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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:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20133C1961985-10-0101 October 1985 Submits Verification Results for Serial Numbers on Each Irvsp Capsule in Lynchburg Research Ctr Storage Pool,Per Rev 2 to BAW-1543 ML20100F7141985-02-27027 February 1985 Requests Info Re TMI-1 Restart.Concerns Raised ML20072K7191983-03-0707 March 1983 Forwards Evaluation of Small Break LOCA Operating Procedures & Effectiveness of Emergency Feedwater Spray for B&W-Designed Operating Nsss ML20064N7551983-02-10010 February 1983 Withdraws Proprietary Classification for BAW-10154P, B&W Small Break LOCA ECCS Evaluation Model ML20008F9151981-05-0505 May 1981 Urges TMI-1 Restart on Behalf of York Container Co ML20126F6821981-03-0303 March 1981 Favors Restart of TMI-1 on Behalf of Brandywine Recycler'S, Inc Due to Met Ed Extra Charges for Power Resulting in Economic Havoc for Many Businesses ML19350B0841981-03-0303 March 1981 Requests Immediate Restart of TMI-1 & Subsidies for Moving People from Vicinity of Facility ML19350B0641981-02-26026 February 1981 Expresses Opposition on Behalf of Wh Weaber Son,Inc,Re Plant Shutdown Due to Economic Reasons.Requests ASLB Rule in Favor of Restart ML20003C9191981-02-25025 February 1981 Requests Permission to Address 810305 Public Session on Issues Involved in Restart of TMI at William Penn Museum, Harrisburg,Pa ML19350B0631981-02-25025 February 1981 Supports Facility Restart ML19350B4391981-02-20020 February 1981 Requests Opening of Facility to Prevent Dependence on Foreign Oil ML20062K4231980-12-0909 December 1980 Comments,By Marion Plywood Corp in Marion,Wi,On Facility Restart.Facility Should Be Restarted Due to Necessity of Nuclear Power ML20062K4731980-12-0808 December 1980 Comments on Behalf of Pioneer Nuclear,Inc on Facility Restart.Nrc Should Place Situation in Realistic Perspective & Allow Plant to Return to Svc ML20002A9851980-12-0202 December 1980 Urges Restart of TMI to Alleviate Growing Cost of Electricity ML19345B9701980-11-21021 November 1980 Urges Swift Restart of Facility Due to Need for Energy ML19339C2891980-11-11011 November 1980 Requests Meeting W/Commissioners to Discuss TMI Situation & Solution for Problems Experienced by Certain Ratepayers ML19321B3251980-07-21021 July 1980 Requests Action in Restoring Svc to Facility.Economic Burden to Electricity Users Has Been Substantial ML19329G1141980-06-26026 June 1980 Urges Efforts to Restart Unit at Early Date Due to Rate Increase Approved by PA Public Util Commission for Met Ed Customers ML19323H8701980-05-20020 May 1980 Comments,Submitted on Behalf of Follett Corp,Re Restart of Facility.Return to Svc Will Reduce Cost of Replacement Power to Util Customers ML19254E1221979-10-12012 October 1979 Urges NRC to Rescind Order & Allow Unit to Start Up & Reach Full Power Operation ML20125B3871979-09-14014 September 1979 Responds to 790806 Request.Forwards Official Field Record of 790328 Reactimeter Setup,Tabulation of Changes Occuring in Following Months & Core Maps of TMI-2 Reactor ML19291C4831979-08-14014 August 1979 Expresses Support Re Restart of Facility.Operation of Facility Important to Economy of Harrisburg,Pa Area & to Vendor ML19260E2271979-08-0101 August 1979 Request Submitted on Behalf of Johnstown Sanitary Dairy That Restart Hearing Begin Immediately.Alternative Energy Costs Are High ML19254D1601979-07-30030 July 1979 Expresses Support by 11 Firms for Expedited Return to Svc of TMI-1 Because of Economic Considerations ML19209A2021979-07-27027 July 1979 Discusses Continued Shutdown of Power Plant & Increased Costs of Power Due to Shutdown.Requests Favorable Consideration of Early Return to Svc ML20024C5941979-05-12012 May 1979 Forwards Suppls 1 & 2 to Evaluation of Transient Behavior & Small RCS Breaks in 177 Fuel Assembly Plant, Vol 1, Section 6.0 ML20024C7431978-07-28028 July 1978 Forwards Responses to NRC 770318 Request for Info Re Selected Technical Issues for Vendor Participation Published in NUREG-0138 & NUREG-0153,per 770822 Ltr ML20090E9951977-04-0101 April 1977 Discusses Interpretation of 10CFR50.46 & App K by NRC & Impact on CP Licensing Proceedings.Recommends That Commission Provide Guidance to NRC ML1112303461975-12-30030 December 1975 Discusses Items 1,2 & 5 in NRC 750523 Ltr Re Integrated Control Sys, safety-related Sys & Protection Against Loss of Reactor Coolant Flow Due to Electrical Grid Frequency Transients ML19210B3721973-06-15015 June 1973 Forwards B&W Proprietary Repts BAW-1389, TMI-1 Fuel Densification Rept & BAW-10054,Revision 2.Includes Results for TMI-1 Fuel & Supports Operation at 2535 Mwt.Will Be Included in OL Application.Repts Withheld (Ref 10CFR2.790) 1985-02-27
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Babcock &Wilcox e ..,0 ne,ation a,ou, P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384 5111 September 14, 1979 i
George T. Frampton, Jr., Esq.
U.S. Nuclear Regulatory Commission TMI Special Inquiry Group, AR-400 Washington, D.C. 20555
Dear Mr. Frampton:
Enclosed are the documents listed below, which are in response to your letter of August 6, 1979 to G. L. Edgar, Esq:
- 1. A copy of the official field record of the reactimeter setup on March 28, 1979, and a tabulation of changes that were made !
during the two months following the TMI-2 incident. (Responsive to Para.1)
- 2. Core maps of the TMI-2 reactor showing placement of control ,
I
, rods, burnable poison rods, power shaping rods, active and C C g ka#. inactive instrumentation tubes, sources and source tubes, p traveling in-core probes, etc., that could serve as " heat sinks" during heatup of the core when it is partially uncovered; copies of in-core temperature maps as functions of time from h[ q0 March 28, 1979 to April 1, 1979, that were presented to members of the NRC/SIG staff on July 26, 1979 at Lynchburg. (Responsive i to Para. 2 and 3)
Additional materials will follow which are responsive to Paragraph 4.
Very truly yours,
& GWC-
. G. Mullin Contracts-Legal Nuclear power Generation Division JGM:nne Enclosures cc:
G. L. Edgar -
l 1
The Babcock & Wilcox Company / Established 1867 7911060 2 O
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Changes in TMI-2 Reactimeter Patch Tapes Date Thot LPA NR Deleted 3/31/79 Thot LPB tiR Deleted 3/31/79 RC Press. NR "B" LP Replaced by RCS LPB Press. WR 3/31/79 NI Flux (NI-5) Power Range Replaced by NI-3 Intermediate Range 3/31/79
. NI-1 Source Range Added 4/8/79 PZR LVL (Temp. Comp.) Added 4/8/79 PZR LVL (Ur. comp.) Added 4/8/79 PZR Spray Valve Pos. Replaced by Tcold LPA WR 4/8/79 Drain Tank Press. Replaced by RCS LPA Press. WR 4/8/79 Reactor Trip Deleted 4/8/79 FDW Temp. Deleted 4/8/79 Turbine KDR Press. (A) Deleted 4/8/79 Turbine Trip Deleted 4/8/79 SU FW Flow LPB Added 4/8/79 PZR LVL (Temp. Comp.) Replaced by Thot LPA (RC4A-TT1) 5/24/79 PZR LVL (Uncomp.) Replaced by Thot LPB (RC4B-TT1) 5/24/79 RCS Flow LPA (Temp. Comp.) Replaced by Teold LPA (RCSA-TT4) 5/27/79 RCS Flow LPB (Temp. Comp.) Replaced by Tcold LPB (RCSB-TT4) 5/27/79 I
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CA1.CITLATIO:t D.9TA/TTU.'IMITTAL S!!EET l
CALC, 32 - -
Doct"CNT IDr."'IFf ER TRANS 86 -
0139 _ _0 2 TYPE: ,,, ,rzsr.n.ot a ormctm.vr ,__ sam zw.tsts erroer J,_,px. sm. Irrvt _etstar terr. ,,_otstew mir.
_,,,_,or m TITLE TMI-2 CYCLE 1 FCLP WITHOUT ORA'S PREPARED BY ff . Ha rl m.f #7)[7 1 (# REVI2WED BY__ /k. (( f . . .S f r -
TnLE Assoc. Eng_ineer DATE 6/2/78TITr.2 ! b 4 2',.1,.(u m DATg/,//N
?
PURP03 E: To revise the Core Loading Plan for THI-2 Cycle 1 af.ter removal of UFK'~s.
l I l f ,
' \
FUW.RY Of ItESULTS (II:CLUDE D0C. ID'S OF PREVIOUS TRANSMITTALS & SOURCE CALCULA PACrd.GES FOR TilIS TRANSMITTAL) i REFEREllCES: 1) 'N.C. Harlow to Distribution, " Revised Initial Core loading Plan for l TMI-2", 86-0139-01, 660-021A/12 Ell.32/NA-78-38, July 13, 1977.
l 2) C.P. Jones to E.H. Cann, " Modified ORA ID flumbers", 6/2/78.
! 3) C.L. Gray to L.C. Rogers, " Burnable Poison and Mod. Grifice Rod Assy.
Retainer", T3.16.3/USS-6, June 1, 1978.
The attached Core.Loeding Plan for TMI-2 Cycle 1 is for use af ter removal of the original ORA's. It is identical to the plan presented in Reference 1 with the ex-ception of the ORA's, their modified replacements and Retainers. All Retainers are '
identified in Reference 2, as well as the modified ORA's to be used in Core locations 8-12 and P-4, where the Primary Neutron Sources are located. At these two locations the following loading procedures should be follcwed: Load Orifice Assembly (Modified ORA) into dumy F. A. , withdraw 0. A.with mast and insert into FA. Perform the Lock i
Test of the Orifice Assembly engagement in the fuel assembly. Verify by records that !
one of the Orifice Assercbly rods is correctly positioned in the Primary Neutron Source guide tube. Thereafter follow the procedure outlined in Reference 3 for installing the retainer, ;
Retainer #L006 only may be used as a substitute for LOO 4 or LC05 The release of this memo by document control indicates that the.necessary signoffs (DAR's) have been obtained per B&'.1 proccdures. The Source Calculational File is l 3?-7019-01.
l RIEdlUdkoli SEE DR"
(
Pac e _1__ c. f 2_ ,
- .- . _ = . - .
THI-11 II:ITI AL CORE LOADISC PIAN TUEL TRNISTER REVISION 2 CANAL >
l.
TP TY UC TC TW A
(Tr UC RL UB RF UA U1 UX C139 3153 C124 B158 C132 f U4 l B 03AT & LOO 4 LOO 7 L008 P TS T7 PW SN QS SY QB SC PY TB TF C B164 C163 0174 C179 B177 C172 B173 C156 B163
! nno r nin L0ll LO12 L0l3 TR TA PV T5 Q4 SW RC S1 Q2 T4 PT T8 TD D'. 8168 LO14 C155 B197 LO15 A024 B160 Lol6 C144 B183 L O17 A017 B200 I nio C152 Lg' U2 QS PN QN RX QG SZ QJ, TO RS PP PZ US E C162 B198 C131 B195 C171 B187 C164 B204 C128 B206 C157 LO20 LO21 LO27 LOP 3 ! n?4 TN UR RW QS R:1 R6 RS QZ S4 QK S7 QQ RH UQ TU i F C138 B171 A023 B202 C151 8146 C140 B155 C145 B201 A018 B182 C133 1 LO25 LO26 LO27 LO28 LO29 i_n30 TM SQ QV SO R2 RQ QX RP QE SM QB SS QA , RK Ud C B147 C178 B185 C170 B145 C183 B149 CISO B139 C165 B176 C173 B157 s , LO31 LO32 LO33 LO3d LO35 i n,c .LO37 ,
~
l UU UF S2 RD T1 QY SH RR SJ QF T2 RA SX UE UY E C127 B186 C147 3139 C143 B143 C123 B142 C141 B188 C145 3184 C125 1 H LO38 LO39 LO40 LO41 ! n4? Ino '
I UW RM Q7 RU R4 T3 QD RT QM SL QC SB Q9 RJ UV I K lg'52 C177 B161 C169 B141 C182 3144 C181 B154 C166 B179 C174 B
+
LO45 LO46 !nig , naq L Og1 Ln47 TQ UK RG QP SR QL SK R0 S3 QW RV Q3 SA UL T.'
L C137 B162 A022 B192 C150 B156 C142 B150 C149 B199 A019 B165 C134'
- _ LO51 LOS2 LO53 Loca L055 1 oc<
UO QR PM Q6 S8 R3 56 R1 RY R9 T6 QT TU H C161 BJo C130 B194 C16S B159 C167 B191 C129 B205 C158 Lus.) / LO58 LO59 LO60 LO61 TZ U9 PU SC Q1 SV RB , RZ QU PQ PS UH TE ,
N B175 C154 B203 A021 B180 C146 B181 A020 B196 C153 LO62 {},9Q um LO63 L OM i nc; ince 1 UB UJ QO 59 R7 ST R5 'S U PX T9 TT O B166 C160 B167 C176 B172 C175 B178 C159 B170 LO68 Ln69 ! n7n i n7i i a,e l
TV U6 UP RE UM SP 0'l U7 TX P LOO 5 & 03AU C1.36 B148 C126 B140 C135
} p LO73 LO74 i TH TL UD U3 TI R
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, Fuc1 Assembly ID (PS-PD: Batch 1; RE-T6 & PM-PQ: Batch 2; T7-UYtBatch 3)
Control Ca ponent ID (CXXX - CRA; AXXX - APSRA; BXXX - EPRA; OXXX MUO.CRA; Sources (P - Primary) LOXX -RETADIER)
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