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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
[Table view] |
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- E S. Nucigar Regulatory Ceanissica
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I Seferencess (1) Letter and Inclosure 5. F. F. Bass. Jr., NRC, to E. E. Suhrke. 34W, March 18. 1977, subject Technical issues for Vender Partietsattoa .
j . (2) Letter, James L Taylor, 34W. to C. E.Hazetis, '
l- .. NBC, Angust 22, 1977, same subject
Dear Mr Nasetis:
Raclased are three (3) copies of our responses to 'the so selected technical issues published in NU21G.0128 and NORIG-0133, requested by your letter of March 18, 1977 (Beforence 1). These responses are in accordance with our 3] 1stter of August 22, 1877 (Reference 2). '
!; If you have ear further questions conceratag this matter.-
lj ,
plasse contact Mr. William R. Speight (1st. 2SO2)'ei y taff.,..
,d
, Very Ln truly yoursiyr . - - .
[k
.3 James N. Tay1
.. ,. Nasager, Licensing .. .
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- 1. O. Yesburgh W. R. Speight
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ha genent of stuastes Men ssfet, cende testement'in pvstostiene steas une ereas ucsoents ,
.j r4'.Babcock M tsad W11ces basically supports the NRC position as expressed
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back 0134 La regards to the use of sea. safety grade equipment s.
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. to safe co onents during a staan-Line break. ' The g number e issues ra sed y secondary.systes transients is large L
- t. and ceaplex enough, that a systematic approach to all secondary
; treasient issues should be undertshes. Therefore, in lieu of
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reiterattar the analysis assumptions currenti in recent SAR sub-
., mittals. SW proposed a series of meetin a vi the Ceanission ,
1eading towards final resolution of the asues involved with , . l 5f .s -
secondary system induced trsasiests.
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1s,s,3g,J,,a Delaved less of Offstte Power Pe11ewiar a LOCA* I l
tU * . . , , A. Offsite power remains available following a LOCA: the '
8
- diesels start; at seas time after the LOCA effsite power It %* sg is interrupted; critical lead 2 are interrupted for a -
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short time until sequessed en to the diesels. .
- 3. Offsite power reaalas available followier a LOCA: the *
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- diesels starts at some time after the LOCA and the ECC5'
- . signal is reset offsite 9 * ** aketdeum leads (met ECCS)are power sequencedis laterrupted, sa (the safe '.
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I' diesels any mise have been stepped, is which case:ther will have to be restarted). *
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This 1sses raises the sencets that the less of offsite power at
? . 4 *
$ sees time follow a LOCA would result in auch more severe de* .
esasequences than i effsite power were test sensurrent'with the t' ! **. ** .
LOCA transient. A study was performed to assess the nazimum I' - *"*..*.s est of a less of offsite power (LOOP) at say time fellowing 9
LOCA. A minor increase as peak claddiar temperature was ebtained: however, due to the sufficiently Iow probability for
. ., this assurrease. 34w fests that it is met necessary to consider g; .
- 1007 subsequent to the LOCA. ,,,,- ,
pellowing the LOCA. the ISPAS signals will actuate the* diesels, and will attala rated voltage"and speed withia 10 sesseds.
. If offs te power is them.last at seas time after the LOCA. ..'
M automatic sequencing features are provided se that interrupted ECCS flew '.e the core is fally re-established withia 20 seesada.
Per BEN's plaats, the ESPAS signal is act required to be reset.
j* Thus, part 3 et this issue is met to be~ addressed.
l l Am. t of a eaded LOOP t* afteranalysis a LOCA.has Thebeenworstperforand ease break, to assess an 8.5L theftp double
..* . break 'et the piump discharge with a Co
- 1.0. for SEN's 205 FA plaats was re. analyzed assuming a LO3P at the time the CFT's '
empty (36 seceeds). A delay of le seconds was them assumed before the BCCS flow to the core was fally re established. A
] -
100P at the time the CFT's empty will yield the naziana tapast en peak sladding temperature for the fellowias reasons
. 1. Prior to the time t:se CFT's empty, the laterruptions of-
. ECCE. flow because of a 100P would be less than 10 seconds g* des to the continued flew free the CPT's. Thus, the imps weeld be less severe than ti.at analysed.
; 2. At any time after the CPT's empty, the amount of time
- hat ECC3' flow would be interrupted dos to a LOGP
- weald be the same as that studied. Newever, for a 1007
,? that occurs lates thaa the time the CPT's empty, the j . sore geench frams would be higher and the sore decay
, heat lower than that analysed. Both of these conditions y
, will result in less-severe ceaseguences than that en=imad.
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is lessense to issue 4 (Cent'd)., .
The results of the ' analysis showed that the peak cladding j- g temperature Sacreased 70 7 to 2144,,7. ,, ,
- It is important to mete that this ame1 7sis was' performed'for '
- l ' ." . 34W's 305 FA staats which utilize Mark C (17 x 17) feel. Das to
, a alty en Mark C refleeding heat transfer esaditions (0.3
- tiplier sa the F12 CIA predicted coefficients), the sensequences
?,
of the LOOP ars highly everestimated. Because of the penalty. .
8 peak sladding temperatures occur,at opprezimately 100 seceeds Ie
, , rather than at approvinately 40 seconds as obtained for plaats with Mark 3 (15 x 15) feel. The extended ties to reach the anaimmt cladding temperature after the time the CFT's empty toads
'i-;
to enp*1fy the impact of the LOOF. Realistically q- - that stad?.iag temperatures would increase less tha. n 30 it isF.espected l f-The results of the analysis discussed above obviously seemd the'
- I effect of a LOOF subsequent to the LOCA for all Sgv plaats. Ia *
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addities,is it hshould be meted that the scenarie of events #
'j! analysed ble imprehable. If the less of offsite poser is t4 : a result of a gr perturbaties due to the LOCA, the less shea14
,. g escur within the first few secoats which is the.present analysis method. Thus, this sencess addresses an indey=d==t less ed Pouer. _ . .
. The probability of am 1A. ' t less of effsite poser la a
- ens neer period, according to WASE.1400, would be about one skaase
-l.i8 la 50.300. The likeltheed of a large LOCA is about ene chasse
' ;5 e4 la 10.000 per reacter year. Furthermore, the analysis that was
- per.
- e. formes.e .aa assumes in 20 a stagle is .ma se failure seen, of.on.e. th .diesel,whi.ch to.4 r. is about -ility of - - ~
;; this sequence of events is very les e
- t* As illustrated for SEN's plaats, the tapact of a LOOP subsequest .
-l to a LOCA results is only a miner impact sa peak sladding ture and does met endanger the public health. Also, the .,j ii*
- ability of the event is estremely low. Thus, the LOOP ,
11 swing a LOCA meed met be seasidsrod for 30f's plaats. j
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Ms Analysis of Postutsted Roseter Caetant Pm Reter
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'y the situaties of a concurrent i.e. staultaneens locked retor e
and less of offsite power is considered as incredible event.
Therefore, the situaties analyzed la response to this issue is a l locked roter event with less of offsite power resulting from *the .~,
subsequest rascter. turbine trip. ,
- The sequence of events for a tacled*Reter'Transiest with a less-t,. of effsite power as analyzed is gives in Table 1. As can be seen. .
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- a cesservative value of ISO millisecents is used for the time between turbine stop valve acties ase less of power to the RC
. ! - Famps. The systes rosynsee is shown in Figures 1. I and 3 for if\ L the mestros power, .systen pressure ar.4 AC flow respectively.
The resultant D(31 ase stad temperature response is skews is
, . Figure 4. As is clearly shows. the less of offsite pewer has a. ,
=,{ segligible result en the peck clad tesysrature. This cesparative lg result holds true for all 34W reacter types, altheagh the -result ef the locked retor transient asy vary depending sa plaat type.
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- a. Theprotectionphikesophyemployedbyall11Wplaatsagatast' flew 71 f amena11cs has been the use of a flux-te. flew trip feature.
J. parther protecties agatasc less of pusrs It isisS&W'rprovided by the that posities pump
.; , power mesitor status trip functies.these two 373 trip functions adequate
*pestvisted transiests and no addittoast protective devices are accessary. Justificaties of this posities is gives is the
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' A simplistic view of as underfrequency transions is to assume a t
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Therefore, the 1 to 1 ratie assumpties Also,is thecesservative an i4- primary assumed issue has to azist been decayfer the este, discussies whereas.toinfollow. reality, there exists two W. frequency limits to c Weder. Cae is the decay rats for.a sua.
ai , tained underfrequency transients the other is a minimum frequency
,. . above which sufficient flev exists as prevent CNE fres occurring.
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- per aes sustained decay rates that recover to assimal frequencies prior to totalThe frequency fluz.to. flew dec.ty trip below setpoint this ralue, the core is determined by one. remains 3
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- 41 . nised,f the source, l.a.. less of pump (s) er underfrequency.
l 'i e less fluz.to o . flew trip setpoint then deteraiaes the sustsiaed decay
..- rate for which protecties is provided and typically ranges fres .
. 1.6 Et/sec to 1.6 Nt/sec for 34W plaats. ~
If 1911 et rated power is divided by the flas.ts. flew rette.Ifa 4
conservative this flow is ceaverted flew is established by the 1 to asuch ratie that assumpties no CN1into occurs. a
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. say frequency decay rate that It is the recevers.before responsibility the is below typical values of 5d to 37 Ns.
* *ef each applicaat to deseastrate grid stability within this range.
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r, Regarding the afog of data gathering lacking; however, several programs, we feel ftha 9$ .
3enerally the availafailure in forty years to is determine ndervsy.
presenti prob- T I*
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i' " and it must be coatluded that data sufficientskility
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