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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:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20247B8801989-03-17017 March 1989 Forwards Radiological Emergency Preparedness Remedial Exercise Evaluation Rept, of 890201 Exercise.Offsite Emergency Preapredness Deemed Adequate to Provide Reasonable Assurance That Public Protected in Event of Emergency ML20196C4771988-11-0909 November 1988 Confirms Proposal to Renew Avisory Panel for the Decontamination of TMI-2 for 2 Yrs ML20151E0091988-07-18018 July 1988 Offers No Comments on Des for Facility ML20238A6471987-08-11011 August 1987 Informs of Status of Dept of Labor Position Re Util Subpoena for Desposition of D Feinberg,Per Enforcement Action EA 84-137.Dept Concerned That Feinberg Not Be Required to Testify Both at Desposition & at Hearing.Served on 870817 ML20234D0911987-06-15015 June 1987 Responds to NRC 870514 Request for Production of Documents & Availability of D Feinburg for Deposition Re NRC Civil Penalty Enforcement Action Brought Against Util.Feinburg Requested Not to Disclose Further Info ML20215M3891987-04-24024 April 1987 Forwards Detailed Comments on NRC Programmatic EIS Re Decontamination & Disposal of Radwastes Resulting from 790328 Accident at TMI-2.Recommends That NRC Not Select Alternatives Involving Discharges to Susquehanna River ML20215M1611987-03-31031 March 1987 Responds to Forwarding Draft Suppl 2 to TMI-2 Programmatic EIS for Review & Comments.Environmentally Preferred Alternative Appears to Be Onsite Evaporation. Comments Encl ML20212K3911987-03-0505 March 1987 Requests Denial of Util Requests for Subpoenas Re Dept of Labor Employees & File Matl.Further Accommodation of Util Would Interfere W/Internal Regulation & Business Operation. Served on 870306 ML20215M4221987-03-0303 March 1987 Comments on Draft Suppl 2 to Programmatic EIS Re Decontamination & Disposal of Radwastes Resulting from 790328 Accident at TMI-2.Suggests That Analysis Should Also Discuss Plans for Mitigation Measures to Be Undertaken ML20212D3851987-02-25025 February 1987 Comments on Public Health & Safety Impact Associated W/ Proposed Alternatives for Disposal of Water Contaminated as Result of Facility 790328 Accident,Per Suppl 2 to NUREG-0683 ML20210P8481987-02-0606 February 1987 Comments on Draft Suppl 2 to Programmatic EIS for Disposal of Radioactively Contaminated Water Stored at Site.No Existing or Proposed Corps of Engineers Projects Would Be Affected by Work Described in Draft Suppl 2 ML20207H9661987-01-0707 January 1987 Requests Listed Name & Agency Be Removed from Mailing List Re Facility ML20214Q8831986-09-15015 September 1986 Forwards TMI Site-Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification. Alert & Notification Sys Adequate to Protect Public ML20199G2181986-06-0909 June 1986 Forwards FEMA & Regional Assistance Committee Region III Exercise Evaluation Rept, for Exercise on 851120.No Deficiencies Identified.Deficiencies Identified at 831117 Exercise Corrected ML20153B9661986-02-10010 February 1986 Submits Responses to ASLB Suggestions for Improvement Re Offsite Radiological Emergency Preparedness Issues,Per 811214 Partial Initial Decision.Revised Plans Received for 36 Risk Municipalities ML20126M0701985-07-24024 July 1985 Forwards State of PA Emergency Mgt Agency 850621 Request for Exemption from 851120 Annual Radiological Emergency Preparedness Exercise for Lancaster County & FEMA 850628 Memo Agreeing W/Request,Per 10CFR50,App E ML20135H5161985-02-27027 February 1985 Responds to 850220 Request for Rept Re Dept of Labor Investigation Concerning Rd Parks Complaint Against Bechtel North American Power Corp.Sanitized Rept Encl ML20090K6121984-05-18018 May 1984 Forwards Updated Status Rept on Offsite Emergency Planning Issues Re Restart of Facility,Per 811214 Partial Initial Decision ML20083G6791983-12-20020 December 1983 Seeks Clarification of Commission Plans to Restart,In Light of Staff 831205 Recommendation That Commission Authorize Low Power Operation.Commission 840110 Meeting Should Either Authorize Restart or Establish Restart Conditions ML20063P3511982-10-0606 October 1982 Submits Updated Status Rept on Offsite Emergency Planning Issues at Facility.Emergency Preparedness Brochures Distributed.Siren Sys Testing Satisfactorily Completed. Communications Drill Held on Quarterly Basis ML20063P1781982-10-0606 October 1982 Responds to Aslab 811204 Partial Initial Decision Re Alert & Notification Sys.Siren Sys for Offsite Alerting Adequate, Pending Determination of Compliance w/NUREG-0654 & FEMA REP-1 ML20062P0331982-08-0202 August 1982 Responds to Approval Request for Info Collection Re Psychological Stress of TMI-1 Restart on Residents of Surrounding Communities.Request Not Approved (Withdrawn at Agency Request) ML17213A3201982-07-30030 July 1982 Transmits FEMA Interim Finding Re Offsite Emergency Preparedness,Based on Draft Plans Submitted by State of Fl & 820210-12 Exercise.Adequacy of Alert & Notification Sys Must Be Verified in Accordance w/NUREG-0654/FEMA REP-1 ML20054M8061982-06-18018 June 1982 Forwards Ja Myers Re Cleanup of Unit 2 & Restart of Unit 1 ML20040C6751982-01-19019 January 1982 Responds to ASLB 811204 Partial Initial Decision Re Emergency Preparedness Issues Per 811218 Transmittal.Pa Emergency Mgt Agency Expected County Brochures & Emergency Preparedness Pamphlet to Be Finalized Feb 1982 ML20004F3051981-06-16016 June 1981 Responds to 810323 & 0522 Requests for Interim Findings & Determination Re Emergency Preparedness.Pa State & Local Govt Response Plans for TMI Are Adequate.Certificate of Svc Encl ML20010A0841981-06-0404 June 1981 Forwards Ch Bell 810515 Ltr to DOE Re Delays in Facility Restart.Nrc Considered Responsible for Delay in Startup.Doe 810604 Response Encl ML20126L4971981-05-26026 May 1981 Confirms 810526 Comments in Response to NRC Requesting Review of Public Info Section of Facility Emergency Plan.Matl Is Acceptable Under Nrc/Fema Criteria. More Educational Matl on Radiation Would Be Useful ML20099E6821981-03-13013 March 1981 Castigates NRC for Withholding Gpu Employee Statements from Doj.Statements May Well Reverse Criminal Convictions.All Info Re Criminal Matters Referred to DOJ Must Be Given to DOJ ML20055B2401981-02-19019 February 1981 Responds to Ltr Commenting on R&D Activities Re Processing & Disposal of Radwaste at Facility.Handling & Processing of Wastes at TMI Site Should Be Limited to Well Established Operations ML19343C0821981-01-27027 January 1981 Forwards Analysis of Sys Adequacy & Reliability as Result of Continuing Outage of Facility,In Response to 810106 Request. Operation During Forthcoming Peak Load Periods Will Offer Major Adequacy & Reliability Benefits ML19345E8541981-01-27027 January 1981 Forwards Analysis of Continuing Outage of TMI-1 in Response to 810106 Ltr.Operating TMI-1 Would Minimize Probability of Brownout Recurrences in Summer 1981 & Result in Optimal Use of Generating Resources & Required Fuels ML19340E3881981-01-0606 January 1981 Forwards Review of PA REP Planning Site-Specific to Tmi. ML20062J4161980-10-10010 October 1980 Forwards Radon Info in Response to Request.Info Should Be Made Available to Aslab & Parties in Radon Proceedings ML20062J5201980-09-25025 September 1980 Comments on Draft EIS Re Facility Radwaste Decontamination & Disposal.Army Does Not Have Any Projects, Studies or Proposed Studies in Immediate Facility Area or Downstream from Plant.Illegible Ltr Encl ML19321A2931980-06-0404 June 1980 Forwards USGS Photographs of Exhibit Panel Featuring TMI computer-plotted Land Use Map.Jr Wray 800429 Memo Re Restart Hearing Map Exhibit Needs Full Size Copies.W/O Photos ML19321A3111980-05-29029 May 1980 Forwards Data Outlining Specs for Prototype Hazard Mitigation Maps.Compilations Will Be Completed by 800630 ML19326E1591980-01-22022 January 1980 Forwards D Hossler Ltr to President Re Intervenor Funding for Reply ML20125B5731979-10-29029 October 1979 Forwards Printout from Which Most Probable Cumulative Dose Was Derived.Input TLD Data for Upper & Lower Bound Calculations Encl ML20125B3991979-10-10010 October 1979 Responds to NUREG-0591.NEPA Process Should Be Integrated Into TMI Plans.Requests Meeting to Discuss Concerns Re Prospective clean-up Operations ML19211A5341979-09-26026 September 1979 Submits Preliminary Comments on NRC 790813 Ltr & Draft NEPA Regulations.Ceq Regulations Are Sufficiently Flexible to Avoid Conflict W/Nrc Responsibility as Independent Regulatory Agency.Certificate of Svc Encl ML20125B3541979-08-30030 August 1979 Forwards Misiti Re Release of Radioactive Gases from TMI ML20125B1881979-08-15015 August 1979 Forwards I Ahlers Re Levels of Natural Radiation ML20136C8311979-07-18018 July 1979 Requests That NRC Prepare Sequence of Events Leading to Concern That Hydrogen Bubble in Reactor Pressure Vessel May Have Been Combustible ML20136B1101979-06-28028 June 1979 Requests Summary Data Re Releases of Radioactive Matls & Regulatory Requirements ML20125B4971979-04-17017 April 1979 Forwards D Suchs Re Health Effects Resulting from Radiation Exposure.Requests Comment ML19290A4031976-01-13013 January 1976 Refers to EPA 751121 Ltr Notifying of Possible Conflict in Temp Limitations Imposed by EPA & NRC & Requesting Info Re NRC Rationale Used in Developing Tech Specs Thermal Limitations.No Response.Requests Info.Orig Ltr Encl ML19290A4051975-11-21021 November 1975 Informs of Possible Conflict in Temp Limitations Imposed by EPA & Nrc.Requests Info Re NRC Rationale Used in Developing Tech Specs Thermal Limitations ML19210A9951971-10-0606 October 1971 Comments on Amend 18 to Fsar.Requests Response ML19210A9261971-06-16016 June 1971 Responds to Deyoung 710306 & 0605 Ltrs Requesting Comments on FSAR 701216 Amend 15 & 710526 Amend 20.Comments Encl 1989-03-17
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e 10 5 r th 3 UNITED STATES ENVIRONMENTAL PROTECTION AGENCY WASHINGTON, D.C. 2046o i Mutft OFFICE OF EXTERNAL AFFAIRS let to W Dr. Michael T. Masnik TNI Project Directorate Office of Nuclear Reactor Regul ation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Dr. Masnik:
In accordance with Section 309 of the Clean Air Act and our responsibilities under the National Environmental Policy Act, the U.S.
Environmental Protection Agency (EPA) has reviewed the U.S. Nuclear Regulatory Consnission's (NRC) Draft Supplement No. 2 to the Progransnatic Environmental Impact Statement (EIS) related to decontamination and disposal of radioactive wastes resulting from the March 28, 1979, accident at Three Mile Island (TMI) Nuclear Station, Unit 2. This draft supplement (NUREG-0683) addresses the environmental and health impacts of disposal of water generated by the accident or used for cleaning up after the accident. The draft supplement identifies a number of potential alternatives for disposal of the water. These include on-site and off-site evaporation, direct solidification, continued on-site storage, and discharge of the water to the Susquehanna River after further treatment.
After extensive review and analysis, EPA has concluded that there are no significant radiation impacts from the proposed alternatives identified in the draft supplement. For each of these alternatives, NRC's calculated EPA dose exposures are below regulatory limits set by EPA and/or NRC.
has therefore rated this draft supplemental EIS L0, indicating a Lack of Objections to the proposed alternatives.
However, because this action involves a new non-routine discharge, EPA recommends that NRC not select either of the alternatives involving discharges to the Susquehanna River. An extraordinary national and multi-institutional (federal and state) effort is presently being implemented toward the restoration and protection of the Chesapeake Bay and its tributaries, including the Susquehanna River. A fundamental part of this restoration effort is to reduce the pollutant burden flowing into the Bay. Therefore, as a general rule, we believe that if there are viable alternatives to such non-routine discharges to the Bay or its tributaries, they should be given great weight.
8705130214 870507 DR ADOCK 05000320 PDR
Finally, because of public concerns regarding TMI and our desire to ensure that the NRC presents the most accurate description possible of the consequences of choosing any particular alternative, we are providing detailed comments to help clarify the basis for NRC's decision-making process.
I have asked Dr. William Kirk (FTS: 590-3909), Director, EPA Three Mile Island Field Station, and John R. Pomponio (FTS: 597-1181) of the Region III staff to provide any needed assistance to you.
Sincerely ,
Richa d E. Sanderson Director Office of Federal Activities Enclosure l
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Detailed Comments of the U.S. Environmental Protection Agency on the U.S. Nuclear Regulatory Comission's Programmatic Environmental Impact Statement related to the decontamination and disposal of radioactive wastes resulting from March 28,1979, accident at Three Mile Island Nuclear Station, Unit 2.
Draft Supplement Dealing with Disposal of Accident-Generated Water
- 1. Page V, Paragraph 3 -- We suggest adding "and lesser amounts of other radionuclides" to the second sentence. A table (or tables) should also be added to Section 2 with complete analytic information for all 25 or so compartments where accident water is located. These tables should include results of all analyses done, with Minimum Detectable Amounts (MDA) provided when results are below detection limits.
The Summary here, the data in Table 2.2, and the initial case data taken from the licensee's (GPUN) proposal for disposal of the accident water seem to conflict with the original tank content data provided by GPUN and what is achievable by ion exchange. For example: if Cs-134 is present in concentrations only 2-10 times less than Cs-137 in the untreated water, it will not be totally removed from the treated water while Cs-137 remains .
- 2. Page xxi -- Add "U.S." preceding " Environmental Protection Agency."
- 3. Page 2.2, Paragraph 2 -- Is it appropriate to say "very slight traces" for Sr-90 when the achievable (i.e., after initial treatment) concentration exceeds Appendix B, Table 2 (10 CFR 20) limits by a factor of 33, and exceeds the base case by a factor of 3677 In the base case, Cs-137 also exceeds the Maximum Permitted Concentration (MPC) in Appendix B, Table 2, of 10 CFR 20. We recognize that the table is correct and, that after final treatment, all standards will be met.
- 4. Page 2.3, Table 2.2 -- We recommend noting that the base case represents retreatment of 40% of the water as it currently exists and the " achievable" represents 100% retreatment.
- 5. Page 2.5 -- What is the source of the quoted background levels of Cs-137 and Sr-907 For example, EPA's latest Environmental Radiation Ambient Monitoring System (ERAMS) data published for Oct-Dec 1985- and Jan-Mar 1986 indicate a range of 1-3 pC1/1 Sr-90 in milk. A review of data 'or Region III indicates that concentrations have reached or exceeded 5 pCi/1 only two quarters since January,1975, and have not exceeded 3 pC1/1 since September, 1982. Yet, the document lists 5 pCi/l as the background level for Sr-90.
_m - _ _ . . _ _ _ . _ _ . _ _ _ . _ _ _ . _ _ _ _ . _ _ . __. .
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, 6. -Page 2.7, paragraph 2 -- This paragraph suggests that the only time '
that analysis was done for tritium in the Susquehanna River was in 1977.
> In fact, daily to quarterly sampling and analysis for tritium and other isotopes are done at 17 locations on the Susquehanna by Pennsylvania or EPA (either TMI or ERAMS) and other locations by several utilities including GPUN. The MDAs for these determinations are all of the order of 200-300 I pCi/1, however, and the results are below these levels. These routine programs should be mentioned to avoid giving the impression that no j
sampling has been done since 1977.
- 7. Page 2.10 - .Is this 1963 report the latest and definitive data on boron?
We recommend that NRC consider more recent references.
- 8. Page 2.13, para. 4 -- To assure consistency of presentation, we reconsnend extending the drinking water limit discussion to include all isotopes actually present in tanks.
- 9. Page 2.14, Table 2.5 -- (1) While we do not believe the results would be 4
affected, we reconnend NRC extend the presentation to include all isotopes
^
present in tanks, including a comparison of MOAS to Maximum Permissible i.
Concentration for Water (MPCw) (10 CFR 20, App. B, Table II) and Drinking Water Limits for isotopes found to be below MDA. (2) The MPCw for tritium
( App. B, Table II) is 3x10 3uci/ml, not 3x10 5 uCi/ml . The drinking
- water limit is 2x10 5 uCi/ml .
- 10. Page 2.15 -- The State of Pennsylvania is in the process of becoming i an Agreement State. If this occurs, it could have an effect on the disposal options for the waste.
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- 11. Page 3.1 -- We recommend the use of BEIR 1980 as a reference rather
, .han BEIR 1972.
- 12. Page 3.2, Table 3.1 (Note b) -- Unless demonstrated to be absent, other isotopes should be mentioned if present in the original tanks.
- 13. Page 3.14, para. 3.2 -- To clarify this alternative, the standards in 49 CFR 173 for bulk shipment of liquids should be explicitly compared with the nuclide concentrations in the water.
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- 14. Page 3.15, Section 3.2.1.1, para. 3 -- Has in situ vitrification been successfuly tested for quantities of waste this large? Intuitively, it seems the electrical demands would be very high.
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- 15. Page 3.16 -- The assumptions for nuclide concentrations for accident
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analysis should be explicitly stated. Both the base case and achievable case given in this supplement represent the average case of 2.1 million <
gallons of water which is actually in 25 separate compartments or tanks 4
! with concentrations as much as 2-3 orders of magnitude different from n the base case. There does not appear to be any simple way to achieve one uniform batch of water.
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- 16. Page 3.20, para. 3.3 -- Has the rist of transporting cement to the site been considered in the accident predictions for the options involving solidification of water or evaporator bottoms?
- 17. Page 3.23, Table 3.9 -- The predicted concentrations of Cs-137 in the finished cured concrete are not different from the average concentration in soil in this area. This would not add to gama exposure since it would, in effect, become part of an infinite slab source.
- 18. Page 4.9 -- Routine determinations of gross alpha and beta activity, as well as radium, etc., are done by Pennsylvania at many locations and should be mentioned.
- 19. Page 4.9, Sec. 4.1.3, para. 1 -- What are the units for the water table gradient? Offsite well monitoring conducted by GPUN and EPA should also be mentioned.
- 20. Page 4.12 -- The description of the vicinity given here should be cl ari fied. TMI is in the extreme NW corner of the area described.
Interstate Route 95 and State Route 10 have minimal importance to the area while routes not mentioned (Interstate Rtes. 81, 283, and Rtes.11,
' 15,322,422) are important.
21 . Page 4.13, Fig. 4.7 -- The figure shows TMI to be in the Northeast part of PA instead of the South Central, and does not show routes from TMI to Interstate Rte. 80.
- 22. Page 5.1, Sec 5.1, para. 2 -- The level of 87 mrem is probably somewhat lower than real per capita background exposure. From the Aerial Radiation Monitoring System overflight data, ambient external gama radiation ranges from 70-120 mrem /yr. Also, many houses in the TMI area have elevated radon levels, resulting in lung doses much higher than the external gama levels.
- 23. Page 5.2, Table 5.1 -- The impact of the Short-Tem River Discharge is the same as that of Long-Term River Discharge only if the same river flow is used. If a more reasonable higher flow is used, impacts are much lower.
- 24. Page 5.3, para,1 -- We recommend adding "at 87 mrem /yr." before "300,000 people will receive..." .
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! 25. Page 5.4, Sec. 5.2, para. 2 -- EPA policy is to use BEIR 1980 values and the relative risk model for calculating risks which, as noted, will yield slightly higher risk estimates.
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! 26. Page 5.8, Sec. 5.4, para. 2 -- The accident scenario described here
' would appear to be impossible rather than highly improbable since the water is in 25 separate tanks / compartments.
- 27. Page 5.9, Table 5.2 -- See comment for page 3.2 - Cement transportation.
- 28. Page 6.1, Section 6.0, Conclusions -- EPA concurs with the NRC Staff's
- conclusion that no significant environmental impact from a radiological I standpoint will be incurred from any of the proposed alternatives.
! 29. Appendix B is so generally written that persons without a technical
! background cannot understand how the calculations were made. Many references, including the applicable NRC regulatory guides, are not mentioned. It is not clear how the pathways to man were calculated, what bioconcentration,
- accumulation, and transfer factors were used, what fish / shellfish species were considered and how food web elements were incorporated into the model . Major clarification or explanation is needed.
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- 30. Page B.1 -- Where do the data for swimming come from? There appears to be very little swiming in the Susquehanna River in the TMI area.
1 31. Page B.2 -- What is the basis for the shellfish harvest and consurption figures? No references are given.
! 32. Page B.3 -- What is the basis for 434 lb./yr. vegetable consumption?
This sounds high, especially if this is supposed to be local consumption ,
- of locally grown vegetables.
- 33. Page B.4 -- What is the basis for doubling innalation dose to account for
, ingestion of contaminated vegetables? This sounds very conservative for Nevada where precipitation, fog, etc., are relatively rare and gardens
- would have to be irrigated.
I 34. General. For the sake of clarity it would be instructive to include a section or appendix explaining what estimates of 0.03 or 0.4 or 1.5 i
cancer deaths really mean in terms of likelihood of having 0,1, 2, 3, 4 i cases or deaths.
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