NF-220 & Endorsements 97 & 84 to Maelu Policies MF-44 & MF-73,respectively ML20205R4751987-04-0101 April 1987 Informs That R Arnold,B Kanga & J Barton Deposed in 1984 by King Counsel Addressing King Involvement W/Quiltec & Related Info.Depositions Available Upon Request.Related Correspondence ML20212C7991987-02-18018 February 1987 Forwards Endorsements 93 & 81 to Nelia Policy NF-220 & Maelu Policy MF-73,respectively ML20211A0911987-02-16016 February 1987 Advises That Herbein Declines Board Invitation in Request & Order to Comment on Numerous Employees Memorandum of Law Re Inquiry Into TMI-2 Leak Rate Data Falsification ML20214X3211986-11-0505 November 1986 Appeals Denial of FOIA Request for 860912 Memo from Ja Fitzgerald to Ofc of Investigations Re Investigation of Individual Actions Concerning Leak Rate Data Falsification Data at Facility ML20203N8791986-10-14014 October 1986 Forwards Licensee to NRC Re Change Request 148. W/Svc List.Related Correspondence ML20210S8941986-10-0202 October 1986 Forwards MPR Assoc,Inc Providing Estimate of Percentage of Billable Hours Attributable to Work Performed for Util ML20215B5801986-09-30030 September 1986 Forwards Listed Items of Evidence Including Annotated Computer Printouts for Leak Rate Tests 147,146 & 145 on 781018 & Strip Chart Traces Showing Effects of Hydrogen Additions in Instances When Leak Rate Tests Not Performed ML20214R6491986-09-23023 September 1986 Forwards Employees for Witness Hw Hartman Proposed Impeachment Questions,For Info.Requests That Questions Be Withheld from All Parties Prior to Hw Hartman Testimony.W/O Encls.Related Correspondence ML20206S2701986-09-17017 September 1986 Notifies of Address Change Effective on 860927.Requests Address on Encl List of Dockets Be Changed ML20214P9291986-09-16016 September 1986 Forwards GP Miller Proposed Questions for Eh Stier.W/O Encl. Related Correspondence ML20211C6091986-09-12012 September 1986 FOIA Request for Records Re Investigation Rept on Individual Operator Actions on Falsification of Leak Rate Test Data at TMI-2 and Documentation of Conversations Between NRC & DOJ ML20214M6371986-09-0808 September 1986 Advises of Util Decision Not to File Findings in Response to Proposed Findings of Other Parties.Util 860815 Proposed Findings Stand.Certificate of Svc Encl.Related Correspondence ML20209H6251986-09-0303 September 1986 Forwards Endorsements 91 & 92 to Nelia Policy NF-220 & Endorsements 79 & 80 to Maelu Policy MF-73 ML20203M6841986-08-27027 August 1986 Forwards Proposed Questions of Jg Herbein for D Haverkamp. Jg Herbein Requests That Questions Not Be Provided to D Haverkamp Prior to Appearance Before Board.Related Correspondence ML20203L4601986-08-22022 August 1986 Forwards Prepared Statements of RR Booher,Cl Guthrie & Wh Zewe Re Leak Rate Data Falsification.Related Correspondence ML20203L2021986-08-21021 August 1986 Forwards Prepared Statements of Kr Hoyt,Ba Mehler & Fj Scheimann Re Inquiry Into Leak Rate Data Falsification. Related Correspondence ML20203L2281986-08-20020 August 1986 Lists Proposed Addl Agenda Items for 860825 Prehearing Conference,Including Opening Statements by Parties at Start of Technical & Individual Responsibility Testimonies,Per Request.Related Correspondence ML20205F3861986-08-16016 August 1986 Forwards C Husted Proposed Findings of Fact & Conclusions of Law for Filing in Proceeding.W/O Encl.Related Correspondence ML20205F5801986-08-15015 August 1986 Forwards Employee Prepared Statements.Statements of Booher, Guthrie,Hoyt,Mehler,Scheimann & Zewe Will Be Filed When Available.Time Extension Requested.Certificate of Svc Encl. Related Correspondence ML20205F4261986-08-15015 August 1986 Forwards Proposed Findings of Fact & Conclusions of Law in Form of Recommended Initial Decision.W/Certificate of Svc ML20205F6591986-08-15015 August 1986 Forwards Testimony of GP Miller Re Inquiry Into Facility Leak Rate Data Falsification.Related Correspondence ML20205C2161986-08-0808 August 1986 Informs That JW Garrison & Rs Hutchison Held Position of Shift Foreman/Shift Supervisor During 780930-790328,per ASLB 860801 Memorandum & Order.Related Correspondence ML20204F7941986-07-30030 July 1986 Notifies That on 860729,US District Court for Middle District of State of PA Granted Motion for Suppression of Info Re Inquiry Into Leak Rate Data Falsification.Goldberg Will Advise NRC of Contents of Sealed Order ML20207J6881986-07-25025 July 1986 Forwards Response to Motion to Suppress Re Inquiry Into Facility Leak Rate Data Falsification,Per ASLB 860604 Protective Order.W/O Encl ML20203E5181986-07-22022 July 1986 Informs That Representation Made by Licensee in 860717 Motion for Deferral of Hearing Schedule Re Objection to Proposed Schedule,Premature & Not Formalized by Staff.Staff Will Advance Position in Answer to Motion ML20207J8211986-07-21021 July 1986 Forwards Proposed Employee Questions to Be Put to Stier, Russell,Capra,Rockwell,Kirkpatrick & Wermiel Per Board 860522 Order.W/O Encl.Related Correspondence ML20207E5461986-07-18018 July 1986 Forwards Response to Aamodt 860630 Response to Ofc of Investigations Rept & Motion for Summary Disposition,For Filing in Inquiry Into Leak Rate Data Falsification Proceeding ML20207D9681986-07-18018 July 1986 Forwards Proposed Corrections to Transcript of Evidentiary Hearing Re Gpu.Certificate of Svc Encl ML20207E7721986-07-18018 July 1986 Forwards Husted Proposed Corrections to Transcript of 860623-26 & 0701 Hearings.W/O Encl.Related Correspondence 1989-03-27
[Table view] |
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- seof aannerten see o C August 23, 1983 wR TER'S DeRECT DaAL NuMSER 822-1026 Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Meted (TMI-1), Docket No. 50-289
Dear Mr. Denton:
In your memorandum to your principal Staff members, dated July 11, 1983, you outlined the plans for NRR review of the GPU v. B&W lawsuit documents. Among other things the memorandum stated that "DL will contact and, if appro-priate, will meet with outside organizations (e . g. Con-gressional Staff and hearing intervenors) to obtain their comments" on those documents. Similarly, by memorandum dated June 30, 1983, Staff counsel advised that counsel was planning to telephone each party to the TMI-1 restart proceeding in order to obtain identification of any of the litigation documents which the parties believe to be per-tinent to the Staff review.
Licensee has apprised its counsel in the litigation, who are familiar in detail with the documents in question, of the NRC's ongoing review of the litigation documents and areas of particular interest as evidenced by pleadings filed in the Restart Proceeding. One such particular area of in-terest is the so-called " Mystery Man" issue and the question 8308250116 830823 n o PDR ADOCK 05000289 y I G pgg l \
3 SHAw, PITTMAN, PoTTs & TROWBRIDGE A PARTNEnsa4sp Or enOFEss10NAL COppOmATsONS Harold R. Denton August 23, 1983 Page Two of actuation of HPI following the TMI-2 accident. For your information I enclose a copy of a memorandum on this subject prepared by Kaye, Scholer, Fierman, Hays and Handler, dated August 16, 1983. Other memoranda, as appropriate, will be forwarded to the Staff for use in its review.
On behalf of Licensee, we request that undersigned counsel be notiflad of, and have an opportunity to attend, any meeting which your Staff or NRC counsel may have with any "outside organizations," including Congressional Staff and hearing intervenors, for the purpose of identifying or obtaining comments on any of the GPU v. B&W lawsuit docu-ments pertinent to your review.
Since rely, SH 1 PITT ,P TS & TROWBRIDGE gi eo e F. T owbridge Counsel for Licensee cc w/ encl: Mary E. Wagner, Esq.
MEMORANDUM ON THE 5:41 HPI ACTUATION
" MYSTERY MAN" ISSUE August 16, 1983 i
1
INTRODUCTION The first reference to a so-called " Mystery Man" was in the opening statement in the GPU v. B&W trial by B&W's counsel, who coined the phrase in the context of his argument that (1) there was evidence in prior testimony that high pres-sure injection ("HPI") was actuated at about 5:41 a.m.; (2) if HPI had been maintained at that time, the core would not have been uncovered; and (3) since no one testified to having turned off HPI near that time, there must have been a " Mystery Man" who did so.1 Prior to this assertion by B&W's counsel, none of the studies and investigations by the NRC and other indepen-dent bodies had found or even speculated as to the presence of a so-called " mystery man" in the control room. After the ar-gument was raised at trial, GPU's trial counsel retained EDS Nuclear Inc., a firm of expert consultants, to perform an analysis of this issue. The EDS study conclusively deter-mined, on the basis of hydraulic analyses, that there had been no actuation of high pressure injection during the time period in question. Since the high pressure injection was proven by scientific analysis not to have been actuated at about 5:41 a.m., no " mystery man" turned it off.
1 Trial tr. 148-49, 159.
i
THE EDS ANALYSIS EDS Nuclear Inc., an engineering consulting firm with an expertise in thermohydraulic analysis, provides engi-neering, design and analysis services to the electric power industry.2 The EDS analysis of the alleged 5:41 full flow ac-tuation of high pressure injection was conducted by Dr. James Holderness, who is the manager of an EDS group specializing in thermohydraulic analysis.3 Dr. Holderness' qualifications to perform the analysis consisted of ten years' past experience in performing hydraulic analyses, including seven years with Combustion Engineering, where Dr. Holderness was responsible for performing analyses in support of licensing applications for nuclear power plants and for verifying the efficacy of the models used in those analyses.4 Dr. Holderness' analysis of the alleged 5:41 actua-tion of high pressure injection was reviewed within EDS both by another EDS engineer and by the EDS Nuclear Quality Assur-ance Department.5 The objectives of the EDS analysis were to determine whether certain indications of operation of the emergency core cooling system, which were recorded on the day of the acci-2 Holderness, trial tr. 5590-91.
3 Id. at 5591-92.
4 Id. at 5590-91.
5 Id. at 5592.
2
dent, could be analyzed to identify an actuation of high pres-sure injection and, if so, to determine whether an actuation occurred at or about 5:41 a.m.6 There are two potential emergency cooling water sup-plies to the high pressure injection pumps: the make-up tank and the borated water storage tank.7 EDS constructed analyti-cal computer models which established that the response of the make-up tank level would indicate whether there was an actua-tion of high pressure injection.8 EDS confirmed the accuracy of its models, and of the conclusions derived from those mod-els, by comparing those conclusions with data on make-up tank level acquired during undisputed actuations of high pressure injection.9 The EDS analysis found that make-up tank level could be used as an indicator of full flow high pressure injec-tion,10 and further found that "the 5:41 response of the make-up tank level does not exhibit the characteristics of (an ac-tuation of high pressure injection]."ll The EDS analysis 6 " Analysis of Reactor Coolant System Make-Up During the Three Mile Island Unit 2 Event," EDS Nuclear Inc., Decem-ber 29, 1982, p. 1. The analysis was marked at trial as GPU trial exhibit no. 2233.
7 Holderness, trial tr. 5594.
8 Id. at 5594; 5600.
9 Id. at 5600-01; 5608-09.
i 10 GPU trial exhibit no. 2223, p. 2.
11 Id. at p. 3.
3
9 j
flatly concluded that the make-up tank level behavior at 5:41 1
! a.m. established the absence of an actuation of high pressure injection.12 Dr. Holderness, in testifying at trial, demon-strated that given the behavior of make-up tank level at or about 5:41, it was impossible for there to have been an HPI actuation at that time.13 a
OTHER INDEPENDENT STUDIES l
The conclusion of the EDS study that there had not been a 5:41 actuation is consistent with the findings of other independent studies regarding the March 28, 1979 accident.14 Among the technical analyses of the Three Mile Is-land accident containing detailed sequences of events are the NRC Special Inquiry Group (SIG) Report 15; NUREG-060016; and 12 Id. at p. 3.
13 Holderness, trial tr. 5637; 5700.
14 See discussion in the NRC staff's " Report of the Review of the Babcock and Wilcox - General Public Utilities Law-6-9.
suit Trial Court Record," March 28, 1983, at pp.
15 "Three Mile Island - A Report to the Commissioners and
'. the Public," Nuclear Regulatory Commission, Special In-quiry Group (NRC-SIG), Volume II, Part 2, "The Accident and Its Analysis" ("SIG Report").
16 " Investigation into the March 28, 1979 Three Mile Island
.! Accident by Office of Inspection and Enforcement," Inves-l tigative Report No. 50-320/79-10, NUREG-0600, July, 1979 l
("NUREG-0600").
4 l
s j
- - - - . - . - - - - .,___ _ _ . . . _ - . . . . _ , . _ . . , . , . . _ _ . - . - . _ ~ . _ . - _ _ , . . _ _ _ _ _ - _ . - - - ~ - - .- - _
. NSAC-80-1.17 None of the sequences of events in these studies include a 5:41 HPI actuation, and none of these studies con-cluded that there was such an event.
A GPU sequence of events, TDR-044,18 refers to a i
5:41 full flow manual HPI actuation. That entry, however, was based on statements by operators, which are reviewed below.
Significantly, the TDR limits the possibility of a 5:41 actua-i tion to a maximum of five minutes, a conclusion consistent with the findings of GPU-sponsored studies of borated water i
storage tank levels that a 5:41 actuation could not have last-ed for more than five minutes.19 As we will show, this maxi-mum five-minute figure in itself casts doubt on the operators' ability to recall the timing of the full flow HPI manual actu-
! ation.
I Moreover, Dr. Holderness of EDS Nuclear discussed the EDS study with the principal author of TDR-044, Dr. Van Witbeck of Energy, Inc. After reviewing the EDS report, Dr.
Van Witbeck concurred that no studies had been done in prepa-1 17 " Analysis of Three Mile Island - Unit 2 Accident," Nucle-ar Safety Analysis Center, NSAC-80-1 (NSAC-1 Revised),
March, 1980 ("NSAC-80 1").
18 GPU trial exhibit no. 2079, GPU Nuclear Technical Data l
Report, TDR-044, " Annotated Sequence of Events, March 28,
~
1979," February 6, 1981 ("TDR-044").
i 19 GPU trial exhibit 2079, TDR-044 at figure 60; Zewe dep.
821-22, 826-28, 830-37.
k 5
.1 1
ration of the TDR which contradicted the EDS conclusion as to the absence of any 5:41 actuation.20 OPERATOR STATEMENTS IN INTERVIEWS REGARDING A 5:41 ACTUATION In early interviews of the operators, their recol-lection of the approximately 15 hour1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> accident sequence gener-ally was not assisted by computer data or engineering analyses of the accident.21 Zewe testified at trial that soon after the accident he spoke to and was interviewed by "a great many people"; that he had had no opportunity to review data to con-firm the accuracy of his recollections; and that some of these early interviews were conducted in motel rooms, cars and trailers.22 Moreover, as Zewe noted during the trial, the op-erators' post-accident recollection often tended to " compress" the timing of various actions taken on the day of the acci-dent.23 Zewe explained in an early interview:
. . . I was very far off in the times. Times were much longer and I felt
! that they were much shorter. . . . (O)n a few of the graphs and things that we have seen, we have noticed that the times there were a lot different than we have previously imag-l ined."24 .
20 Holderness trial tr. 5659-60.
21 Zewe trial tr. 3031.
22
_I_d.
23 Id. at 3032.
24 TMI Staff interview, 4/6/79, p. 1.
6 i
evidenced by the fact that he related attempts to restart the reactor coolant pumps to the concerns about the increasing in-dications on the neutron detectors even though these were ac-tually about an hour apart.26 In order to delineate and understand the sequence of events in a nuclear plant transient, large amounts of data are recorded and then subjected to engineering analysis. As with the " black box" used in airplane accidents, it is more accu-rate to rely on engineering analysis of recorded data than on human recollection of numerous, technically complex events.
No one person could be expected,to recall precisely the time and sequence of the thousands of indications and actuations which occurred over a period of some fifteen hours on March 28, 1979.
Unfortunately, alarm printer data was not available for a period of time on March 28, 1979 that included 5:41 a.m.27 The alarm printer data, where available, recorded each actuation and termination of high pressure injection. The alarm printer records one full flow manual actuation of HPI at 26 Faust, I&E interview, 4/21/79, pp. 51-52. The computer alarm printouts place the attempts to restart the reactor coolant pumps at 6:46 to 6:54, and the increasing indica-tions on the neutron detectors at 5:41 to 6:05. GPU tri-
! al exhibit no. 2084.
27 GPU trial exhibit no. 2079, TDR-044, p. 42. (Alarm printer data not available from 5:13 to 6:48 a.m.)
i 7
7:20. This followed the shutting off of a reactor coolant pump at 7:13.28 Faust Craig Faust, an operator on shift on the day of the accident, stated in an NRC interview that manual HPI actuation occurred prior to the time of the shutting off of the reactor coolant pumps, at 5:41.29 However, Faust later appeared to realize that his recollection of the manual actuation had been displaced in time, and that he had confused the 7:20 full flow manual actuation with the 5:41 time period.30 In response to what an I&E interviewer characterized as a " monday morning quarterbacking" question about what he would have done differ-ently, Fauet stated that he had felt uneasy about turning off the reactor coolant pumps, and that, had he known at that time what he had learned after the accident, he would have tried high pressure injection rather than turning off the pumps.31 This conclusion is inconsistent with Faust's statement that full flow HPI had been initiated at the time of the 5:41 reac-28 GPU trial exhibit no'. 2084, alarm printer data.
29 Faust, NRC I&E interview 4/21/79, pp. 48, 51.
30 Specifically, during an interview on May 25, 1979, Faust, after a lengthy discussion of what was unquestionably the 7:20 manual actuation of HPI, said "[tlhis would be the manual actuation which would be right around when we were stopping the pumps. The one I could think of. So that l would be earlier than what it should be." NRC IEE inter-I view, 5/29/79, p. 10 (emphasis added).
31 NRC I&E interview 4/3/79, pp. 39-40, 48.
l 8
i
tuation of HPI when the remaining reactor coolant pumps were secured.30 As of the May 25th interview, Zewe had attended several meetings at which Faust had mentioned a 5:41 actua-tion.31 Zewe's understanding of the time of the actuation ap-parently derived from the earlier statements of Craig Faust.
For example, during the May 25th interview, in response to a question as to whether he was sure full HPI had been on around 5:41, Zewe s:ated that "I was not as sure as the operator who actuated it was. He is sure, Craig Faust."32 Notably, Zewe's understanding that Craig Faust had actuated HPI was contradicted by Faust himself, who stated that he thought that high pressure injection had been initiat-ed by Edward Frederick at the time that he, Faust, recalled having secured the reactor coolant pumps.33 Frederick Edward Frederick was the operator assigned to the HPI controls throughout the day of the accident.34 He has never testified to a 5:41 actuation, either during the GPU v.
B&W trial, during his deposition or in interviews. In an ear-30 Zewe, TMI Staff interview 5/25/79, p. 31.
31 Zewe trial tr. 2760-62.
32 TMI Staff interview, 5/25/79, pp. 5-6; see Zewe dep. 824-26.
33 Faust, NRC I&E interview, 4/21/79, p. 39; Faust, Presi-dent's Commission deposition, p. 158.
34 Frecerick trial tr. 3492-96; Zewe trial tr. 2124.
9
ly interview, Frederick characterized the manual HPI actuation as having occurred during a time when Gary Miller, Station Su-perintendent, was present in the control room.35 Miller ar-rived in the control room at approximately 7:05 a.m.
Frederick also placed the HPI actuation as occurring "after the relief valve had been isolated"36 which was at 6:19 a.m.,37 and as occurring "during the time when we had decided that we did not have natural circulation,"38 which was at about 6:54 a.m. when reactor coolant pump 1B was restarted in an attempt to induce forced flow circulation, marking the point at which the operators ultimately were convinced that natural circulation was not going to work.39 These statements establish Frederick's recollection that a manual actuation of full flow HPI occurred, not at 5:41 a.m., but rather after 7:00 a.m. -- conforming to the alarm printer entry at 7:20.
35 Frederick, NRC I&E interview, 4/23/79, pp. 48-57.
36 Frederick, U.S. Senate Subcommittee interview, 8/22/79, pp. 16-17.
37 GPU trial exhibit no. 2079, p. 47.
38 Frederick, U.S. Senate Subcommittee interview, 8/22/79, pp. 16-17.
39 Frederick, NRC I&E interview, 4/3/79, p. 36; Faust, NRC I&E interview, 4/21/79, p. 52; GPU exhibit no. 2079, TDR-1 044, p. 51.
10
"GPU v. B&W" DEPOSITION AND TRIAL TESTIMONY Faust Faust's deposition testimony further confirms that he did not have a sound basis for his earlier statement re-garding a 5:41 full flow HPI actuation. He testified that "before" they took the pumps off, high pressure injection was initiated; that he did not physically do it, but he heard it was done or was going to be done; that he did not know if it was at full flow; and that he was primarily involved with the secondary side of the plant.40 Zewe During his GPU v. B&W deposition, after he had had access to relevant technical data, Zewe testified that he had recalled that "we did high pressure injection at or about the time we secured the second two pumps. But I cannot void my-self of everything else that has happened and what is fact from other sources," referring to studies of borated water storage tank level responses to actuations of HPI.41 Thus, Zewe was unable to distinguish in his mind betw4en what he had previously said based on what he had heard from Faust, and facts that he knew to be scientifically accurate.
2 ewe's trial testimony further 'ndicates that his recollection of a 5:41 actuation derived from Craig Faust's 40 Faust dep., pp. 525, 540.
41 Zewe dep., 821-24.
11
statements. Thus, Zewe testified at trial that Faust had said, referring to a 5:41 actuation, that he, Faust, " felt sure that's when it was" and that Zewe had then said: "if you are sure that's when it was, then that's when it was. . . ."42 Zewe also testified regarding his own early recollection of the time of the manual HPI actuation: "I for one could not remember exactly when it happened. One of the operators, as I recall, was pretty sure of the exact time."43 During the GPU v. B&W trial, GPU's counsel asked Zewe a series of questions which he had not been asked in any of his prior testimony or interviews by the NRC or GPU person-nel, i.e.: How many HPI actuations had there been? How many of these were automatic? How many of these were manual? Zewe testified that he recalled four full flow actuations, three of which were automatic and one of which was manual.44 Specifi-cally, Zewe recalled a single manual actuation; the initial automatic actuation a few minutes into the accident; an auto-matic actuation "after the declaration of the site and general emergency"; and an automatic actuation in the early afternoon associated with the hydrogen burn.45 Zewe recalled that the manual actuation was the second actuation of the four.46 l
42 Zewe trial tr. 2761.
43 Zewe trial tr. 2173, 2761.
l 44 Zewe trial tr. 2115-18, 2153, 2156.
45 Zewe trial tr. 2115-18; 2153, 2156.
46 Zewe trial tr. 2117, 2121-22. .
12
automatic actuation a few minutes into the accident; an auto-matic actuation "after the declaration of the site and general emergency"; and an automatic actuation in the early afternoon associated with the hydrogen burn.47 Zewe recalled that the manual actuation was the second actuation of the four.48 This recollection is corroborated by recorded plant -
data. Computer alarm data establish three automatic actua-tions of full flow HPI: at two minutes into the event; at 7:56 a.m., or 30 minutes after the general emergency declara-tion; and at 1:50 p.m., the same time as the hydrogen burn.49 The computer alarm data lists only one manual actuation of full flow HPI, at 7:20 a.m. Thus, the manual actuation was the second HPI actuation, just as Zewe recalled.
Zewe's trial testimony also brought out for the first time that a full flow manual HPI actuation would have started the emergency diesel generators, setting off large alarm bells in the control room, and necessitating the dis-patch of an operator to shut down the diesels. Zewe testified that he did not recall doing this in or about the time period following the shutoff of the reactor coolant pumps.50 47 Zewe trial tr. 2115-18; 2153, 2156.
48 Zewe trial tr. 2117, 2121-22.
49 GPU trial exhibit no. 2084, alarm printer data.
50 Zewe, trial tr. 2120-21; see also Frederick trial tr.
3391.
13 l
\
'\,
x -
N.' - ,_
Zewe also testified that the manually initiated . full u.
flow HPI that he recalled had been maintained "for a consider- '\
x able period of time,"51 which he stated meant from ten minutes '
to half an hour.52 This accords more closely with the record-ed 7:20 a.m. actuation,[for seventeen minutes, than with the five-minute possibility at 5:41.3.m. in TDR-044.53 Zewe's ultimate = conclusion.at trial was that the closest that he could pinpoint his recollection of the single manual high pressure injection actuation at full flow was that
~
it occurred after the reactor coolant pumps were turned off (at 5: 41 a.m. ) but before the second automatic actuation (a t 7:56 a.m.).54 The operators' earlier confusion may have resulted in part from the fact abat some time after the reactor coolant pumps were shut of,f, the. operators began to inject borated wa-ter into the' reactor coolant _ system in order to regulate the boron concentration. ~This action.was necessary to counteract symptoms that the reactor was Seturning to criticality.55 Furthermore, the 7:20 manual actuation was -- according to the J 1
recorded data -- in fact jux?.aposed to the turning off of a N
- -6
~-
51
^
Zewe trial tr. 2115. , , _
52 Zewe trial tr. 2173-77.. -
. s 53 GPU trial exhibit no. 2084, abarn printer data; GPU trial exhibit 2079, TDR-044, figurt 60._
54 Zewe trial tr. 2117,'2121-22.
~~
55 Zewe trial tr. 2110-13;- Frederick trial tr. 3477-79.
s .
~
14
=
W
At trial, B&W's counsel examined Frederick on the issue of a 5:41 actuation pointing out that Frederick had been t present in post-accident interviews when Faust and Zewe re-5 ferred to a 5:41 actuation.57 Frederick consistently denied ever having agreed that there was a 5:41 actuation,58 and B&W 1
produced no statements of Frederick to the contrary. Freder-ick tistified:
I just never disagreed with (Zewel that's all. Until we put all the data together,
~"~ there was nothing to disagree about. . . .
1 I think that they think I agreed because I didn't disagree."59 Frederick also testified to data concerning the be-
.~ _ .-
" - havior of make-up tank levels. On cross-examination, B&W sub-e mitted a chart, prepared by its engineers during the prior few N
dayy, reflecting the behavior of make-up tank levels at 7:20,
'which B&W's counsel claimed was similar to the pattern at 5:41
'c s s a.m.
In order to resolve the issue in a reliable and defini-tive way, G9U's trial counsel decided to call in EDS Nuclear.
3, As discussed above, Dr. James Holderness testified to the EDS i ljuclear study which established that it was not possible for HPI to have been actuated at full flow at or about 5:41 a.m.
in light of the analysis of make-up tank levels. In particu-lar, Holderness explained that while the 5:41 a.m. and 7:20 1
57 Frederick trial tr. 3876-77.
y 58 Frederick trial tr. 3877-79; 3883-84.
59 Id. at 3888.
(: .: 15 x s N
C'.
P i
.. --- _- .- , - . , , - - - , - , - - . . . - - . - - _ _ - , _ . . . . -- ~ _ _ . -
, V,' .
. i i t t 1, lY , a;m. 'make-up' dank level patterns might appear similar to the Y naked eye, compute'r analysis plainly showed critical differ-e7ces and disproved any 5:41 a.m. actuation at full' flow.60 i
CONCLUSION' a
The alarm printer data show in undisputed manual ac-tuation of high pressure injection at 7:20.61 Thus, the alle-gations of a 5:41 manual a:tuation must hypothesize an a'ddi-tional manual actuation.. Yet', uncontradicted trial testimony establishes that both 2 ewe and Fredarick had a clear recollec- , ,
tion of there having been only one manual actuation.62 Fred-erick recalls specific circumstances that place'the manual ac-tuation near to the 7:20 time recorded on the alarm print <ir; r
Zewe accurately places the one manual actuation;as beingithe 1 second of the total of four HPI act'ultions, as is'recorde'd on the alarm printer at 7:20. The recorded 7:20 actuation fol-J lowed a shut-off of a reactor coolant pump, also recorded in I
, plant data, at 7:13. Accordingly, the trial testimony is con-
- I 1,sistent both with the available alarm printer data, and with the conclusion of the EDS technical analysis that there was no
! 5:41 actuation.
60 Holderness triali tr. 5637, 5700; GPU trial exhibit no.
2223, p. 3. ,
61 GPU trial exhibit no. 2084, computer alarm data.
'l 62 Zewe trial tr. 2153; 2156. Frederick trial tr. 3493; 3876.
16 i
Earlier statements made by another operator, Craig Faust, and relied upon by his superior, William Zewe, mis-placed the time of the manual actuation back by an hour and forty minutes, to an earlier shutting off of the reactor cool-ant pumps, at 5:41 a.m. In the absence of data, this was an understandable confusion of recollection.
Since the EDS analysis scientifically proves that that there was no full flow manual actuation of high pressure injection at or about 5:41 a.m., the colorful charge that a
" mystery man" turned it off was conclusively rebutted.
17 l
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