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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:UTILITY TO NRC
MONTHYEARML20059H5351990-09-10010 September 1990
Forwards Encls 1-3 of Generic Ltr 90-07 Re Operator Licensing Exam Schedule
ML20059G0641990-08-31031 August 1990
Advises That Util Agreed to Revised Frequency of Once Every 12 Months for Corrective Actions Audits Per Tech Spec Change Request 65 Based on 900718 & 19 Discussions
ML20059F1691990-08-30030 August 1990
Requests Exemption from Requirements of 10CFR50,App J, Section III.D.1(a) for Facility Re Schedule Requirements for Connecting Type a Testing w/10-yr Inservice Insp Interval, Per 10CFR50.12(a)(2)
ML20064A4661990-08-30030 August 1990
Responds to 900803 SALP Rept 50-289/89-99.TMI Does Not Expect to Be Lead Plant for Installation of Advanced Control Sys.Maint Backlog Goals Established.Info on Emergency Preparedness & Engineering/Technical Support Encl
ML20059C8791990-08-29029 August 1990
Forwards TMI-1 Semiannual Effluent & Release Rept for Jan - June 1990, Including Executive Summary of Effluent Release Rept,Disposal & Effluent Release Data & Assessment of Radiation Doses.No Changes to ODCM for Reporting Period
ML20059D5491990-08-29029 August 1990
Responds to NRC Re Notice of Violation & Proposed Imposition of Civil Penalty Re Personnel Inattentiveness & Failure of Site Managers to Correct Condition.Shift & Immediate Supervisor Discharged
ML20059C7851990-08-27027 August 1990
Forwards Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility, Updating Minor Changes to Pages 6,8,9 & 13
ML20059C1091990-08-24024 August 1990
Forwards Rev 6 to Physical Security Contingency Plan.Rev Withheld
ML20059B8251990-08-24024 August 1990
Forwards Payment of Civil Penalty in Amount of $50,000,per NRC
ML20056B4651990-08-20020 August 1990
Corrects Statement Made in 900716 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Rosemount Transmitters. Identified That Only Half of Operating Crews Provided W/ Briefing on Bulletin
ML20058Q1851990-08-17017 August 1990
Requests That Distribution List for TMI-2 Correspondence Be Updated to Be Consistent W/Recently Implemented Organizational Changes.Ee Kintner,Mb Roche & Wj Marshall Should Be Deleted
ML20058Q1721990-08-13013 August 1990
Forwards TMI-2 Effluent & Offsite Dose Rept,First Quarter 1990, Update
ML20058Q1821990-08-13013 August 1990
Advises That Util Will No Longer Provide Annual Update to Dewatering Sys for Defueling Canisters Sys Description,Per NRC .W/Completion of Defueling & Shipment of All Defueling Canisters Offsite,Sys Has Been Deactivated
ML20058M7201990-08-0303 August 1990
Forwards Rev 2 to TER 3232-019, Div Technical Evaluation Rept for Processed Water Disposal Sys. Mods Include Elimination of Pelletizer & Relocation of Druming Station to Discharge of Blender/Dryer
ML20055J4581990-07-27027 July 1990
Responds to Violations Noted in Insp Rept 50-289/90-10. Corrective Actions:Missing Support Brace on Cable Tray Support Found & Corrected
ML20055J4561990-07-27027 July 1990
Advises That Info Contained in Generic Ltr 90-06,not Applicable to Current Nonoperating & Defueled Condition of Facility.Generic Ltr Will Be Reevaluated,If Decision Made to Restart Facility
ML20055H6901990-07-20020 July 1990
Forwards Rev 25 to TMI-2 Organization Plan for NRC Review & Approval.Rev Proposes Consolidation of Plant Operations & Maint Sections Into Plant Operation & Maint Section
ML20055G4431990-07-19019 July 1990
Forwards Rev 12 to 990-1745, TMI-1 Fire Hazards Analysis Rept & Update 9 to FSAR for TMI-1
ML20055G8781990-07-19019 July 1990
Discusses Compliance W/Reg Guide 1.97 Re Containment High Range Radiation Monitors,Per 900507-11 Insp.Physical Separation of Power Cables & Required Isolation Will Be Provided to Satisfy Reg Guide Category 1 Requirements
ML20055F9601990-07-11011 July 1990
Forwards, 1990 TMI Nuclear Station Annual Emergency Exercise Scenario to Be Conducted on 900912.W/o Encl
ML20044A9531990-07-0909 July 1990
Forwards Util Response to Weaknesses Identified in Maint Team Insp Rept 50-289/89-82.Corrective Actions:Engineering Personnel Reminded to Assure Documented Approval Obtained Prior to Proceeding W/Work
ML20055E0481990-07-0505 July 1990
Documents Action Taken by Util to Improve Heat Sink Protection Sys & Current Status of Sys.Main Feedwater Logic Circuits Modified Prior to Startup from 8R Outage to Eliminate Potential for Inadvertent Isolation
ML20055E0011990-07-0202 July 1990
Forwards Revs 1 & 2 to Topical Rept 067, TMI-1 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.5.4
ML20055C9971990-06-28028 June 1990
Forwards Rev 27 to Physical Security Plan.Rev Withheld
ML20055D2071990-06-28028 June 1990
Forwards Certification of TMI-1 Simulation Facility,Per 10CFR55.45.b.5.Resumes of Personnel Involved Encl. Resumes Withheld (Ref 10CFR2.790(a)(6))
ML20055D0861990-06-25025 June 1990
Documents Deviation from Requirements of Reg Guide 1.97,per Insp on 900507-11.Based on Most Limiting Analysis,Existing Range of 0-1,200 Psi Sufficient.Deviation Consistent W/B&W Owners Group Task Force Evaluation of Reg Guide
ML20043H4851990-06-18018 June 1990
Forwards Application for Amend to License DPR-50,consisting of Tech Spec Change Request 179
ML20043H4031990-06-18018 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements or Corrective Actions.
ML20043F9921990-06-11011 June 1990
Forwards Listing of Exam Ref Matl Sent on 900601 in Response to 900505 Ltr
ML20043F0661990-06-0404 June 1990
Forwards Inservice Insp Data Rept for Period 880816-900304. Owner Rept for Repairs or Replacements Performed on ASME Section XI Class 1 & 2 Components,Also Encl
ML20055C9041990-05-23023 May 1990
Advises That App a to Rept Is Set of Recommendations from Safety Advisory Board on Possible Research Opportunities
ML20043B2391990-05-18018 May 1990
Revises Commitments in Encl Met Ed 800430 Ltr Re QA of Diesel Generator Fuel Oil.Requirement for QC Review for Acceptability Prior to Filling Diesel Generator Fuel Oil Storage Tanks Deleted from Procedure
ML20043A5441990-05-16016 May 1990
Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project
ML20043A5311990-05-15015 May 1990
Responds to Violations Noted in Insp Rept 50-289/89-82. Corrective Actions:Periodic Insp Program Established Utilizing Checklist for Stored Equipment & Existing Tool Rooms Will Be Purged of Controlled or Unneeded Matls
ML20043A2321990-05-11011 May 1990
Forwards TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5) Technical Rept 069.Evaluations Conclude That Test & Insp Results Demonstrate TMI-1 Reactor Bldg post- Tensioning Sys in Good Condition
ML20042G2741990-05-0404 May 1990
Forwards Semiannual Update of Projects Listed in Categories A,B & C of long-range Planning Program Integrated Schedule
ML20012F2621990-04-0202 April 1990
Responds to Violation Noted in Insp Rept 50-289/89-26. Corrective Actions:Util Policy of Shift Supervisor Involvement in Bypassing & Resetting Safety Sys Expanded to Include Shutdown Conditions & Technicians Briefed
ML20012F2611990-04-0202 April 1990
Provides Supplemental Response to Station Blackout Rule. Target Reliability of 0.975 Chosen for Emergency Diesel Generators.Diesel Generator Reliability Program May Change Based on Final Resolution of Generic Issue B-56
ML20012F2731990-03-30030 March 1990
Confirms 900328 Conversations & Provides Technical Basis for Planned Actions to Correct Present Power Limitation Due to High Steam Generator Secondary Side Differential Pressure. Main Turbine Will Be Tripped from 80% Power
ML20042D8281990-03-23023 March 1990
Fulfills Requirements of Tech Spec Section 4.19.5.a Re once-through Steam Generator Tubes post-inservice Insp Rept for Unscheduled Outage 8U-1
ML20012D7001990-03-22022 March 1990
Forwards Util Response to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Site Mgt & Staff Hour Categories Added to Response
ML20012D7121990-03-21021 March 1990
Forwards Rev 0 to TMI-1 Cycle 8 Core Operating Limits Rept.
ML20012C4771990-03-12012 March 1990
Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f). Current Design Adequate W/O Addl Tech Specs
ML20012B8241990-03-12012 March 1990
Forwards Application for Tech Spec Change Request 199 to License DPR-50,revising Tech Specs Re Steam Generator Tube Insp Requirements
ML20055C3931990-02-23023 February 1990
Documents Interpretation of Tech Spec 4.19.5.a Re once- Through Steam Generator Tube post-inservice Insp Rept for Refueling Interval 8R.Total of Eight Tubes Removed from Svc by Plugging
ML20011F5251990-02-23023 February 1990
Documents Interpretation of Tech Spec 5.3.1.1 Re Design Features of Fuel Assemblies in Light of Issuance of Generic Ltr 90-02.Tech Spec Change Request Re Utilization of Dummy Fuel Rods or Open Water Channels Will Be Filed by 900420
ML20011F6651990-02-22022 February 1990
Forwards Updated Status Summary of Consideration of TMI-1 PRA Recommendations as of 891231.Changes to Torque Switch Settings for DH-V-4A & B Will Be Implemented in Refueling Outage 8 Re Closing Against High Differential Pressure
ML20006C2901990-01-26026 January 1990
Provides Addl Info Supporting Deferral of Seismic Qualification Util Group Walkdowns to 10R Outage.Performance of Walkdowns Provide Proper Scheduling & Priority for Resolution of USI A-46 for TMI-1
ML20011E1221990-01-26026 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Audit Rept Determined That Operation of Decay Heat Closed Cooling Water Sys Consistent W/Design Basis Documents
ML19354E8601990-01-25025 January 1990
Requests Approval for Use of B&W Steam Generator Plugs Mfg W/Alternate Matl (nickel-base Alloy/Alloy 600).Alloy 600 Has Superior Corrosion Resistance to Primary Water Stress Corrosion Cracking
1990-09-10
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s 6
- GPU Nuclear Corporation NggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 ,
717 944 7621 '
TELEX 84-2386 !
Writer's Direct Dial Nurnber:
June 26, 1986 5211-86-2111 Office of Nuclear Reactor Regulation Attn: John 0. Thoma, Project Manager PWR Project Directorate No. '
Division of PWR Licensir P U.S. Nuclear Regulator 3 nmission Washington, D.C. 20555
Dear Mr. Thoma:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Implementation of Generic Requirements Our letter of June 2,1986 described the level of effort required to properly respond to your request for THI-l status on the implementation of various Multi-Plant Actions (MPAs) which the NRC has been tracking internally. We stated that it would possibly require several manyears. However, after receipt of our letter, the immediacy of your need for the information was discussed with GPUN management. Based on that discussion, we committed to respond by June 27, 1986 with a reduced scope of our effort. Due to the time constraints, we have not been able to do a thorough search of our records or physically verify the documented actions to determine a status as accurately as is our normal policy for NRC submittals.
The attached markup of your list of generic requirements shows GPUN's estimated status' for each of the MPAs that we feel we can identify from the information you have provided. An additional column of comments has been added to your list. The purpose of'this column is to show the basis for the completion date selected.
In some cases we still do not have a clear identification of the MPA and additional clarification is needed. Our response is based on our best estimate of the action that was required when the MPA was initiated. Some of 1 the MPAs clearly have periodic update requirements. Some of the MPAs deal ;
with issues which have been the subject of on-going requests. Therefore, an i MPA shown to be complete does not reflect any additional required actions i which may relate to the same subject area. For active items, the dates which are given are not intended to revise any commitment date previously provided.
e607080206 e60626 9 ,
ADOCK 0500 PDR P [0 i
GPU Nu:: lear Corporation is a subsidiary of the General Public Utilities Corporation ,
9 5211-86-2111 June 26, 1986 If it appears that we have misinterpreted any of the MPAs or a more accurate status is desired, please inform us. If there are any questions, please contact Mr. C. W. Smyth of GPUNC at (717) 948-8551.
Sincerely, H. D. Hu ill Vice President & Director, TMI-1 HDH/MRK/spb cc: T. Murley J. Stolz R. Conte Attachment 0610A i
- 1
6 MASTER Q-1208738-008 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.s 49 FACILITY IMPLEMENTATION 03/31/8 FACILITY: THREE MILE ISLAND 1 '
PL ANT LDCATIDNs 10 MI SE OF MARRISBURG, PA LICENSED PONER: 2535 MNT PROJECT MANAGER: J. THOMA DOCKET NUM0fts 850-80289 DESIGN PONER: 0819 MNE BRANCH CHIEF: J. STOLZ ARCN/ ENGINEER: GIL NS$$ VENDOR: B&N LIC. ASSISTANis R. INGRAM IE INSPECTOR: R. CONTE LIC ACT DOCUMENTATTON OF COMPLETTON TITLE COMPLETE STATUS DATE TAC NO. MPA 8 05/07/8 0C COMPLETE 1979 TSCR 64, Letter CQL 1357 dated 10/26/79 M07057 A-01 10 CFR 50.55 A(G) - ISI APPENDIX I - ALARA 08/06/81C COMPLETE 1981 TSCR 34A, 01/19/81 N084 56 A-02 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PL ANS 02/23/79C COMPLETE 1978 Modified Amended Physical Security Plan, Rev. O, 02/01/78 M07489 M08710 A-04 APPENDIX J - CONTAINMENT LEAK TESTING 03/30/81C COMPLETE 1980 TSCR 22, Letter TLL-220, 05/13/80 (Amendment 63)
A-09 PRESSURE VESSEL BELTLINE MATERI AL SURVEILL ANCE 01/22/81C COMPLETE 1976 TSCR 40, Letter OQL 1273 dated 10/29/76 C11376
[19542 A-10 CONTINGENCY PLANNING 04/22/81C COMPLETE 1979 Safeguards Contingency Plan, Rev. O, 03/15/79 M19568 A-11 GUARD TRAINING PLANS 04/22/81C COMPLETE 1979 Guard Training & Qualification Plan, Rev. O, 03/15/79 03/04/82C COMPLETE 1930 Letter TLL 697, Security Plan, Rev. 8, 12/30/80 M19565 A-12 VITAL AREA ANALYSIS 10CFR 50.55 A(G) - INSERVICE TESTING 08/05/81C COMPLETE 03/1986 5211-86-2010, 03/03/86 (Am. 71 Open Items)
Z11287 A-14 04/11/80C COMPLETE 1980 TLL 196, dated 4/30/80 M12560 A-15 00ALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 04/12/82C COMPLETE 1981 Letter 5211-81-2230, 08/25/81 M47086 A-16 GUALIFICATIONS OF EXAMINATION. INSPECIION. TESTING A-17 INSTRUMENTATION TO FOLLON THE COURSE OF AN ACCIDEN 12/30/86 COMPLETE 06/1986 Letter 5211-86-2097, 06/05/86 M51361 04/30/86 COMPLETE 05/1986 TSCR 138, dated 05/12/86 P55750 A-18 TECM SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43)
M'S151 j A-20 10 CFR 50.62 OPERATING REACTOR REVIENS 12/31/88 ACTIVE Projected Completion 10/88 (Outage 7R) 04/30/86 COMPLETE 01/1986 Letter 5211-86-2007 B&W Topical Report 1895, 01/23/86
-- M59990 A-21 10 CFR 50.6 8, PRESSURIZED THERMAL SHOCK RUL E M86466 B-02 FIRE PROTECTION 09/19/78C No MPA Written Description Provided More Information Required 02/01/80C C0!!PLETE 1981 Letter TLL 637, 04/06/81 M08 '_0 3 B-03 PNR MODERATOR DILUTION 1978 TSCR 74, dated 03/13/78 M86704 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 06/15/80C COMPLETE 1930 TSCR 61B, dated 05/20/80 M88172 3-08 PNR NPSI-LPSI FLDH RESISTANCE 09/02/80C COMPLETE 1977 TSCR 43. Rev. 1, Letter GQL 0020 dated 01/07/77 M64707 B-12 STEAM GENERATOR TUBE INSPECTION 82/22/78C 00MPLETE
a a
MASTER Q-12sS731-901 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO. 4e FACILITY IMPLEMENYATION 03/31/3 THREE MILE ISLAND 1 (CONTINUATION)
TITit g STATUS DATE DOCUMENTATION OF COMPLETION D C.J L MPA 0 C18850 B-14 CEA GUIDE TUBE NEAR 07/24/8tC COMPLETE 1980 Topical Report BAW 1623, 06/X/80 Cl2147 B-16 EMERGENCY PL ANNING AND REVISIONS 01/26/81C No PFA Written Description Provided More Information Required C11286 B-17 TECM SPEC SURVEILL ANCE FOR NYDRAULIC $NUBBERS 09/30/84C COMPLETE 1984 TSCR 105, Rev. 1, dated 02/17/84 M07046 B-18 NORTNINGTON RNR PUMP SNAFT INTEGRITY 03/21/79C COMPLETE 1979 CPUNC Letter to NRC, 02/28/86 M10322 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 08/25/80C SEE MPA B-24 Ct 9584 3-21 LOSS OF 125-V DC SUS VOLTAGE MITN LOSS OF ANNUNCI A 02/28/82C N/A No Action Planned. No NRC Request Received M08604 B-22 TECM SPEC SURVEILLANCE REQUIREMENTS FOR MECMANICAL 01/01/70C N/A No Mechanical Snubbers (See B-17)
C10055 B-23 DEGRADED GRID VOLTAGE 01/01/70C COMPLETE 1982 Completion of Undervoltage Modification, 01/25/82 C19969 5-23 DEGRADED GRID V0LTAGE 07/29/81C COMPLETE 1982 Completion of Undervoltage Modification. 01/25/82 Kle205 B-24 VENTING AND PDRGING CONTAINMENTS NNILE AT FULL PON 08/25/80C SEE B-24 BELOW M42602 B-24 VENTING AND PURGING CONTAIMMENTS NMILE AT FULL PON 03/25/8 5C ACTIVE 04/1987 T Spe s comp ete 11 23 83 pe SCR 6 ev. 1 M19259 5-26 INADVERTANT SAFETY INJECTION DURING COOLDONN 09/14/79C No MPA Written Description Provided More Information Required C19533 3-35 DRIFICE ROD ASSEMBLY INTEGRITY - B8N 02/01/80C No MPA Written Description Provided More Information Required M08608 B-39 PNR PRESSURE - TEMPERATURE LIMIT TECM SPECS 10/26/79C Closed by NRC. No Action Required per Telecon with J. Thoma 06/26/86 E11236 B-41 FIRE PROTECTION - FINAL TECM SPECS (INCLUDES SER S 0 5/15/84C ACTIVE 04/1987 Complete Mods During Outage 6R M187*2 3-42 TMI FOLLON UP - ALL PL ANTS 04/01/80C COMPLETE --- MPA Too Broad to Assign a Specific Completion Date 012879 B-45 NASN 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C COMPLETE 1980 TLL 137, dated 03/31/80
~* E12601 3-46 ANALYSIS OF TURSINE DISC CRACKS 11/03/8tc COMPLETE 1980 TLL 299, dated 07/11/80 M12737 B-47 ECC$s CLAD SHELLING AND RUPTURE 04/24/81C No MPA Written Description Provided More Information Required M48 586 3-48 ADEGUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 05/13/82C SEE HPA B-23 Ab0VE M42127 B-57 DHR CAPABILITY 03/30/86 COMPLETE 04/1986 TSCR 142 and 5211-86-2065, dated 04/24/86 M42;19 5-59 MASONRY HALL DESIGN 08/08/83C COMPLETE 1983 5211-83-158, dated 06/23/83 M42513 3-60 ENVIRONMENTAL QUALIFICATION 04/21/8 5C 00MPLETE !!/1985 5211-85-2195, dated 11/26/85
MASTER REGULAT0RY INF0RMATION TRACKINO SYSTEM PAGE NO.s 4*
GH1204731-081 FACILITY IMPLEMENTATION 03/31/4 THREE MILE ISLAND 1 (CONTINUATION)
LIC ACT TITLE COMPLETE STATUS DATE DOCUMENTATION OF COMPLETION T AC No. MPA 3 M42710 B-61 LOSi 0F NON CLASS IE ISC P0HER 07/28/82C COMPLETE 1982 Completion of Modification ll/X/82 M42781 3-62 ESF RESET CONTROL DESIGN DEFICIFNCY 11/18/81C COMPLETE 1984 Completion of :fodification ll/X/84 M43921 8-63 INTERIM PROCEDURES FOR SHORT TERM BL ACKOUT 11/10/81C COMPLETE 1981 LIL-147, dated 06/24/81 M43262 3-64 BSC INDUCED FLUX ERRORS 04/30/82C COMPLETE 1981 LIL-273, dated 09/29/81 M47157 5-66 NATURAL CIRCUL ATION C00LDOHN 06/05/84C COMPLETE 07/1985 5211-85-2130, dated 07/24/85 M47551 3-67 THERMAL SNOCK 02/05/83C COMPLETE 1982 5211-82-132, dated 06/01/82 (150-day response)
M47026 B-67 THERMAL $ NOCK 01/15/82C COMPLETE 1981 LIL-316, dated 10/26/81 (90-day response)
M46]C4 B-69 IEB 88-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 07/21/82C COMPLETE 1980 TTL-228, dated 05/20/81 M46638 B-70 FATIOUE TRANSIENT LIMIT TS 05/25/82C No MPA Written Description Provided More Information Required M49764 B-72 NUREG 9737 TECH SPECS (GENERIC LETTER 82-16) 05/10/84C COMPLETE 1982 5211-82-263, dated 12/17/82 M49615 B-7 3 PL ANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 12/27/83C COMPLETE 1983 5211-83-063, dated 03/07/83 05/31/85C COMPLETE 1984 5211-83-330, dated 11/08/83, Procedures Revised (AP 1063)
M52898 B-76 ITEM 1.1 - POST TRIP REVIEHa PROGRAM DESCRIPTION &
M52889 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION 8 VENDOR INTER 11/30/86 ACTIVE 01/1989 5211-85-2160, dated 10/04/85 B-78 ITEMS 3.1.1 8 3.1.2 -POST MAINTENANCE TEST PROCEDU 10/24/85C ACTIVE 01/1990 Update Procedures Based on Vendor Manuals M52979 10/18/85C COMPLETE 1983 5211-83-330, dated 11/08/83 M53051 5-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 10/28/8 5C COMPLETE 1983 5211-83-330, dated 11/08/83 M53105 B-Se ITEM 4.1 - REACTOR TRIP SYSTEM RELI ABILITY - VENDO ITEMS 4.2.1 8 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/12/85C COMPLETE 1985 5211-85-2092, dated 06/24/85 M53158 3-81 M53200 5-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 07/12/84C COMPLETE 1984 Completion of Mod M55641 8-85 SALEM ATHS 1.2 DATA CAPABILITY 03/30/86 COMPLETE 1984 AP 1063 Revised M53724 5-86 SALEM ATHS 2.2 5-R COMPONENTS 12/30/87 ACTIVE 01/1989 vendor Manual Program per MPA B-77 SALEM ATHS 3.2.1 8 3.2.2 S-R COMPONENTS 10/28/85C COMPLETE 1983 5211-83-330, dated 11/08/83 Except Procedures per MPA B-78 M55407 B-87 98/82/85C 00!!PLETE 1983 5211-83-330, dated 11/08/83 M53898 B-88 SALEM ATMS 3.2.3 T.S. 5-R COMPONENTS M53945 3-89 SALEM ATHS 4.2.5 8 4.2.4 LIFE COMPONENTS 10/30/86 B&WOG Activity
HASTER REGULAT0RY INF0RMATION TRACKING $Y$ TEM PAGE NO.s 4' R-1208731-901 FACILITY IMPLEMENTATION 03/31/.
THREE MILE ISLAND 1 (CONTINUATION)
LIC ACT T AC 180. BO'A 0 TiitE COMPLETE STATUS DATE DOCU!!ENTATION OF COMPLETION M55542 S-90 ' SALEM ATHS 4.3 H AND B4H T.S. 09/15/84C COffPLETE 1984 TSCR 115, dated 06/01/84 M53959 S-91 SALEM ATHS 4.4 SSH TEST PROCLDURES 04/30/86 COMPLETE 1933 5211-83-330, dated 11/08/83 M54117 S-92 SALEM ATHS 4.5.1 41VCMSE TRIP FEATURES 10/28/85C COMPLETE 1984 1303-4.1 Revised M54034 3-93 SALEM ATHS 4.5.2 4 4.5.3 TEST ALTERNATIVES 04/30/87 COMPLETE 08/1985 5211-85-2135, dated 08/28/85 M86371 C-Si PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 02/20/80C COMPLETE 1979 TSCR 89, dated 10/11/79 M08709 C-03 GUALIFICATIONS OF RADIATION PROTECTION MANAGER 84/30/80C COMPLETE 1977 TSCR 58A, dated 10/06/77 8008613 C-04 FILTER TECN SPECS 06/05/80C COMPLETE 1975 TSCR 7A, dated 10/28/75 9008708 C-05 CONVERSION TO STA.lDARD TECH SPECS 01/20/82C COMPLETE 1983 5211-83-037, dated 02/09/83 M88590 C-06 PUMP SUPPORT-LAMELLAR TEARING 12/12/79C COMPLETE 1980 TLL-327, dated 07/09/80 COMPLETE 1979 CQL 0460, dated 05/08/79 M88615 C-07 FUEL HANDLING ACCIDENT INSIDE CONT AINMENT fgl2/ 31/79C M88086 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL 12/01/8tC CANCELLED BY NRC PER TELECON WITH J. THOMA M4Fl31 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL J. 01/11/85C COMPLETE 02/1986 Completion of Mod C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 08/ll/83C COMPLETE 1984 Letter - Denton to Weiss 09/26/64 (2.206 response)
M43454 C-15 CONTROL OF HEAVY LOADS - PHASE II (FDLLONUP OF MPA 06/28/85C CANCELLED BY NRC IN CL 85-11, DATED 06/28/85 M52279 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/08/86C COMPLETE 03/1986 IEB 85-02 Revised AP-1030, 03/20/86 (AI 85-9175)
M58096
- 406103 0-08 DEFICIENCY IN CHEM ADDITION TO CONT AINMENT SPRAYS 84/02/80C COMPLETE 1983 TSCR 107, Rev. 1, dated 01/05/83 9008603 9-10 ASYMMETRIC LOCA LOADS- 03/27/84C ACTIVE Projected Completion 04/87
~
M10109 D-11 FISSIOtt GAS RELEASE 05/16/80C No MPA Written Description Provided More Information Required M68012 D-13 B4H SMALL BREAK ERROR 03/16/79C COMPLETE 1981 Completion of Hod 90084"1 3-14 REACTOR VESSEL HELD - HIRE DEFICIENCY 10/26/79C COMPLETE 1979 Topical Report BAW 1556, 08/X/79 M12327 D-15 HIGH ENERGY LINE BREAK 8 CONSEQUENTIAL SYSTEM FAIL 01/01/70C COMPLETE 1982 Letter 5211-82-170, dated 07/21/82 D-87 DEFINITION OF OPERA 0LE 08/07/84C (X)MPLETE 1984 TSCR 139. Rev. 1, dated 05/11/84 M43043 M51733 D-18 NUREG 0630 CL ADDING MODELS (08N PL ANTS) 10/28/83C COMPLETE 1983 TSCR 127, dated 06/20/83
l 1
MASTER Q-1208731-001 REOULAT0RY INF0RMATION 7 RACKING SYSTEM PAGE NO.s 4*
FACILITY IMPLEMENTATION 8 3/ g g i, TNAEE MILE ISLAND l (CONTINUATION)
LIC ACT TAC Mo. MPA 0 TITLE COMPLETE STATUS DATE DOCUMENTATION OF COMPLETION M55982 D-19 DIESEL GENERATOR RELIABILITY TECM SPECS (GL 84-15) 10/11/85C COMPLETE 1984 5211-84-2242, dated 10/17/84 M46545 E-Gl SPENT FUEL POOL EXPANSIONS 12/19/77C COMPLETE 1977 TSCR 47, dated 02/03/77 MS6195 E-02 FUEL CASK DROP 09/15/81C COMPLETE 03/1985 TSCR 38. Rev. 1, dated 03/05/85 M08611 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 03/16/79C No Written MPA Description Provided More Information Required M48283 F-05 I.C.t.2/3.0 PROCEDURES GENERATION PACKAGES (NUREG 03/28/84C ACTIVE 09/1986 Respond to Questions 12 & 13 of NRC SER M47257 F-86 !.C.5 FEEDSACK OF OPERATING EXPERIENCE 02/01/82C COMPLETE 1980 Procedure Implemented 12/X/80 M47329 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI Ol/01/82C- COMPLETE 1983 IR 82-16, dated 10/05/82 & IR 83-02, dated 03/10/83 M51218 F-08 I.D.t.1 DETAILED CONTROL ROOM DESIGN REVIEN PROGRA 04/08/85C 00MPLETE 02/1985 5211-85-2026, dated 02/14/85 M51299 F-89 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 12/23/85C ACTIVE 04/1987 Incorporate RG 1.97 Mods into SPDS During Outage 6R-M44;tt F-10 11.0.1 RCS NIGN POINT VENTS 10/17/83C COMPLETE 1984 Completion of Modifications. 01/30/84 M47980 F-11 II.B.2 PLANT SNIELDING 03/28/83C COMPLETE 1984 5211-84-2179, dated 07/27/84 M48284 F-12 II.G.3 POST ACCIDENT SAMPLING 03/22/84C COMPLETE 1984 Completion of Mod M44624 F-14 I I . D .1 RV AND SV TRAINING 08/22/84C COMPLETE 1984 5211-84-2073, dated 03/20/84 M41790 F-16 II.E.9.2.1 AFH SYSTEM INITIATION 09/27/82C ACTIVE 04/1987 Complete HSPS Mods During Outage 6R M44756 F-17 II.E.l.2.2 AFH SYSTEM FLON INDICATION 04/02/81C COMPLETE 1984 TR 84-01, dated 04/09/84 M475tl F-23 II.F.t.4 CONTAINMENT PRES $URE INSTRUMENT 04/20/44C 00MPLETE 1983 5211-83-323, dated 11/28/83 M47712 F-24 II.F.l.5 CONTAINMENT HATER LEVEL INSTRUMENT 84/20/84C COMPLETE 1984 5211-84-2043, dated 03/01/84 M47783 F-25 II.F.1.6 CONTAINMENT NYDROGEN MONITOR 84/20/84C COMPLETE 1983 5211-83-323, dated 11/28/83 M47048 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEGUATE 01/31/87 ACTIVE Projected Completion 11/86 M48285 F-27 II.K.2.9 FMEA ON ICS 08/02/82C COMPLETE 1982 5211-82-145, dated 06/11/82 M54973 F-30 II.K.2.13 THERMAL-MECMANICAL REPORT 06/05/84C 00MPLETE 1980 RAW-1648 M45240 F-31 II.K.2.14 LIFT FREQUENCY OF PORVS AND SVS 04/22/81C COMPLETE 1982 TSCR 103 Rev. 2, dated 05/20/82 M45274 F-56 II . K . 3.1 A6TO PORV ISOLATION 03/ 05/84C Not Required per HPA F-37
_~ _. _ - . _ _ .
=
MASTER REGULAT0RY INF0RMATION TRACKINO $Y$ TEM PAGE NO. 40 R-1288731-801 FAC1LITY IMPLEMENTATION 03/31/8 THREE MILE ISLAND 1 (CONTINUATION)
LIC ACT r TITLE EDMPLETE STATUS DATE DOCUMENTATION OF COMPLETION TAC MD. frA B M 5328 F-37 II.K.3.2 REP 0tf ON PORV FAILURES 95/05/84C COMPLETE 1981 LIL-102, dated 04/06/81 M8216 F-39 II.K.3.5 AUTO TRIP OF RCPS 83/te/83C SEE MPA C-01 M 5671 F-47 II.K.3.17 ECCS OUTA0ES 82/24/82C COMPLETE 1981 5211-81-2243, dated 09/04/81 M8246 F-57 II.K.3.38 58 LOCA METHODS 87/12/85C COMPLETE 01/1985 Letter B&WOG IST Code Verification Plans. 01/03/85 M48288 F-54 II.K.3.31 COMPLIANCE WITN to CFR 50.46 03/34/87 ACTIVE Projected Completion 09/86 M 5987 F-63 III.A.S.2 TECHNICAL SUPPORT CENTER 89/30/86 COMPLETE 1983 5211-83-2336, dated 11/15/83 M46058 F-64 III.A.1.2 OPERATIONAL' SUPPORT CENTER 89/30/86 COMPLETE 1933 5211-83-2118, dated 04/15/83 M6150 F-65 III.A.I.2 EMERGENCY OPERATIONS FACILITY 09/3e/86 COMPLETE 1933 5211-83-2336, dated 11/15/83 M46202 F-66 III.A.1.2 NUCLEAR SATA LINK 12/te/80C NRC Requirement Never Approved M6274 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 83/e9/84C COMPLETE 1980 TLL-700, dated 12/31/80 M8247 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 09/38/86 COMPLETE 1983 5211-83-2118, dated 04/15/83
< M7849 F-70 III.D.3.4 CONTROL ROOM MABITABILITY 08/22/84C ACTIVE 04/1987 Install Mods During Outage 6R M56174 F-78 I.D.1.2 DETAILED CONTROL ROOM REVIEN (FOLLONUP 10 04/08/85C SEE MPA F-08 M49698 G-01 REACTOR COOL ANT PUMP TRIP (D660 - II.K.3.5) 05/28/86 ACTIVE 07/1986 Schedule for Response to NRC CL 86-05, dated 05/29/86 Being Developed
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