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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
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
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
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
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
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
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
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
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
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
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
ML20211L2401999-09-0101 September 1999
Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates
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
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
ML20211H3571999-08-19019 August 1999
Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019
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
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
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
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
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
ML20216D4001999-07-22022 July 1999
Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999
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
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
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
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
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
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
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
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
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
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
ML20196J5631999-07-0101 July 1999
Informs That Util 981203 Joint Application with Amergen Energy Co Marked Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
ML20206H0781999-04-30030 April 1999
Forwards Rev 0 to 1092, TMI Emergency Plan. Summary of Changes Encl
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
MONTHYEARML19325E9001989-10-19019 October 1989
Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response
ML19327A8441989-10-11011 October 1989
Forwards Pleadings,Motions & Orders Filed in Alchemie Reorganization Action.Alchemie Currently Preparing Reorganization Plan Which Will Serve as Framework for Future Company Business Activities
ML19327B2491989-10-0606 October 1989
Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept.
ML19327A8511989-10-0505 October 1989
Forwards Wh Arowood 890907 Ltr & Other Supplemental Info to Replace Info Previously Filed
ML20247F4121989-08-31031 August 1989
Advises That Response to Order Modifying Licenses & Order to Show Cause Why Licenses Should Not Be Revoked Will Be Sent. Responses to NRC Three Basic Questions Re Status of Licensee Finances & Rationale for Having License Provided
ML20246B1671989-08-0808 August 1989
Forwards Response to 890717 Request for Info Re Filings W/ Us Bankruptcy Court & Financial Capabilities.Ownership of Unclassified Equipment Remains Unchanged
ML20247Q5521989-05-24024 May 1989
Notifies That J Smelser Contract Ended,Effective 890517. Mgt of Company by Listed Board of Director Members Will Continue Until New Chief Executive Officer Selected
ML20247P8071989-04-0404 April 1989
Forwards Ltr in Which Concerns for Potential Significant Deficiency Under 10CFR21 Expressed
ML20247G4991989-03-30030 March 1989
Forwards Proprietary BAW-10175P, Rod Exchange Methodology, Developed for Calculating Parameters While Performing Control Rod Measurements Using Rod Exchange Technique to Be Used at Plants.Rept Withheld (Ref 10CFR2.790)
ML19324C3151989-02-20020 February 1989
Informs of Change in Vendor Plans for Inspecting Fuel Rods Containing Fuel Pellets Supplied by Ge.Ultrasonic Insp of Fuel Rods at Oconee 1 Found No Failed Rods in three-cycle, Discharged Fuel Assemblies
ML20235M8971989-02-10010 February 1989
Requests Withholding of Proprietary WCAP 12125, Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per 10CFR2.790
ML20206D6241988-11-11011 November 1988
Forwards Projected Decommission Costs of Centrifuge Machines to Be Transferred to New Facility at Oliver Spring,Tn. Licensee Will Be Able to Offset Total Decommissioning Costs by Setting Aside Annual Decommissioning Cost Plus Reserve
ML20205Q6331988-11-0202 November 1988
Forwards Revised Proprietary Pages to BAW-10164P, RELAP5/Mod2-B&W,Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis. Cso Film Boiling Correlation Replaced w/Condie-Bengston IV Correlation & Typos Corrected
ML20205P9511988-11-0101 November 1988
Forwards Rev 6 to Security Plan for Alchemie Facility 1 - Cpdf,Oak Ridge,Tn & Rev 6 to Security Plan for Alchemie Facility 2 - Oliver Springs,Oliver Springs,Tn. Revs Withheld (Ref 10CFR2.790(d))
ML20195E4291988-10-31031 October 1988
Forwards Numbers 1-5 of Rev 5 to Alchemie Security Plans. Requests Replacement of Pages 23-25 & 35 & Encl Rev Page
ML20205N3301988-10-27027 October 1988
Forwards Sketch of Feed Sys,Withdrawal Sys Refrigeration Cart & Typical Withdrawal,Large & Small,Pumping Stations
ML20195B6091988-10-21021 October 1988
Forwards Summary of B&W Fuel Co Position Re Small Break LOCA Calculations Contained in Util FSARs for Upcoming Reload Cores Which Will Contain Fuel Mfg by B&W
ML20154K3841988-09-12012 September 1988
Forwards Enhanced Facts Re Adequacy of Funding for Decontamination & Decommissioning (D&D) of Facilities. Intends to Establish Funded Reserve for D&D at Completion of Sale of Unclassified Equipment Not Needed for Production
ML20154E6451988-08-31031 August 1988
Requests That 880722 & 0812 Ltrs Re Security Sys Components Be Withheld from Public Disclosure (Ref 10CFR2.790(d))
ML20207L7651988-08-30030 August 1988
Requests That Proprietary WCAP 11935, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue, Be Withheld from Public Disclosure (Ref 10CFR2.790)
ML20151H9381988-07-25025 July 1988
Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants
ML20151M9211988-07-20020 July 1988
Responds to 880621 Request for Addl Info Re Enrichment of Naturally Occurring radioisotopes.Te-123 Will Be Enriching Approx 60 G to About 50%
ML20151L3321988-07-20020 July 1988
Forwards DOE Ltr Indicating Acceptance of Classified Matter. Licensee Agrees to Remove Any Toxic or Hazardous Matl from Classified Equipment Prior to Transfer to DOE for Disposal
ML20151G9761988-07-14014 July 1988
Forwards Rev 2 to Security Plan for Shipment of Classified Matter.Rev Withheld (Ref 10CFR2.790)
ML20150F1561988-07-0808 July 1988
Advises of Changes to Alchemie Board of Directors,Per 880618 Annual Stockholders Meeting
ML20155F4441988-05-0404 May 1988
Responds to NRC & Request at 880504 Meeting Describing GE Program to Reconfirm Design Adequacy of Associated Circuits in GE Bwrs.Upon Completion of Phases 1 & 2 of Evaluation of Bwrs,Ge Will Submit Summary by 881104
ML20151F7661988-03-29029 March 1988
Forwards Updated Pages to Proprietary BAW-10171P, REFLOD3B- Model for Multinode Core Reflooding Analysis, Per ECCS Methodology for Facilities Reloads.Mod Removes Henry Quench Temp Criteria & Potential Conflict in Logic.Pages Withheld
ML20234C2231987-12-28028 December 1987
Forwards Proprietary BAW-10164P, RELAP5/MOD2-B&W,Advanced Program for LWR LOCA & Non-LOCA Transient Analysis. Rept Describes Computer Code Used to Analyze RCS Behavior During Blowdown Phase of LOCA Transient.Rept Withheld
ML20234D1101987-12-14014 December 1987
Forwards Proprietary BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis. Rept Describes Computer Code That B&W Will Be Using to Analyze RCS Behavior During Refill of LOCA Transient.Rept Withheld
ML20237C3611987-11-24024 November 1987
Requests That Proprietary Rev 2 to WCAP-11386, Byron/ Braidwood T-Hot Reduction Final Licensing Rept, Be Withheld (Ref 10CFR2.790(b)(4))
ML20236C0261987-10-22022 October 1987
Forwards Proprietary BAW-10165P, FRAP-T6-B&W:Computer Code for Transient Analysis of LWR Fuel Rods. Rept Describes Computer Code That B&W Will Be Using for Future Transient Analyses of LWR Fuel Rods.Rept Withheld (Ref 10CFR2.790)
LD-87-056, Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request1987-09-18018 September 1987
Forwards Summary of C-E Fuel Irradiated &/Or Discharged in 1986 on plant-by-plant Basis in Response to 870807 Request
ML20236H4971987-07-29029 July 1987
Forwards Draft Proprietary Topical Rept BAW-10166P, Beach Computer Code for Reflood Heat Transfer During Loca. Draft Submitted to Permit Interaction Between B&W,Nrc & Util. Affidavit for Withholding Encl.Fee Paid
ML20236B4141987-07-13013 July 1987
Forwards Proprietary Draft 1 of BAW-10168P, ...B&W LOCA Evaluation Model for Recirculating Steam Generator Plants, to Be Used for LOCA Analysis of Catawba & McGuire Reload Fuel Cycles.Rept Withheld (Ref 10CFR2.790).Fee Paid
ML20196K1621987-07-0909 July 1987
Partially Deleted Ltr Submitting Addl Info in Response to NRC 861230 & 870211 Requests Re 860918 Application for Exemption from Requirement to Convert from High Enriched U to Low Enriched U for Reactor Fuel,Per Generic Ltr 86-12
ML20215L0591987-06-22022 June 1987
Responds to Request for Assurance That Facility Neutron Monitoring Sys Design Similar to Design of Other Plants.List of Plants W/Similar Design,Already Reviewed & Approved by Nrc,Encl
ML20215D4081987-05-15015 May 1987
FOIA Request for Reactor Vessel Surveillance Capsule Repts for Turkey Point 4,Zion 2 & DC Cook 1
ML20237D2761987-04-27027 April 1987
Forwards List of 200 Parameters That Company Will Provide to Offsite Agencies,Per Request to D Schultz.List of Parameters That Will Be Available to NRC Via Zion Data Link During Coming Federal Field Exercise & Dryrun Also Encl
ML20212R4711987-04-15015 April 1987
Forward Proprietary Draft 1 to BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis, for Review of ECCS Methodology for Plants Fuel Reloads,Per . W/Affidavit.Draft Withheld (Ref 10CFR2.790).Fee Paid
LD-87-017, Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days1987-04-10010 April 1987
Responds to 870327 Questions Re Steam Generator Tube Vibration Observed at Palo Verde Units 1 & 2.Definition & Scope of Program to Review Phenomenon Will Be Available for Review W/Nrc in Approx 90 Days
ML20206E7851987-04-0202 April 1987
Confirms Intention to Use FOAM2 Computer Program as Part of ECCS Evaluation Model for Westinghouse Designed Plants. Review of Applicability of Code to Westinghouse Designed Plants Requested Prior to 880701
ML20237D6431987-03-25025 March 1987
Forwards Technical & Cost Proposal for Task Order 009, Continuing Exercise Support to NRC Operations Ctr, Electronic Transmission of Plant Parameters During Exercises, Under Contract NRC-05-86-170
ML20237D6681987-03-0404 March 1987
Forwards Revised Draft Statement of Work Proposed for Task Order 009, Continuing Exercise Support to NRC Operations Ctr,Electronic Transmission of Plant Parameters During Exercises, for Contract NRC-05-86-170
ML20237D6881987-02-14014 February 1987
Forwards Parameters & Computer Points That Author Will Be Attempting to Get Util to Make Available for Transmission to NRC During Federal Field Exercise - 2
ML20205G1591987-01-20020 January 1987
Requests Proprietary Responses to NRC Review Questions Re Resistance Temp Detector Bypass Elimination Be Withheld (Ref 10CFR2.790)
NRC-87-3194, Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted1987-01-0707 January 1987
Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted
ML20214P1911986-11-19019 November 1986
Forwards Proprietary NEDC-31336, GE Instrument Setpoint Methodology, Per Lrg Instrument Setpoint Methodology Group .Rept Applicable to Listed Plants & Withheld (Ref 10CFR2.790)
ML20213H0151986-11-14014 November 1986
Forwards Proprietary Draft 1 to BAW-10165P, FRAP-T6-B&W Computer Code for Transient Analysis of LWR Fuel Rods. Rept Submitted to Permit Interaction Between NRC & B&W to Support Util Schedule Needs.Rept Withheld (Ref 10CFRF2.790)
ML20207H9471986-11-12012 November 1986
Requests Withholding of Proprietary WCAP-11323, Resistance Temp Detector Bypass Elimination Licensing for Byron 1 & 2 & Braidwood 1 & 2, from Public Disclosure,Per 10CFR2.790. Affidavit Encl
NRC-86-3160, Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P1986-09-0808 September 1986
Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P
1989-08-08
[Table view] |
Text
o fe r e, o
MXEDO March 7, 1983 lEE)l!I()lYl RcHaac P. Caoust
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14191259 5221 Mr. H. R. Denton Nuclear Regulatory Commission 1717 H Street, N.W.
Washington, D. C. 20555
Attachment:
" Evaluation of SBLOCA Operating Procedures and Effectiveness of Emergency Feedwater Spray for B&W-Designed Operating, NSSS,"
B&W Doc. I.D. 77-1141270-00, dated February 1983.
Dear Mr. Denton:
The B&W Regulatory Response Group (RRG) met with members of your Staff on February 23, 1983 to present the results of our re-review of emergency feed-water spray effectiveness and SBLOCA operating procedures.
The attached report documents the details of the review and is provided for your use on behalf of the Utilities with B&W-designed operating NSSS. I met briefly with Mr. R. A. Purple on March 2, 1983 and left several copies with him.
Our conclusions are that: 1) the EFW spray is effective under SBLOCA con-ditions and adequate core cooling is provided, and 2) existing Utility operat-ing procedures and operator training programs provide sufficient guidance to the operators to assure the safe mitigation of small breaks (isolatable and non-isolatable) in the primary system.
If you require any followup, please contact Mr. Ed Wallace, Chairman of the E&W Owners Group Steering Committee, at the GPU Nuclear office, 201/299-2191.
Very truly yours,
[
Chairman, B&W Regulatory Response Group cc: D. G. Eisenhut - w/a R. A. Purple - w/o B. Sheron - w/o B&W RRG Representatives - w/o E. G. Wallace - w/o 8303300717 830316 PDR ADOCK 05000289 P PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652
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I paarru W d o,, UNITEDpTATQS -
8 g NUCLEAR REGULA FORY COMMISSION E WASHINGT,0N, D. C. 20655
..... MAR 16 G83 Docket \ o. 50-289 MEMORANDUM FOR: Chairman Palladino
\CommissionerGilinsky Commissioner Ahearne Commissioner Roberts Commissioner Asselstine
\ G. Eisenhut, Director, Division of Licensing Darrell FROM:
\ /
/
SUBJECT:
BOARD NOTIFICATION (BN-83-218)
/
In accordance with the NR procedures for Board Notifications, the enclosed letter (R. Crouse (Toledo Ed{ son) to H. Denton (NRC)/ dated March 7,1983) is being provided to the Commission. The ASLAB is,being informed by copy of this notification. \ /
The letter forwards the B&W Reg latory Responsd Group report documenting its review and conclusions with respect to the eniergency feedwater (EFW) spray effectiveness and SBLOCA operating' procedure concerns previously identified in BN-83-21. The report concludes that:/1) the EFW spray is effective under SBLOCA conditions and adequate core c'aoling is provided, and 2) existing Utility operating procedures and operator training programs provide sufficient guidance to the operators to assure <the' safe mitigation of small breaks (isolatable and non-isolatable) in'the peimary system.
' \
The staff has completed its review of these\ concerns for TMI-l as reported in BN-83-21A. Reviews for the , remaining B&W plants are continuing.
/
/
2 a\k Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
\
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OGC l ED0 OPE SE ASLB for Mid d 50-329/330 (Bechoefer, Cowan, Harbour)
ASLAB for land 50-329/330 (Kohl, Buck, Moore)
ASLB for T -1 50-289 (Smith, Jordan, Little)
ASLAB for MI-l 50-289 (Edles, Buck, Gotchy, Kohl)
ASLB for Rancho Seco 50-312 (Cole, Shon)
ASLAB for Rancho Seco 50-312 (Rosenthal, Buck, Kohl) i
Contact:
J. Van Vliet, NRR X27380 1
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NUCLEAR REGULATORY COMMISSION wAsHsNOTON, D. C. 20655
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ORB #4 DISTRIBUTION FOR BOARD ~ NOTIFICATION NO.83-218 RE: B&W __RG rept. on EFW spray effectiveness & SBLOCA operating procedure concerns Docket File AE00 NRC PDR JThoma L PDR H0rnstein ORB #4 Rdg EBlakkwood ORB #4 Memo File TMI Site Pouch ORB #4 Board Notification File JGray HDenton JScinto-2 ECase MCutchin
( DEisenhut EChristenbury Glainas BSnyder JStolz Or. John H. Buck , ASLAP, EW-529 JVan Vliet Judge Reginald L. Gotchy, ASLAP, EW-529 t
l RIngram Christine N. Kohl, Esq. , " " "
MJambor -
Dr. Lawrence R. Quarles , " " "
JHard Judge Gary J. Edles , ASLAP, EW-529 Chairman, ASLAP, EW-529 ACRS-16 (nailing labels provided by OELD). Henr ukill e
RHartfield GPU Nuclear Corporation P. O. Box 480 OIE Middletown, Pennsylvania 17057 PPAS l
Williams ORB #4 THI-l Service List (Attached)
~
l
GPU Nuclear Corporation 50-289, TMI-l Mr. R. J. Toole Jordan D. Cunningham, Esq.
Manager,TMI-l Fox, Farr and Cunningham GPU Nuclear Corporation 2320 North 2nd Street P. O. Box 480 Harrisburg, Pennsylvania 17110 Middletown, Pennsylvania 17057 Ms. Louise Bradford TMIA Board of Directors 1011 Green Street P.A.N.E. Harrisburg, Pennsylvania 17102 P. O. Box 268 Middletown, Pennsylvania 17057 Ms. Marjorie M. Aamodt R. D. #5 Coatesville, Pennsylvania 19320
- Docketing and Servica Section Earl B. Hoffman U. S. Nuclear Regulatory Connission Dauphin County Consnissioner Washington, D. C. 20555 Dauphin County Courthouse Fmnt and Market Streets Chauncey Kepford Harrisburg, Pennsylvania 17101 Judith H. Johnsrud V.
Envimnmental Coalition on Nuclear Power Union of Concerned Scientists 433 Orlando Avenue c/o - Harmon & Weiss State College, Pennsylvania 16801 172C I Street, N. W.
Suite 506
J. B. Lieberman, Esq. Dupont Circle Building, Suite 1101 Ber16ck, Israel & Lieberman Washington, D. C. 20036 26 Broadway New York, New York 10004 f1r. Ronald C. Haynes, Regional Administrator U. S. N. R. C., Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
- Gary J. Edles, Chairman Atomic Safety & Licensing Appeal Board ANGRY /TMI PIRC U.S. Nuclear Regulatory Commission 1037 Maclay Street Washington, DC 20555 Harrisburg, Pennsylvania 17103
- Dr. John H. Buck Atomic Safety & Licensing Appeal Board John Levin, Esq. . U.S. Nuclear Regulatory Commission Pennsylvania Public Utilities Washington, DC 20555 Commission Box 3265 Harrisburg, Pennsylvania 17120
- -. _= _. ._-_- - --. ..- _
GPU Nuclear Corporation General C;unsel
. ~-
. Federal Emergency Management Agency Mr. Thomas Gerusky .
ATTN: Docket Clerk Bureau of Radiation Protection 1725 I Street, NW - '
Department of Environmental Resources Washington, DC 20472 P. O. Box 2063 Harrisburg, Pennsylvania 17120 Karin W. Carter Esq. ?
505 Executive House P. O. Box 2357 Harrisburg, Pennsylvania 17120 1
I G. F. Trowbridge, Esq. Dauphin County Office Emergency Shaw, Pittman, Potts & Trowbridg,e Preparedness 1800 M Street, N.W. Court House, Room 7 -
Washington, D. C. 20036 Front & Market Streets
- ' Harrisburg, Pennsylvania 17101
' Mr. E. G. Wallace Licensing Manager GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 William S. Jordan, III, Esq. Ms. Lennie Prough Harmon & Weiss 1725 I Street, NY Suite 506 U. S. fl. R. C. - Till Site Washington, DC 20006 P. O. Box 311 Middletown, Pennsylvania 17057 i
Ms. Virginia Southard, Chairman l
Citizens for a Safe Environment 264 Walton Street Lemoyne, Pennsylvania 17043 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division i Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. David D. Maxwell, Chairman - --
Board of Supervisors Londonderry Township .
RFD#1 - Geyers Church Road Middletown, Pennsylvania 17057 Mr. C. W. Smyth Supervisor of Licensing THI-l GPU Nuclear Corporation Regional Radiation Representative P. O. Box 480 EPA Reaton III Middletov:n, Pennsylvania 17057 Curtis Building (Sixth Floor) 6th and Walnut Streets
! Philadelphia, Pennsylvania 19106 Mr. Richard Conte '
Governor's Office of State Planning !
SeniorResidentInspector(TMI-1) and Development U.S.N.R.C. ATTN: Coordinator. Pennsylvania-P. 0. Box 311 State Clearinghouse Middletown, Pennsylvania 17057 P. O. Box 1323 t Harrisburg, Pennsylvania 17120
_ . _ ,. .__