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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:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML20248C0881989-09-0808 September 1989 Forwards Ref Matls to Accompany NUREG-0683,final Suppl 3 ML20134D7551985-05-0909 May 1985 Forwards Water Data Used to Prepare Document, Analysis of Possible Options for Reducing Occupational Dose from TMI-2 Basement ML20126G0811985-03-0505 March 1985 FOIA Request for TMI Emergency Evacuation Plan ML20086A1041983-09-28028 September 1983 Forwards TMI-1 Steam Generator Elastic Fracture Mechanics & Load Characterization, Technical Evaluation Rept ML20084E0111983-04-0808 April 1983 Forwards TMI-1 Steam Generator Degradation & Repair, Final Technical Evaluation Rept ML20070V2071983-01-0707 January 1983 Forwards Request for Refs Listed in Topical Rept 008, Rev 1,per NRC .Refs Necessary for Preparation of Technical Evaluation Rept ML20078B5441982-11-18018 November 1982 Forwards Minutes of 821018-19 Meetings W/Util in Bethesda,Md Re Steam Generator Repair Process Update & Return to Svc Overview ML20054J2171982-05-11011 May 1982 FOIA Request for Documents & Records Re DOE Decision to Accept Entire TMI-2 Nuclear Reactor Core & NRC Decision to Enter Into Memorandum of Understanding W/Doe ML20093C0431982-02-19019 February 1982 Notifies That Upon Implementation of Mods to Control Bldg Ventilation Sys Program Will Meet Criteria Identified in NUREG-0737 Item III.D.3.4, Control Room Habitability. Mods Include Addition of Redundant Low Leakage Dampers ML19350B0791981-03-0202 March 1981 Urges on Behalf of Whitmoyer Labs,Inc Restart of TMI-1 W/O Bypassing Safe Operating Procedures.Cost of Electric Power Should Be Lower ML20002B3521980-12-0404 December 1980 Requests Action to Expedite Restart as Facility Was Not Involved in TMI-2 Accident ML20049A3431980-12-0101 December 1980 Urges Restart of TMI-1 ML20003C8891980-08-0505 August 1980 Reviews EPRI Evaluation Re Potential Conservatisms & Ranges of Uncertainity in WASH-1400 Analysis of Iodine Release for Tmlb Sequence.More Research Required.Prof Qualifications & Certificate of Svc Encl ML19323F2131980-05-0707 May 1980 Forwards App C of Responses to Interrogatories.Consists of Telephone Survey Forms for Evaluation of Effect of Incident on Local Residents ML19290F0011979-11-19019 November 1979 Forwards Fire Protection Design Review.Discusses Fire Detectors,Automatic Sprinkler Sys,Fire Barrier Penetrations, Thermal Insulation of Valves,Emergency Feedwater Pump Penetration,Cable Separation & Relay Room Protection ML19250C3411979-11-19019 November 1979 Forwards Input to TMI-1 Design Review & Supplemental Items ML19210D0451979-11-13013 November 1979 Forwards Comments on Item 3.1.0 of Fire Protection Safety Evaluation.Will Require Licensee to Quantify Pressure Differential Between Areas Where Proposed Penetration Seals Will Be Installed ML20062H2931979-04-24024 April 1979 Forwards Requested Summary of Telcon ML19210A3611978-09-11011 September 1978 Lists J Riopelle Major Concerns Re 780817 TMI-1 Draft Safety Evaluation:Establish Program to Hydrotest All Fire Hoses at 220 Psi,Inspect Fire Hydrants for Drainage Prior to Freezing Weather & Provide 1-1.5 Hose Capability ML19210A3571978-09-0101 September 1978 Recommends That Electrical Supervision Be Required on All Control Valves in Fire Protection Systems Protection Areas Containing or Exposing safety-related Equipment ML20147B0211978-09-0101 September 1978 Advises That Review of Fire Protection for Facility Noted Areas of Plant Where Fire Could Affect Safe Shutdown & Release of Radioactivity.Presents Different Points of View on Value of Supervision by Util 1989-09-08
[Table view] |
Text
__
' v l
- . ' i Columbus Laboratories 563 Eng Avence t
Columbus. Ohio 41:m *
. Tetephone (6 4) 424-W24 l Teles 24 5454 August 5, 1980 ,
Mr. Robert Bernero Probabilistic Analysis Staff -
U.S. Nuclear Regulatory Cocinission ~
Washington, D.C. 20555
Dear Mr,
Bernero:
At your request, we have reviewed an evaluation that was made by EPRI of the. potential conservatisms and ranges of uncertainty in the WASH- Our c'om- s 1400 analysis of the iodine release for the TMLB'6 sequence.
ments follow. ,
The representation of attenuation factors for the WASH-1400 Scenario and Models (Case A) is somewhat over-simplified and does not quite represent what was actually done. Although only 88% of the iodine inventory was
(.. ,
assumed to be released during core melting in the vessel, the other 12%
was released during the gap'and vapo'rization periods. The attenuation factor should therefore be unity. Similarly, the fraction.of the con- .
tainment inventory released rapidly at the time of rupture was 0.85.
However, more iodine was released from containment.during the following In
- . hours as the result of gas production from attack of the concrete.
fact', RCB plateout and RCS rupture mode attenuation factors cannot be l
separated. In WASH-1400, 0.7 of the core inventory The of iodine was esti-total attenua-mated to be eventually released to the environment.
i In our reanalysis of TMLB'6 using PARCH tion factor was therefore 1.4 and CORRAL, the total release obtained was 0.31 for a total attenuation of 3.2. The reduction in .the predicted release of iodine relative to WASH-1400 is due to the improved treat:nent of containment themal-hydraulics afforded by PARCH, leading to increased plateout in the l
- containment.
- Case B, which is intended to be more realistic about attenuation factors, -
raises some interesting questions .that will require Some more of the effort most to resolve significant l
than is possible in this limited review.
issues relate to the details of the themal-hydraulic behavior in the pri-i-
mary system during core melting, though clearly there are substantial'un- He-f certainties regarding the chemistry and transport behaviorSome of iodine.
of the other will provide you with our current views on these issues.' in the un -
apsects of fission products attenuation have been address . and TRAP .
(
i tainty analyses that have been performed for PARCH / CORRAL 1
I 8103180 ( G y s n e ui ci ser,;ce 15.7-1US L
l
0 U l 2 August 5, 1930 j
' 1:r. F.abert Barnero j
/ !!e see no reason to be as optimistic about the core melt releasa fraction as indicated by EPRI in Case B. TheSASCHAreleaseexperiments[3Ishow
/. -
Although the f( 10 % release for iodine at the temperatures of interest.in these experiml p actor situations, we see no reason to assume enhanced retention; though 7 the chemical form of the iodine could obviously have an influence on its
-[c[s9/Vratios o
release. It has been speculated that some peripheral low power bundles may not actually melt in an accident of this type because of reduced self absorption of nuclear radiation and because of high thermal radiation to surrounding structures. Even if these were the case, it would only repre-sent a small fraction of the core inventory of iodine. We would estimate the range of the core melt release attenuation factor as 1-1.2.
We have investigated primary systen plateout for the TMLB's sequence ir)qn 1 uncertainty analysis associated with the developaent of the TRAP code.H Under the assumption that iodine is released as a vapor, the attenuation factor is predicted to be in the range of 1-1.02 with a best estimate of 1.007. If postulatedge iodine is actually released in the CsI, as Malinau dicted to be 1.1. These values
- are obviously well below the EPRI range of 1-100. .,
As implied earlier, water ' trapping of the released iodine is the most dif-ficult mode of attenuation to assess because of many uncertainties regarding the details of thermal-hydraulic conditions during meltdown as well as un-R certainties regarding iodine chemistry and transport. The first question is whether or not there will be water in the pressurizer during the time of iodine release from the fuel. Following dryout of the steam generators, Heat removal the flow through the primary system loops would stagnate.
- from the primary system would then be accomplished by steam generated in
- the core region passing to the upper plenum, to the pressurizer surge line in one of the hot legs,- through the pressurizer and out the relief'and/or safety valves to the pressurizer quench tank. As the steam passes through l
' the water in the pressurizer, both would be saturated. Except for some amount of carryover, the water in the pressurizer would not be released out the safety valve or boiled away. Prior to core uncovery, this water l
I would not be able to flow down against the countercurrent flow of steam from the core. At 2 hr following shutdown, the steam flow rate would be 5
o approximately 2.3 x 10 .lb/hr and the steam velocity in the surge line would be 7.8 ft/sec.
l
! countercurrent flow ir. pipes, the critical velocity above which no flood-ing (countercurrent flow of water) can occur is 1.8 ft/sec under these conditions. Thus, until significant core uncovery occurs, water would LOFT experiments also confirm beexpectedtogiaininthepressurizer.As core uncovery takes place, however, two im this behavior.
happen: The flow rate of steam decreases and the exit temperature of gases from the core becomes superhaated relative to the water in the pressurizer.
With no countercurrent flow of steam, the. pressurizer could empty into the primary system in approximately one minute. Thus, we would expect the water
~"
.) .
g August 5,1930 3
Mr. Robert Bernero in the pressurizer to flow back into the reactor vessel as the core ,
, being heatup.
uncovered and heated up.It would also,i however, this waterlead wouldto reevolu f
the water i; 'he pressurizer earlier in the accident s nceConsequently, ,
be subseq0e i evaporated.
water in tne pressurizer does not have a significant potential for retain ing iodine'in an accident of this type.
The tank.
other region in which water could trap fodin f presserizer is saturated at the pressure corresponding to the the relief and/or safety valves. .
back pressure, the steam remains saturated and actually gains tion (assuming a containment Thus, the saturated pressure water in ofrelief the 2 barstank the may quality not be would b imately 0.925).
heated and boiled away by the hydrogen released from the primary sy After core uncovery, the steam released from the If all of system primary superheated, but the flow rate would beit would significan Since k
take about 40 minutes to boil-away the g00 ft only a fraction of the decay heat would be transf of the pressure vessel.
If the water in the quench tank were subcooled, Since condensation the water of th would be very effective in scrubbing fodine from the flow.
is expected to be saturated, however, toe amount ofbubbles. iodine sc on the ability of the iodine toAssuming diffuse aout of the bubble.s water-steam before the partition coefficient escape the surface of the water. i f of 200, a subchergency of 5 feet, and71aUnder bubble s using mass transfer calculations for stagnant spherical i ld be bubble.
these assumptions, approximately 50 percent of the released iod ne w retained in the water. Variations in the above assumptions do not appe to markedly affect the above results.
from the fuel would flow out of the pressurizer and through the q Some of the iodine would still be in the primary system at the .
failure and would flow into the reactor cavity Based following on the abovevessel esti- hea without passing through water in the quench tank. ARCH results bound on mates of iodine diffusion out of the bubbles and observa regarding gases retained in the vessel, we would estimate the upper
- 10. ..
the po'tential for water trapping to be an attenuation factor of '
The amount of plateout in thel containm9n} has been studied At a i analyses of the MARCH and CORRAL codest / for this accident sequ 90%
2.3 to 20.
probability level, the range of attenuation factors but does notfa rate following containment failure as well as several otherAlthough it is p include attenuation in the leak path.
9 I O
l O a
/ 4 August 5, 1950 j gr. R:bert Bernero
/ containment failure mode could involve tortuous leak paths through the concrete which would result in significant attenuation; such a failure
- rode would not be consistent with pressure levels that challenge.the .
gross structural integrity of the containment, as have been considered in HASH-1400 and related studies.
Given the other accident assumptions, we see little basis for taking credit for significant attenuation in the leak path. .
Table 1 sea.arizes our estimates for potential iodine attenuation factors.
As you can see, our total range is much smaller than the EPRI evaluation and our best estimate is actually below the EPRI lower value.
We will not comment in detail on Case C since a wide variety of assumptions can be made about partial core melt accidents. The consequences will be obviously influenced by' the degree of core melting and, perhaps make im-Further, if con-portantly, by the effectiveness of containment sprays.
tainment integrity is maintained, the consequences to the public health would be minor regardless of other assumptions.
We believe that the exercise performed by EPRI has been useful in showing the magnitude of uncert.ainty associated with =any of the phenomena in the The THLS's accident, one of *the . dominant sequences for the WASH-1400 PWR.
evaluation provides good evidence that more research is required to enable accurate predictions to be made of the consequences of core meltdown acci-dents. It cannot be concluded, however, that the consequences of the THLS'd f.i..
'"' accident segeunces are being grossly overestimated under our current assumptions.
Sincerely,
~
,' ry) k . ^* 9 04( ,.
Richard S. Denning (
Research Leader Nuclear and Flow Systems Section RSD:erc .
xc: H. Cunningham, NRC O
e O
. O ()
t Mr. P.obert Scencro 5 Aupst 5,1950 l
l l
- ~
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/
/ TABLE 1. ESTIMATED ATTENUATION FACTORS FOR TML3'6 Low High B.E.
Core Melt 1 1.2 1 1.1 1
PCS plateout 1
~
Water trapping 1 10 2 RCB plateout 2.3 20 3.2
- 2.3 260 6.4
- c, e
6 I -
l t
0 I
1 i
4
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August 5,1930 Mr. R:bert Sernero 6
. (1) P. Baybutt, et al., "Results of Uncertainty Studies for the MARCH / -
CORRAL Code Package", to be published September, 1980. .
(2) P. Baybutt, et al., "An Assessment of LWR Primary System Radio-Nuclide Retention in Meltdown Accidents Using the TRAP Computer Code", CONF-800403/V-II, pp 1322-1327-(April,1980). .
(3) H. Albrecht, Y. Matschoss, and H. Wild, " Experimental Investigation of LWR Core Material Release at Temperatures Ranging from 1500 -
2800 C", unpublished.
(4) R. A. Lorenz, J. L. Collins, and A. P. Malinauskas, " Fission Product Source Terms for the Light Water Reactor loss-of-Coolant Accident",
Nuclear Technolocy, Mid-December,1979.
(5) G. B. Wallis, One-Dimensional Two-Phase Flow, McGraw-Hill Book Company, New York,1979.
(6) L.. P. Leach, "Results ana Evaluation of the Nuclear Tests", GRS-16 April, 1980. .
(7) Crank, J., The Mathematics of Diffusion, Oxford University Press, Oxford, 1967.
e e
O I
h Appendix II Resume of Dr. Jan Beyea m ,n m 9
I
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Rscums for Jan Boysa February 1981 EDUCATION:
Ph.D., Columbia University, 1968 (Nuclear Physics)
B. A., Amherst College, 1962 EMPLOYMENT HISTORY:
1980 to date, Senior Energy Scientist, National Audubon Society, 950 Third Avenue, New York, New York 10022.
1976 to 1980, Research Staff, Center for Energy and Environmental Studies, Princeton University.
1970 to 1976, Assistant Professor of Physics, Holy Cross College.
1968 to 1970, Research Associate, Columbia University Physics Department.
CONSULTING WORK:
Consultant on nuclear energy to the New Jersey Department of Environmental Protection, the Office of the Attorney General, Common-wealth of Massachusetts, the state of lower Saxony in West Germany and the Swedish Energy Commission, and various citizens' groups in tha United States. _._
PUBLICATIONS CONCERNING ENERGY CONSERVATION AND ENERGY POLICY:
" Details of the The Audubon Energy Plan," Peterson, Beyea, Paulson and Cutler, National Audubon Society, March 1981.
" Indoor Air Pollution," Commentary in the Bulletin of the Atomic Scientists, 37, Page 63, February 1981.
" Locating and Eliminating Obscure but Major Energy Losses in Resi-dential Housing", Harrje, Dutt and Beyea, ASHRAE Transactions, 85, Part II (1979). (Winner of ASHRAE outstanding paper award.)
" Attic Heat Loss and Conservation Policy", Dutt, Beyea, Sinden.
ASME Technology and Society Division paper 78-TS-5, Houston, Texas, 1978.
" Comments on the proposed FTC trade regulation rule on labeling and advertising of thermal insulation", Jan Beyea and Gautam Dutt, testimony before the Federal Trade Commission, January 1978.
" Critical Significance of Attics and Basements in the Energy Balance of Twin Rivers Townhouses", Beyea, Dutt, Woteki, Energy and Buildings, Volume I (1977), Page 261. Also Chapter 3 of Saving Energy in the Home, Ballinger, 197S.
"The Two-Resistance Model for Attic Heat Flow: Implications for Conservation Policy", Woteki, Dutt, Beyea, Energy--the International Journal, 3, 657 (1978).
PUBLICATIONS CONCERNING ENERGY CONSERVATION AND ENERGY POLICY (CONT'D.):
" Energy Conservation in an Old 3-Story Apartment Complex," Beyea, Harrje, Sinden, Energy Use Management , Fazzolare and Smith, Pergamon 1977, Volume 1, Page 373.
" Load Shifting Techniques Using Home Appliances," Jan Beyea, Robert Weatherwax, Energy Use Management, Fazzolare and Smith, Pergamon 1978, Volume III/IV, Page 121.
PUBLICATIONS CONCERNING NUCLEAR POWER SAFETY Articles:
""mergency Planning for Reactor Accidents," Bulletin of the Atomic Scientists, 36, Page 40, December 1980. (An earlier version of this article appeared in German as Chapter 3 in Im Ernstfall hilflos?,
E. R. Koch, Fritz Vahrenholt, editors, Kiepenheuer & Witsch, Cologne, 1980.)
" Dispute at Indian Point," Bulletin of the Atomic Scientists, -
36, Page 63, May 1980.
Published Debates:
The Crisis of Nuclear Energy, Subject No. 367 on William Buckley's Firing Line, P.B.S. Television. Transcript printed by Southern Educational Communications Association, 928 Woodrow Street, P. O.
l Box 5966, Columbia, South Carolina, 1979.
Nuclear Reactors: How Safe Are They?, panel discussion sponsored l
l
by the Academy Forum of The National Academy of Sciences, 2101 Con-stitution Avenue, Washington, D. C. 20418, May 5, 1980, to be published.
Reports:
"Some Long-Term Consequences of Hypothetical Major Releases of Radioactivity to the Atmosphere from Three Mile Island," Report to the President's Council on Environmental Quality, December 1980.
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PUBLICATIONS CONCERNING NUCLEAR POWER SAFETY (CONT'D.)
" Decontamination of Krypton 85 from Three !!ile Island Nuclear
' Plant", (with Kendall, et.al.), Report of the Union of Concerned Scientists to the Governor of Pennsylvania, May 15, 1980.
"Some Comments on Consequences of Hypothetical Reactor Accidents at the Philippines Nuclear Power Plant" (with Gordon Thompson),
National Audubon Society, Environmental Policy Department Report No. 3, April, 1980.
" Nuclear Reactor Accidents: The Value of Improved Containment",
(with Frank von Hippel), Center for Energy and Environmental Studies Report PU/ CEES 94, Princeton University, January 1980.
"The Effects of Releases to the Atmosphere of Radioactivity from Hypothetical Large-Scale Accidents at-the Proposed Gorleben Waste Treatment Facility", report to the Government of lower Saxony, Federal Republic of Germany, as part of the "Gorleben International Review",
February, 1979.
" Reactor Safety Research at the Large Consequence End of the Risk ;
Spectrum", presented to the Experts' Meeting on Reactor Safety Research in the Federal Republic of Germany, Bonn, September 1, 1978. l A Study of Some of the Consequences of Hypothetical Reactor Acci-dents at Barseback, report to the Swedish Energy Commission, Stockholm, DS I 1978:5, January,1978. ,
! ' Testimony:
" Advice.and Recommendations Concerning Changes in Reactor Design l.
and. Safety Analysis which Should Be Required in Light of the Accident o at Three Mile Island," Statement to the Nuclear Regulatory Commission
' concerning the proposed rulemaking hearing on degraded cores, Dec. 29, i 1980. ;
" Testimony on Behalf of the Anti-Nuclear Group Representing York
- j. Regarding A.N.G.R.Y. Contention.No. V(d)," submitted Sept. 30, 1980.
(This' testimony concerned filtered venting retrofits at TMI Unit No. 1 as-a condition of restart.) ___
" Alternatives to the Indian Point Nuclear Reactors", Statement
E
-before.the Environmental Protection Committee.of the New York City
' Council, December: 14,_1979. Also before the Committee, "The Impact i
on New York City of Reactor Accidents at' Indian-Point", June 11, 1979.
Also " Consequences of.a Catastrophic Reactor' Accident", statement to l the New York City Board of Health, August.12, 1976.(with Frank i
L ._ _.a. von Hippel).
-. e. ..-
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PUBLICATIONS CONCERNING NUCLEAR POWER SAFETY (CONT'D)
" Emergency Planning for a Catastrophic Reactor Accident",
Testimony before the California Energy Resources and Development Commission, Emergency Response and Evacuation Plans Hearings, November 4, 1978, Page 171.
"Short-term Effects of Catastrophic Accidents on Communities Surrounding the Sundesert Nuclear Installation", testimony before the1976.
California Energy Resources and Development Commission, December 3, /
" Consequences of Catastrophic Accidents at Jamesport". Written testimony before the New York State Board on Electric Generation Siting and the Environment in the matter of Long Island Lighting Company (Jamesport Nuclear Power Station, Units 1 and 2), May, 1977.
piscellaneous:
" Comments on WASH-1400", Statement to the Subcommittee on Energy and the Environment, Oversight Hearings on Reactor Safety, June 11, 1976, Serial No. 94-61, Page 210.
" Upper Limit Calculations of Deaths from Nuclear Reactors",
Bull. Am. Phys. Soc. 21, III (1976).
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a UNITED STATES OF AMERICA
. NUCLEAR REGULATORY COMMISSION fMTg_ ppF?.ESPONDENCB BEFORE THE ATOMIC SAFETY AND LICENSING BOARD
)
In the Matter of )
METROPOLITAN EDISON ) Docket No. 50-289 g q)
COMPANY, et~~
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) M occ:"ITO (Three Mile Island ) , cy:--
tiuclear Station, Unit pgg g 1gm
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CERTIFICATE OF SERVICE p I hereby certify that copies of the " Direct Testimony of Dr. Jan Beyea on Behalf of the Anti-Nuclear Group Representing York Regarding A.N.G.R.Y. Contention No.IIIB(D)" have been mailed postage pre-paid this 27th day Of February, 1901,to the following parties:
Secretary of the Commission Mr. Steven C. Sholly U.S. Nuclear Regulatory Commission Union of Concerned Scientists
, Washington, D.C. 20555 ' Suite 601 Attn: Chief, Docketlng & Service '1725 I Street, N. W.
Section ' Washington, D. C. 20006 James A. Tourtellotte, Esq. Jordan D. Cunningham, Esq.
Office of the Exec. Legal Director Fox,' Farr & Cunningham U.S. Nuclcar Regulatory Commission 2320 North Second Street Washington, D.C. 20555 Harrisburg, PA 17110 Robert !!. Adler, Esq. _
r.'ada Berryhill Assistant Attorney General Coall. n for " clear Power 505 Executive House Postpo < t P.O. Box 2357 2610 endon -
Harrisburg, PA 17120 W4 ington, Delaware . 8 Da .. Pt. P . Walter W. Cohen, Consumer Adv.
32 South 'ar Street Department of Justice York ennsylvani l'*1l Strawberry Square, 14th Floor Harrisburg, PA 17127
') - , .
4 Cert, of Service -
Docket No. 50-289 Ro ** L. Knupp, E qufre Chauncey Kepford Assista. Solici* Judith H. Johnsrud County of D in Environmental Coalition on P.O. Box- Nuclear Power 407 N . Front eet 433 Orlando Avenue Har 1sburg, PA 171 - State College, PA 16801 John A. Levin, Esquire t Q. Pollard Assistant Counsel Chesap Energy ' lance Pennsylvania Public Utility 609 Montpell reet Commission Baltim - , arylan 8 Harrisburg, PA 17120 Ms. Louise Bradferd Marvin I. Lewis TMI Alert .. .
6504 Bradford Terrace 315 Peffer Street Philadelphia, PA 19149 Harrisburg, PA 17102 ,
Ms. Marjorie Aamodt Ivan W. Smith, Chairman RD #5 Atomic Safety & Licensing Board Coatesville, PA 19320 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Walter H. Jordan Dr. Linda N. Little 881 W. Outer Drive 5000 Hermitage Drive Oak Ridg1, Tennessee 37830 Raleigh, North Carolina 27612
~
GeorgeF.Trowbridge,Esqukre MsT Jm.n fa Shaw, Pittman, Potts & R.D. 3 ox s.' ~
rs, Pennsylvania '4 Trowbridge 1800 M Street, N.W.
Washingto'n, D.C. 20036 .
/^ V .eu, r
// Dr. Jan Beyra e se O
.