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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:NRC TO U.S. CONGRESS
MONTHYEARML20246M2141989-05-0808 May 1989 Responds to Request to Review Jr Sutton to Fj Remick Expressing Concern Re Actuation of Warning Siren in York,Pa on 890317.Event Isolated Malfunction of One Siren ML20245D1501989-04-20020 April 1989 Advises of Decision Re Approval of Method of Disposal of Contaminated Water Other than Discharging Water in River NUREG-1355, Forwards NUREG-1355, Status of Recommendations of President Commission on Accident at TMI - 10-Yr Review. Over 90% of Items Identified for Followup Action Have Been Implemented by Nuclear Reactor Licensees.W/O Encl1989-03-24024 March 1989 Forwards NUREG-1355, Status of Recommendations of President Commission on Accident at TMI - 10-Yr Review. Over 90% of Items Identified for Followup Action Have Been Implemented by Nuclear Reactor Licensees.W/O Encl ML20196C4611988-11-28028 November 1988 Forwards Charter for Advisory Panel for Decontamination of TMI-2 ML20154P6071988-05-20020 May 1988 Responds to Constituent J Rhen 880301 Request Re Potential Health Problems Affecting General Population in South Central Pennsylvania as Result of 1979 Accident at TMI-2.No short-term Physical Health Effects Noted ML20238C1531987-12-15015 December 1987 Responds to Expressing Concern That Possible NRC Staff Reductions at Facility Could Adversely Impact Cleanup Operations.Reorganization of Staffing Scheduled for 880201. Reductions Will Not Impact Safety.Press Release Encl ML20235J5351987-09-28028 September 1987 Responds to Constituent Tf Gross Ltr Supporting Ucs 870210 10CFR2.206 Petition to Suspend OLs & CPs of Any Util Operating or Bldg Nuclear Power Reactors Designed by B&W,Per 870803 Request.Nrc Statements Re Plants Discussed ML20235J1171987-09-28028 September 1987 Responds to Requesting Info Re Ucs 870210 Petition Requesting Mods to B&W Facilities,Per E Gallizzi to Recipient Requesting Support of Petition. Gallizzi Statements Discussed.Petition Under Review ML20236L1811987-08-0404 August 1987 Responds to Addressed to Chairman Zech,Requesting That Commission Keep Recipient Fully Apprised of All Developments Re Both Petition Filed by Ucs & Ongoing Reassessment of B&W Reactors.Review of Petition Continuing ML20236F4261987-07-28028 July 1987 Responds to Recipient to Chairman Zech Requesting Info Re Operation of TMI-1 W/Present Emergency Feedwater Sys.Encl Statement Gives More Detailed Explanation of NRC Requirements & Reasons Why Waiver Granted ML20236D8231987-07-24024 July 1987 Responds to Urging Expeditious NRC Approval of Util Plan for Disposal of 2.1 Million Gallons of Slightly Radioactive Water,If Technically Feasible & Safe.Notice of Opportunity for Public Hearing on Request Will Be Issued ML20206J9681987-04-0808 April 1987 Responds to Requesting Findings & Views Re Recent Correspondence from F Skolnick of Susquehanna Valley Alliance on Radioactive Water Disposal at Facility.Nrc Involvement in Issue Summarized ML20206B6821987-04-0606 April 1987 Responds to Re Constituent Concerns About Public Exposure to Releases of Radioactive Materials from TMI-1. Radioactive Release Requirements Embodied in License Conditions.Description of Monitoring Encl ML20211N4761987-02-20020 February 1987 Responds to W O'Donnell Concerns Re Health Effects of Living in Vicinity of Plant.Independent Groups Concluded That Impact of TMI-2 Accident on Physical Health of Local Residents Negligible.Radiation Monitoring Continuing ML20212A5481987-01-23023 January 1987 Forwards One Time Rept to Congress on TMI Items, in Accordance W/Nrc 850919 Response to Gao Rept, NRC Should Rept on Progress.... Safety Issues Mgt Sys Created to Assist in Mgt of Safety Concerns ML20212A6511987-01-23023 January 1987 Forwards One Time Rept to Congress on TMI Items, in Accordance W/Nrc 850919 Response to Gao Rept, NRC Should Rept on Progress.... Safety Issues Mgt Sys Created to Assist in Mgt of Safety Concerns ML20212A7191987-01-23023 January 1987 Forwards One Time Rept to Congress on TMI Items, in Accordance W/Nrc 850919 Response to Gao Rept, NRC Should Rept on Progress.... Safety Issues Mgt Sys Created to Assist in Mgt of Safety Issues ML20212A8301987-01-23023 January 1987 Forwards One Time Rept to Congress on TMI Items, in Accordance W/Nrc 850919 Response to Gao Rept, NRC Should Rept on Progress.... Safety Issues Mgt Sys Created to Assist in Mgt of Safety Issues ML20213A3471987-01-23023 January 1987 Forwards One Time Rept to Congress on TMI Items, in Accordance W/Nrc 850919 Response to Gao Rept, NRC Should Rept on Progress.... Safety Issues Mgt Sys Created to Assist in Mgt of Safety Concerns ML20212H6071987-01-15015 January 1987 Responds to Constituent J Seertsen Ltr Re Continuing Health Effects of TMI-2 Accident.Nrc,Epa & Commonwealth of PA Studies Concluded That No Significant Impacts to Health & Safety of Residents Around Site Resulted from Accident ML20206F2531986-06-16016 June 1986 Advises That Encl NRC Sent to Judge Sh Rambo Re Hm Donley TMI Evacuation Claims in Response to 860528 Inquiry.Nrc Has No Authority to Act on Claims NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress1986-04-23023 April 1986 Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco1986-04-23023 April 1986 Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco ML20203F2141986-04-18018 April 1986 Responds to 860319 Request for Info on Constituent Gm Cochran Inquiry Re Federal Govt & Commonwealth of PA Involvement in Payment for Cleanup & Waste Storage.Doe Funds Expended for Data Collection for R&D Program ML20137T7361986-02-0606 February 1986 Submits Addl Info Re Concerns Raised by M Osborn,Per 860108 Request.Continued Operations Oversight Will Include Close Observation of day-to-day Activities & Scope Reviews of Plant & Licensee Performance ML20137P5121986-01-24024 January 1986 Provides Info Concerning Financial Qualifications of Utils Re Safety of Plants.Nrc Regulation of Commercial Nuclear Power Based on Responsibility of Licensees for Safe Operation.Addl Views of Asselstine Encl ML20137A8971985-12-17017 December 1985 Forwards Fr Notice of NRC Authorization to Issue & Make Immediately Effective,Any Amend to OL Upon Determination That Amend Involves Nshc,Per Public Law 97-415.W/o Encl ML20132G6251985-09-19019 September 1985 Forwards Responses to Gao Rept, NRC Should Rept on Progress in Implementing Lessons Learned from TMI Accident ML20132G2461985-09-16016 September 1985 Forwards Insert of Page 39,Line 827 of 850417 Hearing Record on NRC Budget.Insert Provides Addl Views on Estimate of Crude Cumulative Probability of Core Melt Accident ML20137L0451985-08-29029 August 1985 Forwards Revised Charter for Advisory Panel for Decontamination of TMI-2,broadening Scope of Committee Activities to Include Consulting W/Commission on Public Reactions to Plans ML20137L0211985-08-29029 August 1985 Forwards Revised Charter for Advisory Panel for Decontamination of TMI-2,broadening Scope of Committee Activities to Include Consulting W/Commission on Public Reactions to Plans & Results of Studies Re TMI-2 Accident ML20137L0021985-08-29029 August 1985 Forwards Revised Charter for Advisory Panel for Decontamination of TMI-2,broadening Scope of Committee Activities to Include Consulting W/Commission on Public Reactions to Plans & Results of Studies Re TMI-2 Accident ML20140H5741985-08-12012 August 1985 Forwards Press Release 85-106 Re Proposed Fine for Util Alleged Violation of NRC Requirements Concerning Employee Discrimination in Cleanup Program ML20132H1941985-07-18018 July 1985 Responds to Representative Jr Miller Requesting Explanation of Procedures NRC Used to Authorize Restart of TMI-1 & Description of Safety Risks That Communities Surrounding Plant Now Subj To.Served on 850719 ML20129G1881985-07-0808 July 1985 Responds to Forwarding Constituent L Evers 850607 Complaint Re Gpu Disposal of TMI-2 Waste.Nrc Only Assures That Cleanup Proceeds Safely & Expeditiously.Gpu Chooses & Evaluates Contractors ML20132F5981985-04-17017 April 1985 Ack Receipt of Ltr Re Status of NRC Deliberations on Whether to Lift Immediate Effectiveness of Orders Directing That TMI-1 Remain Shut Down Pending Further Order of Commission. No Date Set for Public Meeting ML20149H1901984-11-0202 November 1984 Forwards NRC & Ofc of Investigations (OI) Responses to Questions Raised in H Myers 840604 Memo to N Haller & OI 840913 Responses ML20132E9771984-10-18018 October 1984 Ack Receipt of Inquiry on Behalf of J Merryman Re Status of Restart Proceeding.Commission Will Undertake & Complete Review of ALAB-772.Forwards Commission 840911 Orders & Commissioner Asselstine Dissenting Views.W/O Encl ML20197H4751984-06-15015 June 1984 Responds to Re Commission Intentions to Pursue Tentative TMI-1 Restart Schedule Announced in Apr 1984. Decision by June 1984 No Longer Possible Due to Need for Addl Comments by Interested Parties.Served on 840618 ML20132C2031984-06-12012 June 1984 Responds to to Chairman Palladino Re Constituent Lw Bussert Concerns on Licensing Delays & Impact on Utils. Minimized Delays Key in NRC Decisionmaking Process ML20132E7431984-06-0404 June 1984 Ack Receipt of Ltr on Behalf of Constituent,Jc Morris, Inquiry as to Status of Commission Decision on Restart of TMI-1.On 840601,Commission Issued Encl Order Requesting Parties Comments on Subj Question by 840615.W/o Encl ML20149M4341984-05-31031 May 1984 Forwards NRC Responses to 840216 Questions Re TMI-2 Cleanup Allegations ML20140H6581984-02-29029 February 1984 Forwards Press Release 84-26 Re NRC Proposed Fine Against Util for 12 Alleged Violations of Tech Specs While Performing Work at Facility ML20207D1551983-11-0404 November 1983 Clarifies Position on Staff & Commission Knowledge Re Hartman Allegation Investigation ML20207D0761983-10-25025 October 1983 Forwards EDO 831020 Memo Providing Addl Info to NRC 831017 Response to Inquiries Re Hartman Leak Rate Allegations ML20207D0901983-10-25025 October 1983 Forwards EDO 831020 Memo Providing Addl Info to NRC 831017 Response to Inquiries Re Hartman Leak Rate Allegations ML20207E6031983-10-17017 October 1983 Forwards Responses to Re Allegations That Leak Rate Calculations Falsified at Unit 2 Prior to 1979 Accident,Responses to Question 1 of & Info on Unit 1 Restart Record ML20062G3531982-08-0404 August 1982 Responds to Reiterating Concerns of Kent County, MD Residents Re Possible Disposal of Waste Water from TMI Into Susquehanna River & Chesapeake Bay.Two Studies Underway to Evaluate Impacts of 27 Disposition Alternatives ML20055A8901982-07-0808 July 1982 Responds to 820621 Request for Info Re Shipments of Radwaste from Facility Through State of Wi.Shipments Resulting from Cleanup Efforts Estimated to Range from 350-1,000 Ci ML20209B2871982-02-26026 February 1982 Forwards NRC 16th Monthly Status Rept for 820115-0215, Discussing Actions Taken on Operating Reactors & Licensing Reviews of New Facilities,Per House Rept 96-1093.Licensing Schedules for Perding OL & Cp/Ml Applications Encl 1989-05-08
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 ML20212J0011999-09-27027 September 1999 Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted 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 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 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 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) 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 ML20209F2571999-07-0909 July 1999 Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1 ML20209G5861999-07-0909 July 1999 Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted 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 ML20196J5631999-07-0101 July 1999 Informs That Util 981203 Joint Application with Amergen Energy Co Marked Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196J5741999-06-30030 June 1999 Informs That as Result of Staff Review of Util Response to GL 92-01,rev 1,suppl 1,info Provided in Support of PT Limits License Amend & B&W Topical Rept,Staff Revised Info for Plant,Unit 1,in Reactor Vessel Integrity Database ML20196H6811999-06-29029 June 1999 Forwards Insp Rept 50-289/99-03 on 990425-0605.No Violations Noted.However,Adequacy of Assessment of Reactor Bldg Emergency Cooler Operability Prior to Conducting Maintenance on One Reactor Bldg Spray Sys,Questionable ML20212H8711999-06-21021 June 1999 Discusses Updated Schedule Commitment Submitted by Gpu on 990602 for Implementing Thermo-Lag 330-1 Fire Barrier C/As & Completion of Thermo-Lag Effort at TMI-1.Informs NRC Will Incorporate Commitment Into Co Modifying License ML20195K2821999-06-17017 June 1999 Forwards Request for Addl Info Re Kinetic Expansion Region Inspection Acceptance Criteria ML20212H6621999-06-0404 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Three Mile Island Nuclear Station ML20207E7201999-05-27027 May 1999 Discusses Reorganization of Nrr,Effective 990328. Organization Chart Encl ML20207B6541999-05-27027 May 1999 Forwards SER Accepting Util Program to Periodically Verify design-basis Capability of safety-related MOV at TMI-1 & That Util Adequately Addressed Actions Requested in GL 96-05 ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206S3411999-05-14014 May 1999 Forwards Insp Rept 50-289/99-02 on 990314-0424.Violations Occurred & Being Treated as non-cited Violations.Security Program Was Inspected During Period & Found to Be Effective ML20206N5831999-05-13013 May 1999 Requests Description of Proposed Corrective Actions for Fire Zones AB-FZ-3,AB-FZ-5,AB-FZ-7,FH-FZ-2,CB-FA-1 & FH-FZ-6. Confirmation That Corrective Actions & Commitments Made Will Be Completed by 991231,requested IR 05000298/19980091999-05-12012 May 1999 Refers to Insp Rept 50-298/98-09 Conducted Between 981227-990130.During Insp,Apparent Violation of 10CFR50.50 Identified & Being Treated as non-cited ML20206H3571999-05-0606 May 1999 Forwards RAI Re 981203 Application & Suppls & 0416,requesting Review & Approval of Revised Core Protection SL & Bases for TMI-1 to Reflect Average of 20% of Tubes Plugged Per Sg.Response Requested within 10 Days of Receipt ML20207A5401999-04-29029 April 1999 Informs That Licensee 980930 Response to GL 96-06,appears to Be Reasonable & Appropriate for Specific Design & Configuration of RB Emergency Cooling at Plant,Unit 1 & That Staff Satisfied with Licensee Resolution of Waterhammer ML20206D4001999-04-20020 April 1999 Informs of Completion of Review of Gpu Request for Exemption Submitted on 961231,970908,971230,980521,981014,981125 & 981223 from Requirements of 10CFR50,App R,Section III.G.2 for TMI Unit 1.Forwards Exemption & Safety Evaluation ML20205S6791999-04-16016 April 1999 Forwards Insp Rept 50-289/99-01 on 990131-0313.No Violations Noted.Identification by Licensee Staff of Elevated Tritium Activity in Monitoring Well Led to Investigation & Identification of Leak from Buried Radwaste Path ML20205P3391999-04-0909 April 1999 Discusses Results of Plant Performance Review for Three Mile Island Completed on 990225.Historical Listing of Plant Issues That Were Considered During PPR Encl IR 05000289/19980061999-03-26026 March 1999 Ack Receipt of 981112 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-289/98-06 .Action Does Not Change NRC Determination That Change to Hpis Valve Configuration Involved URI ML20204E3911999-03-17017 March 1999 Informs That Region I Plans to Conduct Open Predecisional Enforcement Conference to Discuss Apparent Violations Re Efs Issues as Described in Insp Rept 50-289/98-09,per ML20204B6771999-03-15015 March 1999 Submits Withdrawal of Amend Request for Operating License DPR-46.Proposed Change Would Have Modified Facility TSs Pertaining to Neutron Monitoring Neutron Detectors ML20207H7391999-03-0505 March 1999 Forwards Insp Rept 50-289/98-09 on 981227-990130.Two Apparent Violations Being Considered for Enforcement Action.First Violation Deals with Failure to Follow Procedures for Control of Emergency Boration Source ML20203F4911999-02-0505 February 1999 Forwards Request for Addl Info Re Licensee 981125 Amend Application Re TS Change Request 277 for OTSG Inservice Insp During 13R for Three Mile Island,Unit 1 ML20202H6771999-02-0303 February 1999 Documents Basis for NRC Staff Generic Approval of Requests to Relocate TS Requirements from Tss.Staff Generic SER Finding Relative to Relocated TS Requirements Encl ML20196K3511999-01-22022 January 1999 Refers to Gpu Responses to Second NRC RAI Re GL 92-08 & Review of Gpu Analytical Approach for Ampacity Derating Determinations.Forwards SE & SNL Technical Ltr Rept Concluding That No Outstanding Safety Concerns Identified ML20199H6471999-01-20020 January 1999 Forwards RAI Re Gpu TS Change Request 277 OTSG Cycle 13 for Plant Unit 1.NRC Has Determined That Addl Info Needed to Complete Review ML20199G7401999-01-12012 January 1999 Forwards Insp Rept 50-289/98-08 on 981101-1226.No Violations Noted.Operator Workaround Program Found to Be Acceptable ML20206S0221999-01-0808 January 1999 Responds to Re Changes to Physical Security Plan Identified as Rev 38,submitted Under Provisions of 10CFR50.54(p).Based on NRC Determination,Changes Do Not Decrease Overall Effectiveness of Security Plan 1999-09-30
[Table view] |
Text
- _ _ _ _
e . /ada a pu-tiay 31, 1984 l
I l
l f4EHORANDUM FOR: Henry Myers Subcomittee on Energy and the Environment Coct:ittee on Interior and Insular Affairs United States House of Representatives FROM: Carlton Kamerer, Director Office of Congressional Affairs
SUBJECT:
STAFF RESPONSES TO QUESTIONS ON THI-2 CLEANUP ALLEGATIONS
/
Attached are the NRC staff responses to your February 16, 1984 questions conceriting the THI-2 cleanup allegations.
Attachnent:
1 As stated cc: E00
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ENCLOSURE 5
. RESPONSE TO HENRY MYERS' QUESTIONS Oil TMI-2 POLAR CRANE ALLEGATIONS D
r:.
t 3 QUESTION 1. I am enclosing a chronology of crane statements, contentions and allegations. Does NRC staff dispute elements in this chronology?
If so, which ones?
NRC RESPONSE .
The staff has clarifications for some of the elements in your chronology. In the list which follows, we have provided a response to each of your ch-onological ;
events. Where the staff cannot confim nor deny statements or conversations '
or disput's what you have stated, we have responded with "no comment." The staff has also added some important events to the list that should be a part o'/
a complete chronology of the activities related to the polar crane during this pe riod. ,
As is discussed in some of our responses, the polar crane functional description, safaty evaluation, cr'ane operating procedure and load test procedure are different docinents, each with a different purpose. Therefore, it is possible to approve one of these documents and disapprove another without being in conflict. These docunents constitute the major elements of the staff's reviews related to the polar crane.
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CHRONOLOGY I
H. MYERS ITEMS NRC STAFF C(WWENTS DATES
- 0ctober 12, 1982 Functional Description submitted by GPU to the RC for review
( and approval.
IGtC TMI Project Office m rts NRC nonnally reported GPU January 17, 1983 that the crane load test is proposed schedules without scheduled for late February. stating if they wre opti-mistic or pessimistic. In the case of the polar anne.
GPU schedules were ve';
optimistic when consi v <-
ing the outstanding issues A, that they had to resolve '
prior to perfonning the load test.
8 50 reviews crane SER. No Comment.
January 20, 1983 -
Februa ry 10 1983 Polar crane was inspected by No Comment.
Janua ry 24, 1983 NRC consultant. The inspection did not "identify any hardware deficiencies Alch could delay the , crane recovery schedule."
Gischel (plant engineering director) No Conunent. ,
February 10, 1983 writes King TMI-2 Site Doerations Director, a memorandum stating that the safety evaluation of the crane was "technically unacceptable as presented."
- Denotes itons added to the chronology by the NRC staff.
1
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NRC STAFF CMENTS DATES H. MYERS ITEMS King and Gischel inform IMI-2 chief No Comment.
February 11, 1983 Kanga that they had problems with the polar crane safety evaluation and would not concur.
TMI-2 deputy chief Barton complains No Comment.
February 14, 1983 to King about Gischel's not agreeing with the crane safety evaluation.
King finds that the crane safety As may be seen on the GPU February 14, l_983 concurrence list for the evaluation had been sent to the polar crane load test NRC without his having reviewed it. This, according to King, was safety evaluation, a violation of the NRC regulations. Larry King apparently did concur on that document bafore submit-tal to NRC staff as his initials appear on h the document (See Attachment 1). .
King and Gischel send memoranda to King and Gischel sent a l February 14, 1983 memo to management on upper management expressing funda-mental disagreement with crane the polar crane SER on I
program.
February 17, 1983, not February 14, 1983.
Parks says that, "On Monday No Comment.
February 14, 1983 morning, February 14, 1983 Mr. King informed the 50 staff that he had received a phone call from Jonn Bartoo asking 'what the hell' Ed Gischel was doing writing l
' the polar crane memorandum.
Larry KLg reported Barton's threat -
- I don' t need peopie like that working for me. I'll fire their ass.'"
(Parks p.18-19.)
l '
. ~:
H. MYERS ITEMS NRC STAFF COWEENTS .
DATES 1MI-2 engineer Parks infones No Casument.
February 17, 1983 Radb111 (leader of the Polar l
Co.se Task Force) that the polar crane test procedure did not comply with administrative
- Februa ry 17, 1983 Revision 2 to the functional Description was submitted
. by GPU to the NRC.
February 18, 1983 Kitler (TMI-2 management official) No Comument.
l threatens to have Parks renoved l
from the site.
1 Februa ry 18, 1983 NRC TMI Project Office reports. that No Comument.
the polar crane load testing is ,
7 "scheduled to be accomplished during the next two weeks."
GPU sutzeits polar crane load test
- Februa ry 18, 1983 safety evaluation to NRC for .
review and approval.
4 Meeting at dich King and Parks No Comument.
February 22, 1983_
explain that crane refurbishment did not comply with administra-tive procedures 1043 and 1047.
Kanga orders King to appoint a test director for the polar crane test. King refuses.
4 Februa ry 23, 1983 Agreement is reached that Q/A would As indicated in the review procedures for polar crane February 23, 1983 internal modification and testing. GPU memorandum from
- 8. Ballard to 8. Kanga, (Attachment 2) QA clearly indicates that they were previously involved in the over-sight of the polar crane i
.3 2
NRC STAFF C90ENTS DATES H. MYERS ITEMS i refurbishment program. , ,
Although 04 identifies l administrative deficiencies. .!
they do state that they
".. .found no significant l programmatic probits i
(
with the Safety Evaluation l or the polar Crane refurbishment process....".
At 5:00 p.m. 8arton (TMI-2 No Cameent.
February 23, 1983 I Deputy Chief) asks King if he is president of Quiltek. King said yes and Barton "lif ted King's badge." (King was suspended, prohlht ted from the site and fired on p.
March 23.
We would like to clarify Februa ry 25, 1983_ MC-TMI Office Chief Lake Barrett what transpired in the ,
infonas Parks that NRC had meeting between Mr. Parks inspected the crane and could find no problems. and the MC staff on February 25, 1983. The
' M C staff (L. Barrett and J. Wiebe) told Mr. Parks that MC found no probless that were not already being considered. For completeness, the staff summarizes below the relevant discussion given in Attachment 3, 3/24.meno L. Barrett to 8. Snyder, which locludes an account-ing of what took place at the February 25, 1983 meeting with Mr. Parks.
l l ..
NRC STAFF COMMENTS DATES H. MYERS ITEMS As was erranged the previous day, J. Wiebe and Mr. Barrett met with Mr. Parks in the TMIPO offices for over an hour. Mr. Barrett told Mr. Parks the NRC found no evidence of threats but we could not, on the other hand, prove that they did not occur. The NRC had conducted an inspection and had found no irreg-ularities in the calcu-lations at Gaithersburg.
1 Mr. Parks did not identify any safety issues that were not already being considered.
Mr. Barrett and Mr. Wiebe also told Mr. Parks that the NRC was ,
concerned with the poor relation- y ships between departments and
- with the degradation in quality of procedures. Mr. Barrett asked if Mr. Parks had any specific safety issues concerning the crane or anything else at TMI that Mr. Parks thought was un-safe. Mr. Parks said no, but that he just had general concerns about administrative procedures and harassment.
Mr. Parks was told that if he made a fonnai allegation, an outside investigator would come in if he wanted.
Mr. Parks declined and said he would rather wait to see what GPU QA would do.
Mr. Barrett and Mr. Wiebe also generally discussed
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.s NRC STAFF CWW4ENTS-DATES H. MYERS ITDtS the King suspension of the previous night.
Mr. Parks was told that the NRC would continue to look at the Polar Crane ciescly in the review process. -
90tC TMI Project Office reports No Comument.
February 28, 1983 that preparations for polar crane full load test were continuing.
Parks receives response to his No Comument.
Februa or 28, 1983 polar crane comuments. The response stated that certain Q/A require-ments did not apply to the polar crane test procedure.
Parks and Chwestyk (King's replace- No Comument. ,
Nrch I ,1983 ?
ment) write ausnorandum to manage-ment stating opinion of Q/A '
managers that Q/A requirements did apply to the polar crane test procedure.
No Ceaunent.
Nrch 4,1983 TMI Q/A staff state that certain modifications to the crane had not been made in accordance with Q/A requirements.
March 7,1983 NRC TMI Project Office reports that This statement was made in the TMIPO's Weekly the polar crane evaluation was Status Report and was complete and that a polar crane load test was scheduled for the referencing NRC's review latter part of March. of GPUNC's Polar Crane Functional Description.
The staff was already aware of possible admin-1strative deficiencies as is documented in the NRC's February 1983
N. MYERS ITEMS _ NRC STAFF CGOENTS DATES Monthly Inspection Report covering the period 1/30 - 2/26/83 (see Attachment 4). The staff had not completed its technical review of the load test program as of this date because implementing procedures had not been received and the staff had not completed its safety review of the load test SER.
-s March 7, 1983 NRC TMI-2 Program Director states: The TMI-2 Program Director made the referenced state-
"The NRC staf f concurs with ment in the NRC's approval f, the Functional Description as it of the Functional Description relates to the Reactor Buf1 ding for the refurbishment of TMI-2 Polar Crane Load Test using the Polar Crane dated March 17, 1983. t main hoist system. QA/QC has The functional description is a '
been involved at all stages of document that discusses the the refurbshment process in programmatic approach to the addition to NRC staff. Safety refurbishment. Specific .
considerations have been addressed polar crane load test safety i
under a separate letter." issues were addressed in the licensee's Safety Evaluation '
Report dated February 18, 1983, as amended. Because any state-r ments made in the staff's i appraisal of the functional Description relate to re-furbishment philosophy, it was not contradictory to approve the Functional ,
Description and disapprove the detailed procedures. 6 The statement that QA/QC was involved in the refurbishment process means that in our m ------
m - . . . - . . . . . - . _ . . . _ _ . _ - __ _ _ . _ _ _ _ _ _ _ _ _ _ ___ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _
NRC STAFF C(MMENTS DATES H. MYERS ITEMS judgement QA/QC was carrying out their audit l functions. (See March 10,1983 discussions below as evidence of this.)
l GPU submitted the Polar .
l
- March 8, 1983 Crane General Operating Procbdure for NRC approval.
March 10,1983 TMI-2 Q/A staff express concern to QA forwarded a memorandum to TMI-2 management about crane activi- J. Theising of Recovery Programs on March 10, 1983.
ties not carried out in accordance with Q/A requirements. This memo discussed Polar Crane QA/QC itens that had been previously reviewed. It stated 1*
that polar crane "tests l were technically adequate" even though it appeared that there were some administrative l deficiencies. It also indicated that QA had previously reviewed the functional Description.
NRC TMI Office Chief Lake Barrett It should be noted that March 10, 1983 this disapproval (see disapproves proposed procedures for test of polar crane. Attachment 5) was for the detailed implementing procedure for operating the polar crane. This disapproval was for detailed procedural steps and therefore was not l in conflict with the NRC's l approval of the prograsanatic functional Description.
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DATES H. MYERS ITEMS NRC STAFF CWWENTS March 14,1983 RC 1MI Project Office reports No Comument.
to NRC HQ that the polar crane load test was scheduled for the week of March 21.
March 21,1983 NRC TMI Project Office reports to No Comument.
HQ that the crane test was delayed
- from late March to early April.
Parl s makes public his affidavit on polar crane allegation.
April 7,1983 NRC TMI Project Office disapproves Disapproval of Polar Crane polar crane test procedures. Test Procedure (see Attach-ment 6) was based on
"... technical aspects of the procedure in areas other ,
than those pertaining to g the Parks /Gischel affidavits. .
These issues are being handled by the NRC's Office of Investigations." The technical reasons for dis-approval are detailed in 18 separate comuments.
Has NRC staff compiled a list of defects in the proposed crane QUESTION 2. l test program as the program existed on February 23, 19837 As it
- i existed on March 3, 19837 l NRC RESPONSE The basic polar crane test program as stated in Appendix A Table 4 of the B. Kanga to L. Barrett letter, "Polar Crane Refurbishment," dated .
October 8,1982, has remained the same and no changes have been made.
The basic test program (but not the details of the implemen. ting operating and test procedures) was approved by the NRC in a letter from 8. Snyder to B. Kanga on March 7,1983. The GPUN detailed procedures which were to impicment the details of the basic test program did require changes when they were. originally submitted to the NRC for approval. On both February 23 and March 3,1983, the TMIPO staff was awaiting various detailed GPU documents (e.g., polar crane operating procedure and load test procedure) concerning the polar crane and was reviewing other documents (e.g., test results, Polar Crane Safety Evaluation and Functional Description) regarding the polar crane that it had in its possession. The procedure review resulted in L. Barrett's March 10,1983 disapproval of the polar crane operating procedure ( Attachment 5) and L. Barrett's April 7,1983 disapproval of the polar crane load test procedure ( Attachment 6). The reasons for these disapprovals are listed in the above doctnents. lne issues discussed in these disapprovals were based on NRC's technical reviews and did not originate fran any allegations of Messrs. Parks, King and Gischel.
On February 18 ,1983, Mr. Parks contacted the TMIPO regarding concerns he had with the polar crane load test implementing procedure. This led to a TMIPO inquiry into the issue during late February. This inquiry resulted in the March 14, 1983 inspection report ( Attachment 4) which addressed inter-departmental communication problems (NRC item 320/83-03-01)and the use of administrative procedure AP-1043, "Work Authorization Procedure," and AP-1047, "Startup. and Test" (NRC item 320/83-03-02).
l These items were largely initiated because of Mr. Parks' concerns and were to be resolved prior to the polar crane load test. The NRC staff held an l exit interview with GPU management to infonn GPU of these concerns on March 1,1983 (i.e., between the February 23, 1983 and March 3,1983 dates).
l Ctronological details of this time period are included in the attached i
( Attachment 3) L. Barrett to B. Snyder memorandum dated March 24, 1983.
In summary, the defects are listed in the NRC procedure disapproval document (NRC technical issues) and the February inspection Report (Parks' adminis-trative procadure issues).
QUESTION 3. If the crane had been tested in accord with the GPU/Bechtel 1
plan that existed on February 23, 1983, would such tests have violated the NRC's regulations? That existed on March 7, 19837 l
NRC RESPONSE l If the crane had been tested on February 23, 1983, or March 7,1983, the test would have been a violation of the THI-2 Technical Speci#ications (and there-fore a violation of NRC regulations). The TMI-2 Technical Specifications
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require NRC revipw and approval of the GPU procedures required to perfom such activities. However, on February 23 and March 7,1983, it was not possib.e for GPU to conduct the polar crane load test because they had not completed, and the NRC staff had not approved, the detailed implementing procedures for the test. Additionally, the staff had not completed its safety review of the planned load test. Only the basic polar crane functional description (October 12, 1982 Kanga letter) had been approved by the NRC by March 7,1983 (March 7,1983 Snyder letter).
QUESTION 4._ In what respects does the current crane test program differ from that which existed on February 23, 1983? That which existed on March 7,19837 NRC RESPONSE There has been no change to the basic polar crane test program logic nor the load test sequence; however, there have been sone changes to the detailed implementing p ocedures. These changes fall into two categories; technical and administrative. The technical changes were a result of NRC staff and consultant reviews and were not as the result of Parks, King and Gischel all egations. The following is a list of technical changes that were required by the NRC relative to the load test and operating procedures, to improve the safety margin:
' , ,.. .' - e Technical Changes to the Polar Crane t.oad Test and Operating Procedures
- 1. Rigging was upgraded per NRC consnents dated March 10,1983 and April 7,1983.
- 2. Vertical lift height limits were added per NRC comment dated April 7,1983.
- 3. Hook rotation precautions were added per NRC comment dated April 7,1983.
- 4. Electrical current monitoring requirements were added per NRC comment dated April 7,1983.
- 5. A sudden stop test was added per NRC comment datred April 7,1983.
- 6. Mditional miscellaneous changes were made to more clearly define various steps in the procedure.
The administrative changes were to correct the administrative deficiencies that Mr. Parks brought forward (e.g., compliance with Administrative Procedures l 1043 and 1047). These were noted by NRC in the March 1 inspection exit interview l
l with GPU as doctmented in the February Inspection Report, dated March 14, 1983 1
( Attachment 4). For the polar crane program these deficiencies were subsequently corrected by GPU.
15-QUESTION 5._ Is ,it the position of NRC staff that revisions in the plan for testing the crane would have been required even if Parks, King and Gischel had not expressed disagreement with the directives, orders, plans, etc. put forth by their Bechtel-and GPU supervisors?
Is it the position of NRC staff that revisions in the plan for testing the crane would have been required even if Parks, King and Gischel had not gone public with their concerns?
MRC RESPONSE As previously noted, no changes were required to the basic crane load '.est program.. 'Certain revisions in the implementing procedures for testing the crane (see response to Question 4) wculd have been required even if Parks, King and Gischel had not expressed disagreement with Bechtel/GPU supervisors nor gone public with their concerns. The NRC staff was conducting its safety and technical review of the polar crane (refurbishment anu testing) when the allegations were raised. Based en the staff's review, changes were made to the implementing procedures (a.g. , load pathways, upgraded rigging, testing and monitoring requirements) to improve the margin of safety. These require-ments were not influenced by th3 allegations raised.
It should be noted, however, that the administr6tive issues identified by Parks, King and Gischel made their management aware of the deficiencies in the administrative procedures which were uployed to refurbish the polar crane.
As stated previously, these deficiencies were corrected by GPU and NRC was monitoring their corrective action via the February 1983 inspection report open items.
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QUESTION 6. On, March 14, the TMIPO office reported to HQ that the polar crane ;
loM test ws scheduled for the week of March 21. On March 21, the TMIPO office reported that the crane test was delayed from ;
1 March to early April. What elements of the plan caused the l change? When did TMIPO receive infonnation which caused it to disapprove the procedures for testing the crane?
NRC RESPONSE The TMIPO Weekly Status Report dates were based on schedule infonnation provided by GPU. The staff just reported GPU's schedule change in the Weekly Status Report. The schedule was delayed because: (1) GPU was having difficulty responding to TMIPO questions on the operating procedure (see Attachment 5); (2) GPU did not submit the load test procedure to the NRC for review and approval until March 31,1983; and (3) GPU was resolving internal consnents, e.g., issues rsised by Parks.
The polar crane operating procedure was received on March 8 and disapproved on March 10, 1983. The polar crane load test procedure was received on March 31, 1983 and disapproved on April 7,1983. The procedures were rejected because they were not acceptable for reasons stated in response f4 QUESTION 7. Does the NRC staff intend to specify which of the Parks, King and Gischel allegat;ons it has substantiated and which it has not substantiated?
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i NRC RESPONSE ,
The NRC Office of Investigations (01) report, dated September 1,1983, I addresses the allegations of Parks, Kir.g and Gischel relative to the polar c rane. The TMIPO presented their analysis of the Septaber 1,1983 report in a paper to the Cm elssion, dated January 25,1984.
QUESTION 8. What is the basis for the staff staternent that tilere ws no evidence of deliberate circumvention of administrative procedures to avoid technical requirenents? Does the staff intend to say there is no evidence of willful violations of NRC requirements
- or conspiracies to violate NRC requirst, ants?
NRC RESPONSE 8ased on the staff's review of the infonnation related to the polar crane refurbishment and testing, including the allegations raised by Pa rks ,
King and Gischel, it is the staff's judgement that the licensee had not deliberately or will, fully circumvsnted their technical requirements nor conspired to violate NRC requirements.
In the staff's opinion, the aaministrative deficiencies were more th?
3 result of confusion related to the turnover of the polar crane from GPO to Bechtel rather than any deliberate attempt to bypass GPU administrative requi renents.
,y __ _ _ _
3 f ATTACHMENT 2 Intor=@ffloo Momorandum
.[
Date February 23, 1983 k.h;j Nticlear SMt polar Crane Safety Evaluation 6110-83-039 Locanon TMI Trailar 175 7c. 3. K. Kanga
) Directat , Unit 2 1
l Quality Assurance has reviewed the saf ety Evals.cion for the Polar Crane Load Test and the concarns that have been raised par your request, i Rechtel l' The calculations to back up the safety Evaluation were reviewed.
Quality Assurance was requested and haa reviewed the The only calculations available at the site were Bsw an applicable to the loss of components due to load drop.
l j
some events were evaluated in a probabelistic manner and no, calculations were made. One axample is the drop of a missile shield directly on the hectcr Nead.
The extent of damage is postulated and not backed up by caleulations.
l Our review also identifie8 two iteEs that were not specifically addressed in
~
the safety Evaluation: .
1)
The Icad test should :;ualify the same length of cable that will be required for head'11ft.
- 2) 1 cad testing of the f abricated load test frame prior to Polar Crans I
load test has not been addressed, although all other rigging componatts have.
"here he", beea additional concerns raised that are not dirnetly rotated We plu u it.tsto: the .iit-i Safety Evaluation but which could be a potanual pror,ies.th is inadequate:
test.
- 1) Traising f ar :prit:rs ar.d perser x1 dizart',nc the ick:.
- 2) calibration et the lead cell.
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- .o the Polar "Jar,e--concerns hava been raised that 31 Modif':ations modificauens so the Polar trane vere not a;propriately docu:nented.
- 4) Test Prgram - verify that the prograrmatic, Omntrols for testing were followed (i.e . Ar-1M1 and At-1047 have been cceplied with) .
- 3) Reverify inspectica and refurbishment documentation.
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! Memorandue 4110-43.c33 . ,
February 23, 1983
I would recanumand Engineering ' assure themselves that they have adequately covered the two items noted concerning' the Safety Fraluation. Though hse items any not require any modification to the safety tvaluation, they try .
requize change or review for applicabit.ity to the actual load test implementin-procedures. -
I.n stammary, we in 9A hrve found no significaat programmatic problems with the safety Evaluation or the Polar crase refurbistment peccess but we will continu-to assess this prograc apd keep you. appraised of any problems discovered. It should be noted that there appears to be a nuabar vf technical concerns being ,
raised and these showe be addressed fully by Engi.neering.
An interesting ites to nots which we did discuss within QA was the approach Achtel has taken on this specidic safety tvaluation. Though it is acceptable from a programmatis sad engi.neering standpoint to perform the evaluat&tian has on a worst case scenario, in our recovery mods, there may be sw.e operationi considarations t. hat may make th'is approach not always prader.t. An a. alogy is ,
i la our industry for years we considered the large
- break krA the worst case '
limiting accident bef tre the di ace'ident, where as now we have learr.e4 that a small break Loch , deserves i..;ml s' tention. Serder Engineering management should perhaps review this issue.
I ,
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- 3. E. stils.rd, Sr.
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i Fanae r - TMI GA
. Modifications / operations BER:JTMicam , ,
cc: M. C. Earanas R. L. Zang CARIRS l
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Muknewe Pennsyhinia 17M7 reux .n 717 944.7421 4.ter's Oweet Del &imte: -
i i M Petgran Offina j Acta Mr. L. M. Barrem DierrJcy Prop as D!.ruuaae i l IB Nslaar hapdate.7 WW=S***'m . _
j e/o 'Dzse Mila IsLata E*1^^" _
MLddEar Ar., WA 17057 4 91 sua assions.
l Dear Sta an' I
These MLla Islard helaar Stathm, Dedt 2 (M-2) W ' "' ' ' ' "' ' l mw='
- 22C"~ I 0parating Liesnee h. Drt 73 i
Dochet 2 . S 320 C'
. Polar Cesan Refu W N 4 Enclooed ibe your approval is the Safety Raluatten laxst (SER) ter the
- Folar crans lead Test. This doansne ocecludes andthatera betm aconspl/ahed load test Joes with-noe aanstit:sta an tksmissed Safety
- out unian risk to the baalth and of tbs public. Your +Einn j in Mting tbs review and syproval tida h ==re in a tianly ==nnar is seestly vr
- If you have any quast*ms or desire furder %" H=; plaase feel free to er=*=ce Mr. J. J. Byrne of my 6taff.
Sincerely,
/s/ 3. L Eangs M -2 [
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