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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:UTILITY TO NRC
MONTHYEARML20059H5351990-09-10010 September 1990 Forwards Encls 1-3 of Generic Ltr 90-07 Re Operator Licensing Exam Schedule ML20059G0641990-08-31031 August 1990 Advises That Util Agreed to Revised Frequency of Once Every 12 Months for Corrective Actions Audits Per Tech Spec Change Request 65 Based on 900718 & 19 Discussions ML20059F1691990-08-30030 August 1990 Requests Exemption from Requirements of 10CFR50,App J, Section III.D.1(a) for Facility Re Schedule Requirements for Connecting Type a Testing w/10-yr Inservice Insp Interval, Per 10CFR50.12(a)(2) ML20064A4661990-08-30030 August 1990 Responds to 900803 SALP Rept 50-289/89-99.TMI Does Not Expect to Be Lead Plant for Installation of Advanced Control Sys.Maint Backlog Goals Established.Info on Emergency Preparedness & Engineering/Technical Support Encl ML20059C8791990-08-29029 August 1990 Forwards TMI-1 Semiannual Effluent & Release Rept for Jan - June 1990, Including Executive Summary of Effluent Release Rept,Disposal & Effluent Release Data & Assessment of Radiation Doses.No Changes to ODCM for Reporting Period ML20059D5491990-08-29029 August 1990 Responds to NRC Re Notice of Violation & Proposed Imposition of Civil Penalty Re Personnel Inattentiveness & Failure of Site Managers to Correct Condition.Shift & Immediate Supervisor Discharged ML20059C7851990-08-27027 August 1990 Forwards Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility, Updating Minor Changes to Pages 6,8,9 & 13 ML20059C1091990-08-24024 August 1990 Forwards Rev 6 to Physical Security Contingency Plan.Rev Withheld ML20059B8251990-08-24024 August 1990 Forwards Payment of Civil Penalty in Amount of $50,000,per NRC ML20056B4651990-08-20020 August 1990 Corrects Statement Made in 900716 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Rosemount Transmitters. Identified That Only Half of Operating Crews Provided W/ Briefing on Bulletin ML20058Q1851990-08-17017 August 1990 Requests That Distribution List for TMI-2 Correspondence Be Updated to Be Consistent W/Recently Implemented Organizational Changes.Ee Kintner,Mb Roche & Wj Marshall Should Be Deleted ML20058Q1821990-08-13013 August 1990 Advises That Util Will No Longer Provide Annual Update to Dewatering Sys for Defueling Canisters Sys Description,Per NRC .W/Completion of Defueling & Shipment of All Defueling Canisters Offsite,Sys Has Been Deactivated ML20058Q1721990-08-13013 August 1990 Forwards TMI-2 Effluent & Offsite Dose Rept,First Quarter 1990, Update ML20058M7201990-08-0303 August 1990 Forwards Rev 2 to TER 3232-019, Div Technical Evaluation Rept for Processed Water Disposal Sys. Mods Include Elimination of Pelletizer & Relocation of Druming Station to Discharge of Blender/Dryer ML20055J4581990-07-27027 July 1990 Responds to Violations Noted in Insp Rept 50-289/90-10. Corrective Actions:Missing Support Brace on Cable Tray Support Found & Corrected ML20055J4561990-07-27027 July 1990 Advises That Info Contained in Generic Ltr 90-06,not Applicable to Current Nonoperating & Defueled Condition of Facility.Generic Ltr Will Be Reevaluated,If Decision Made to Restart Facility ML20055H6901990-07-20020 July 1990 Forwards Rev 25 to TMI-2 Organization Plan for NRC Review & Approval.Rev Proposes Consolidation of Plant Operations & Maint Sections Into Plant Operation & Maint Section ML20055G4431990-07-19019 July 1990 Forwards Rev 12 to 990-1745, TMI-1 Fire Hazards Analysis Rept & Update 9 to FSAR for TMI-1 ML20055G8781990-07-19019 July 1990 Discusses Compliance W/Reg Guide 1.97 Re Containment High Range Radiation Monitors,Per 900507-11 Insp.Physical Separation of Power Cables & Required Isolation Will Be Provided to Satisfy Reg Guide Category 1 Requirements ML20055F9601990-07-11011 July 1990 Forwards, 1990 TMI Nuclear Station Annual Emergency Exercise Scenario to Be Conducted on 900912.W/o Encl ML20044A9531990-07-0909 July 1990 Forwards Util Response to Weaknesses Identified in Maint Team Insp Rept 50-289/89-82.Corrective Actions:Engineering Personnel Reminded to Assure Documented Approval Obtained Prior to Proceeding W/Work ML20055E0481990-07-0505 July 1990 Documents Action Taken by Util to Improve Heat Sink Protection Sys & Current Status of Sys.Main Feedwater Logic Circuits Modified Prior to Startup from 8R Outage to Eliminate Potential for Inadvertent Isolation ML20055E0011990-07-0202 July 1990 Forwards Revs 1 & 2 to Topical Rept 067, TMI-1 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.5.4 ML20055C9971990-06-28028 June 1990 Forwards Rev 27 to Physical Security Plan.Rev Withheld ML20055D2071990-06-28028 June 1990 Forwards Certification of TMI-1 Simulation Facility,Per 10CFR55.45.b.5.Resumes of Personnel Involved Encl. Resumes Withheld (Ref 10CFR2.790(a)(6)) ML20055D0861990-06-25025 June 1990 Documents Deviation from Requirements of Reg Guide 1.97,per Insp on 900507-11.Based on Most Limiting Analysis,Existing Range of 0-1,200 Psi Sufficient.Deviation Consistent W/B&W Owners Group Task Force Evaluation of Reg Guide ML20043H4031990-06-18018 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements or Corrective Actions. ML20043H4851990-06-18018 June 1990 Forwards Application for Amend to License DPR-50,consisting of Tech Spec Change Request 179 ML20043F9921990-06-11011 June 1990 Forwards Listing of Exam Ref Matl Sent on 900601 in Response to 900505 Ltr ML20043F0661990-06-0404 June 1990 Forwards Inservice Insp Data Rept for Period 880816-900304. Owner Rept for Repairs or Replacements Performed on ASME Section XI Class 1 & 2 Components,Also Encl ML20055C9041990-05-23023 May 1990 Advises That App a to Rept Is Set of Recommendations from Safety Advisory Board on Possible Research Opportunities ML20043B2391990-05-18018 May 1990 Revises Commitments in Encl Met Ed 800430 Ltr Re QA of Diesel Generator Fuel Oil.Requirement for QC Review for Acceptability Prior to Filling Diesel Generator Fuel Oil Storage Tanks Deleted from Procedure ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A5311990-05-15015 May 1990 Responds to Violations Noted in Insp Rept 50-289/89-82. Corrective Actions:Periodic Insp Program Established Utilizing Checklist for Stored Equipment & Existing Tool Rooms Will Be Purged of Controlled or Unneeded Matls ML20043A2321990-05-11011 May 1990 Forwards TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5) Technical Rept 069.Evaluations Conclude That Test & Insp Results Demonstrate TMI-1 Reactor Bldg post- Tensioning Sys in Good Condition ML20042G2741990-05-0404 May 1990 Forwards Semiannual Update of Projects Listed in Categories A,B & C of long-range Planning Program Integrated Schedule ML20012F2621990-04-0202 April 1990 Responds to Violation Noted in Insp Rept 50-289/89-26. Corrective Actions:Util Policy of Shift Supervisor Involvement in Bypassing & Resetting Safety Sys Expanded to Include Shutdown Conditions & Technicians Briefed ML20012F2611990-04-0202 April 1990 Provides Supplemental Response to Station Blackout Rule. Target Reliability of 0.975 Chosen for Emergency Diesel Generators.Diesel Generator Reliability Program May Change Based on Final Resolution of Generic Issue B-56 ML20012F2731990-03-30030 March 1990 Confirms 900328 Conversations & Provides Technical Basis for Planned Actions to Correct Present Power Limitation Due to High Steam Generator Secondary Side Differential Pressure. Main Turbine Will Be Tripped from 80% Power ML20042D8281990-03-23023 March 1990 Fulfills Requirements of Tech Spec Section 4.19.5.a Re once-through Steam Generator Tubes post-inservice Insp Rept for Unscheduled Outage 8U-1 ML20012D7001990-03-22022 March 1990 Forwards Util Response to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Site Mgt & Staff Hour Categories Added to Response ML20012D7121990-03-21021 March 1990 Forwards Rev 0 to TMI-1 Cycle 8 Core Operating Limits Rept. ML20012C4771990-03-12012 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f). Current Design Adequate W/O Addl Tech Specs ML20012B8241990-03-12012 March 1990 Forwards Application for Tech Spec Change Request 199 to License DPR-50,revising Tech Specs Re Steam Generator Tube Insp Requirements ML20011F5251990-02-23023 February 1990 Documents Interpretation of Tech Spec 5.3.1.1 Re Design Features of Fuel Assemblies in Light of Issuance of Generic Ltr 90-02.Tech Spec Change Request Re Utilization of Dummy Fuel Rods or Open Water Channels Will Be Filed by 900420 ML20055C3931990-02-23023 February 1990 Documents Interpretation of Tech Spec 4.19.5.a Re once- Through Steam Generator Tube post-inservice Insp Rept for Refueling Interval 8R.Total of Eight Tubes Removed from Svc by Plugging ML20011F6651990-02-22022 February 1990 Forwards Updated Status Summary of Consideration of TMI-1 PRA Recommendations as of 891231.Changes to Torque Switch Settings for DH-V-4A & B Will Be Implemented in Refueling Outage 8 Re Closing Against High Differential Pressure ML20006C2901990-01-26026 January 1990 Provides Addl Info Supporting Deferral of Seismic Qualification Util Group Walkdowns to 10R Outage.Performance of Walkdowns Provide Proper Scheduling & Priority for Resolution of USI A-46 for TMI-1 ML20011E1221990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Audit Rept Determined That Operation of Decay Heat Closed Cooling Water Sys Consistent W/Design Basis Documents ML19354E8601990-01-25025 January 1990 Requests Approval for Use of B&W Steam Generator Plugs Mfg W/Alternate Matl (nickel-base Alloy/Alloy 600).Alloy 600 Has Superior Corrosion Resistance to Primary Water Stress Corrosion Cracking 1990-09-10
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' M December 1, 1980 The Hon. John F. Ahearne, Chairman Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Chairman:
It is the purpose of this letter to request that the Com-mission reconsider and modify its Orders of July 2, 1979 and August 9, 1979 dealing with the restart of Three Mile Island Unit No. 1 ("TMI-1"). We believe that an evaluation of developments since the entry of such Orders demonstrates that they have pro-duced consequences which are unjust and inconsistent with the public interest. The discussions at the Commission's public meetings prior to the entry of the August 9, 197,9 Order and.the terms of that Order manifested a clear expectation by the Commission that the hearings required by that Order would have been completed by February and that a Commission decision on the matter of lifting the suspension of TMI-l's operating a'uthority could be reached by September of this year. Yet the fact is that the hearings did not even begin until mid-October 1980. The consequence of those orders, has been to severely penalize the four million residents of our service areas and our hundreds of thousands of investors. Unless the Commissien takes action to expedite matters, authorization for operation of TMI-l will be further delayed for many more months.
We are addressing this request for re-consideration and modification of your July 2 and August 9, 1979 Orders to the Commission, rather than to the Atomic Safety and Licensing Board (ASLB), since it is the Commission (and not the ASLB) that can determine whether, in the light of all the pertinent considera-tions, such orders should be modified.
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December 1, 1980 l BACKGROUND AND 3 ASIS FOR THE ORDERS There is no legal requirement that the Commission employ the formal procedures which it has ordered prior to authorizing TMI-l restart. Section 189a of the Atomic Energy Act does not preclude continued operation of a nuclear unit while the Commis-sien has under consideration the matter of suspension or amend-ment of the operating license. The Commission is today proceeding on that basis with respect to other nuclear units. Prior to the adoption by the Commission of its August 9, 1979 order, we sug-gested that a discretionary (not mandated by the Act) public hearing could be held before restart is authorised and that the formal proceedings under Section 189a cou'i be initiated and go forward as a wholly separate matter and be completed after restart.
In a Lemoranden dated July 26, 1979, your legal staff pointed out the clear distinction between (1) a hearing on an order to suspend or revoke a license, which is governed by Sec-tion 189a of the Atomic Energy Act, and (2) a hearing as an aid o
to ena'le tF Commission to reach a decision as to whethe. re- .
start coulc be permitted, to which no statutory requirements are applicable. Your legal staff pointed out in that memorandum that, while the first type of hearing requires a full adjudi-
. catory hearing, "the Atomic Energy Act does not require the hear-i ing to be held prior to restart" (Emphasis in original)'. That memorandum pointed out that, with respect to the second type of hearing:
"No statutory requirements are applicable to any such hearing. Since the plants could be restarted in the absence of any hearing l
whatsoever, it wou1C appear to follow that if a hearing of Ki t nature were prescribed, no recuirementt. 3rre those of fairness, l
would be ace.!.3 y ,753Y." (Emphasis added) l l
l
December 1, 1980 Our efforts in July 1979 to persuade the Commission to adopt procedures that would permit the TMI-l issues to be addressed within a reasonable time frame were unsuccessful.
Instead the Commission chose to treat TMI-l differently than all othe. effected plants and ordered a full adjudicatory hearing with a further requirement for specific approval by the Commis-sion itself prior to restart. The Commission did not cive an adequate explanation of its discriminatory action nor is there any record that it considered the strong public interests to be served by procedures for TMI-l which were less time-consuming.
The Commission's Order, dated August 9, 1979, stated (at pages 3-5) that the bases for the conclusion (in the Commission's July 2, 1979 Order) that the Commission presently lacks requi-site reasonable assurance that the Licensee's Three Mile Island Unit No. 1 facility can be operated without endangering the ,
health and safety of the public" were:
- 1. "The NRC staf f has ascertained that B&W designed reactors appear to be unusually sensitive to certain off-normal transient conditions originat-ing in the secondary system. . ....
This, in turn, places a large burden on the plant operators in the event of off-normal system behavior during such anticipated tiansients."
The Commission's statement is applicable to all B&W reac-tors and, notwithstanding this statement, the Commission has permitted ull B&W units with operating licenses (other than TMI) to operate. Numerous reviews and studies have not resulted in any determination that B&W reactors cannot be operated safely.
TMI-l is not unique in this regard.
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- 2. "As a result of a preliminary review of the TMI-2 accident chronology, the NRC staff initially identified several human errors that occurred during the accident and contributed significantly to its severity."
1 There is no question that, with the benefit of hindsight, some of the actions taken by the TMI-2 operators were proved to have been inappropriare. But there is no question, also, that the actions taken by them were responsive to their training which reflected the perception by B&W and NRC of plant behavior during a loss of coolant accident. Both the Kemeny and the Rogovin reports clearly identify the critical linkage between presumed system behavior and operator action. Indeed prior experiences revealed that under circumstances such as those which occurred at TMI-2, operators were likely to inappropriately terminate high pressure injection when faced with high pressurizer level, but this finding by the NRC and B&W was not communicated by the NRC or B&W to the TMI-2 operators. The Kemeny and Rogovin reports point out that the TMI operators had superior qualifications in terms of background and experience and above-average scores in NRC qualifying examinations. To the extent that the August 9, 1979 order is predicated on the actions taken by the individual TMI-2 operators, it is not well-grounded since the Kemeny, Rogovin and other reports have since_ demonstrated that the principal cause of the accident and its severity was the failure to integrate and disseminate knowledge gained from the Davis-Besse investigation and other reports.
- 3. "In addition to the items identified for the other B&W reactors, the unique circumstances at TMI require i that additional safety concerns identified by the NRC staf f be resolved prior to restart. These concerns result from (1) potential interaction between Unit 1 and the l
. . )
December 1, 1980 damaged Unit 2, (2) questions about the management capabilities and tech-nical resources of Metropolitan Edison, including the impact of the Unit 2 accident on these, (3) the potential effect of operations neces-sary to decontaminate the Unit 2 fa-cility on Unit 1, and (4) recognized deficiencies in emergency plans and station operating procedures."
Even a year ago, it appeared probable that the Consission had overgeneralized its concerns as identified with TMI and that it had expressed such concerns in a way which would inc itably provide occasions for delay. In the light of the experience gained over the period since the entry of that Order, it is clear that this has been the situation. For example, in the Safety Evaluation Report ( SER) , ( NU REG-0680 ) , the staff refers to areas in which it regards existing s'andards as " inadequate" or where
" formal acceptance standards" do not exist, and for which "new acceptance criteria have been or are being developed." What this means in reality is that we are confronted with undefinable schedules which result from attempting to comply with non-exist-ent or changing criteria. At the same time, the staff is inter-preting the July 2 and August 9, 1979 Orders as requiring a complete demonstration to the Licensing Board as to just how the requirements will be met, even though the staff admits that some
- requirements have not been adequately defined and that it expects to impose additional requirements beyond those listed in the Orders, which have not been defined. Presumably, these require-ments will be imposed on at least all B&W plant licensees when i ultimately defined and are not unique to TMI. The matter is l further aggravated by the tendency of the staff to require full compliance with the long term actions, (NUREGS 660 and 0737), as
{ contrasted with the requirement of the Order for reasonable l
progress. These difficulties have been particularly manifested l in connection with the issues of management capability for which l
I l . .
6- December 1, 1990 criteria are in a continuing state of development and of e=ergency planning where the interface with FEMA is still in the process of definition. As a result, the staff is many months behind schedule in preparation for the hearings before the TMI-l ASLB. The issue of financial qualifications also lacks clear criteria, however compliance with the staffing and system modification requirements will constitute the best measure of adequacy of financial resources.
RESPONSIBILITY FOR THE DELAYS Let us make clear that we are not criticising the TMI-l ASLB for the delay. On the contrary, we believe that the Board has struggled valiantly to deal, in a timely manner, with the ill-defined assignment gi ve.. 7 it by the Ccamission. The delays are attributable primarily to the following:
(a) The Commission's orders defining the issues to be considered prior to restart, open up to relitiga-tion many of the NRC's licensing criteria applied not only to TMI-l but to all operating power reactors. As a result, our customers and investors have been made easy prey for those seeking to exploit all opportunities for delay; (b) The Commission's staff has not given the priority to this matter which the orders clearly contemplated; indeed, the staff has candidly admitted that this is the case.
( c) Some of the issues involve items for which the Com=ission either has not yet established criteria or for which it is unwilling to apply existing criteria; the result is that there are items for which there are no established standards against which our performance or that of other licensees can be measured;
December 1, 1980 (d) Even where there are purported standards, the staff interpretations frequently change and, with changes in staff personnel, these problems have been magnified.
(e) There is a staff tendency to reach out and require compliance before restart with actions identified for the future.
It -ay well be that the internal structure within the Com-mission, and the impediments to communications to the Commission from its staff and licensing boards, are such that the Commission is not adequately informed that the priority that it assigned to the TMI-l restart proceeding has been altered. More than two months ago, the Chairman of the ASLB for the TMI-l restart proceeding expressed concern on that score and stated (Prehearing Conference page 2436):
"I think that the Commission has to be made aware that the staff has allocated its prior-ities inconsistent with the schedule it first adopted, and inconsistent with the schedule that we thought we had some understanding on."
The follow-up September 17 Memorandum and Order of the ASLB states:
"There have been substantial delays in this proceeding. In November 1979 the NRC staff predicted that its Safety Evaluation Report (SER) would issue in January 1980. Tr. 553.
The SER, served June 16, 1980, remains incom-plete in several large and essential areas:
management capability and resources, financial qualifications, lessons learned Category A Items, and emergency planning. It is there-fore not possible to schedule an evidentiary hearing on those issues."
"This latest failure by the staff to meet its schedule predictions has once again raised the board's concern that the Commission should be informed that the expeditious hearing antici-pated in the August 9, 1979 Order and Notice of Hearing (10 NRC 141, 147) will not be realized."
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"When it became 1771 rent from the staff's report ;
on August 13 that the staff would not soon be )
ready to proceed to hearing on management, finan- ;
cial, and emergency planning issues, the board, in very emphatic terms, advised the staff that the Commission is not receiving the information it deserves in this case, and that the Commis-sion has a right to be informed that the pro-ceeding is threatened with further delay. As far as the board can determine, the staff has made no such report to the Commission."
The recent report of the Subcommittee on Nuclear Regulation of the Senate Committee on the Environment and Public Works and the Senate action on the' Commission's fiscal 1981 authoriration bill have urged that the Commission expedite the restart of TMI-l to the extent consistent with protection of the public health and safety. In his Report "Three Mile Island: The Financial Fallout" (EMD-80-89, July 7, 1980), the Comptroller General stated:
"NRC has treated Met-Ed's restart program differently from other utilities with Babcock and Wilcox reactors. We do not question their judgment in setting dif-ferent requiremen,ts and procedures, given the situation at TMI. However, we believe that the uniqueness of the situation that led to the differing requirements should also engender different procedures for expediting the corrective actions needed and the return of the unit to service.
Performance criteria that are lacking either for restarting TMI-l or cleaning up TMI-2 should be expeditiously fur-nished and timely decisions on company compliance with the requirements should be made. While full recognition of the
, public's right to participate in the l decision making process should be giv.en, the hearing process should be conducted so that it is as ecuitable to the uti..ities as it is to the public."
(emphasis added) i l
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w December 1, 1980 Ue respectfully suggest that the Commission should recog-nice that its actions in delaying the restart of TMI-l adversely impact the cost of electric energy to the four million residents of our service area (and the economy of that area) and conflict with National policies relating to foreign oil imports. Such delays also increase the cost and reduce the financial resources available to us to deal with the clean-up of TMI-2. The Orders of the PaPUC and NJSPU sum =arized in Section C7 of the SER
( NU REG-0680 ) made clear, as of that date, the interrelationship between authori=ation by the Commission of restart of TMI-l and our financial ability to continue with priority items.
The various reports and orders to which we have previously referred have demonstrated that one of the major problems in dealing with the aftermath of the TMI-2 accident is what the Comptroller General's report, dated July 7, 1980 (EMD-80-89) has characterized (at p.60) as the "present fragmented roles and responsibilities of the various Federal and State regulatory agencies". It also referred to the need to bring those roles and responsibilities together into'a unified approach towards re-solving the problems created by the accident. Action by the Commission in connection with TMI-l restart is central to achiev-ing that objective and accounts for the Comptroller General's recommendation that (at p.62) l . . .NRC move as quickly as possible, i
while taking all necessary steps to protect the public health and safety, to consider and act on the question of restarting TMI-1."
l l
RECOMMENDED ACTION What we are urging, in substance, is that the Commission r
re-examine the matter in the light of the developments in the past months since the July 2 and August 9, 1979 Orders were
10 - December 1, 1980 entered and thtt it recognise that the public interest is not served by prolon7 1 ng for many additional months the more than 16 months of forced shut-down which have already occurred since the July 2, 1979 Order.
Specifically we propose that the Commission follow a course consistent with its treatment of other B&W reactor plants by lifting the immediate effectiveness of its July 2 and August 9, 1979 Orders upon a determination by the Director of Nuclear Reactor Regulation (NRR), with the approval of the Commission, that the bases for making the suspension orders immediately effective have been satisfactorily resolved.
Such a determination would, of course, include a determi-nation that TMI-l has taken all of the actions required of other S&W reactors as a condition for resumption of operation following the shut-down orders issued to these reactors in the Spring of 1979. The determination would, in addition, encompass those con-cerns peculiar to TMI-l listed in the Commission's August 9 Order as bases for the immediately ef fective suspension of TMI-l's operating authority. The determination should be based on those criteria that are now in effect and/or apply to all other operating reactors. Further, we would expect the determination by the Director, NRR, to include compliance by TMI-l with those
" lessons learned" actions required by the Commission to have been implemented by other B&W plants at the time of TMI-l restart.
Determinations by the Director of Nuclear Reactor Regulation on the above matters would not remove such matters from the issues to be considered in the hearing before the ASLB and would not preclude the ASLB from recommending modification of those determinations based on the hearing record. The Director's determinations would serve solely as a basis for lifting the immediate effectiveness of the July 2 and August 9, 1979 Orders.
~
December 1, 1980 We do not propose that the TMI-l hearing now in progress before the ASLB be cancelled. We anticipate, instead, that the hearing would proceed along its present course with (1) the pre-sentation of evidence on all of the substantive issues enumerated in the Commission's August 9, 1979 Order, (2) the filing of proposed findings, (3) the issuance of a decision by the ASLB recommending the continuation, suspension or modification of TMI-l's operating license, and (4) the Commission's review and final action on the ASLB's recommended decision.
We do not suggest that the Commission should compromise public health and safety at TMI-l or at any other nuclear reac-tor. However, we believe that National and regional interests are being needlessly sacrificed by the continued delay in developing and applying appropriate procedures for expeditious authorization of TMI-l restart and that the Commission has the authority and responsibility to bring that sacrifice to an end.
Respectfully,
/.
. w ys
_, s n . -
H. Dieckamp .,
cc: Governor Brendan T. Byrne Governor Richard Thornburgh George H. Barbour, Pres. NJBPU Susan M. Shanaman, Chmn. PaPUC Commissioner Peter A. Bradford Commissioner Victor Gilinsky Commissioner Joseph M. Hendrie bec: R. C. Arnold E. L. Blakev/
P. Clark
- W. G. Kuhns J. B. Liberman G. F. Trowbridge E. G. Wallace Info. copies
- W. J. Dircks, NRC H. Denton, NRC Dr. B. Snyder,NRC l
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