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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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Text
- .- . , t.Metropolitan Edison Company e Post Office Box 480
-Middletown, Pennsylvania 17057 717 9444041 Wnter's Direct Dial Number November 8, 1979
, GQL 1400 D1I Support Attn: Richard Vollmer, Director U. S. Nuclear Regulatory Co= mission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (DII-1)
License No. DPR-50 Docket No. 50-289 U!I Restart Questions Enclosed please find 10 copies of the response to your letter of October 31, 1979 concerning improvements in management control of operational activities. The following information will be included in the next amendment to the "TMI-l Restart Report".
Sincerely,',. _ .J. G. Herbein Vice President-Nuclear Operations JGH:LWH:rt Enclosures cc: J. T. Collins H. Silver R. Reid 1323 339&O/N 9 \%7911130 8 Metropol. tan Ecson Company is a Member of the General Pubhc UtSt:es System
...QUESTION: In format ion Required for the TMI-l Restart Review The staf f review of your operat ional act ivit ies for the Three Mile Island Nuclear Station prior to and including the TMI-2 accident indicates a significant number of pot ent ial non-compli ance items that place in quest ion the adequacy of your management controls.
The se potential non-compliance items can be generally categorized as failure to adhere to Technical Specificat ion requirements, failure to meet certain NRC Regulations, and failure to follow established procedures.
Specific examples of such items are found in Appendices I-B and II-F of NUREG-0600.*
In view of the above, describe the specific measures you have taken, or plan to take, to cemanstrate that the Met r opolitan Edison Campany has established a clear commit-ment to operational safety through significant improvements in the management cont rol of operat ional act ivit ies.
Measures to be described should include, but not be limited to: 1.Organizational changes to improve management controls.
2.upgrading of management and technical qualifications.
3.Changes to review and approve provisions for plant and emergency procedures .
4.Improvements in the review and audit programs for plant activities.
5.Independent verifications of operat ional act ivit ies af fect ing safety.
6.Establishment of and/or revisions to training programs for all levels of management and technical personnel involved with operation of the TMI NS.
7.Greater involvement of corporate management and staff in operational act ivit ies.
8.Upgrading of the operational quality assurance program.
- Invest igation into the March 28, 1979 Three Mile Accident by Of fice of Inspect ion and Enforcement .
1323 340.9
- ..Following the TMI-2 accident, Metropolitan Edison Company recognized through its own and other investigations of the accident that major organiza-tional changes were desirable for more ef fective management control.
These changes indicate Met-Ed's commitment to operational safety and provide signi-ficant improvement in the control of operational activities, and the technical and management resources directing and supporting facility operations.
The first step taken was to ccmbine the technical and mana;ement resources of Met-Ed and GPU Service Corporation Generation Divisions into a single organizational entity identified as the TMI Generation Group.
The TMI Generation Group was formed on July 30, 1979, to strengthen the overall canagement and provide greatly increased technical resources for the restart of TMI Unit 1 and the recovery of TMI Unit 2.
The Group is headed by R. C. Arnold. To effect this new organization, Mr. Arnold was elected to the positiva of Senior Vice President of Met-Ed, and he continues to serve as a Vice President of GPU Service Corporation.
In this position, Mr. Arnold reports to He rman M. Dieckamp, President of GPU and GPUSC, and acting president of Met-Ed.
This reporting structure provides a direct link from the Chief Operating Officer of these three companies to the activities at TMI.
A primary objective of the TMI Generation Group is to insure that NRC Regulations, Technical Specifications and established procedures are adhered to.
As head of the TMI Generation Group, Mr. Arnold directly supervises the following functional groups.
THE MET-ED NUCLEAR OPERATIONS The head of this group, Mr. J. G. Herbein, Vice President - Nuclear Operations (Plant Manager) is serving full time at TMI and his responsibilities and functions are described in Section 5.2.1.
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..-2-Formerly, Mr. Herbein held the position of Vice President - Generation, Met-Ed, where he had the responsibility for directing the engineering, operations and maintenance of Met-Ed's fossil fuel and nuclear power plants.
The organization formed under Mr. Herbein's direction specifically gives the Unit 1 Superintendent only the responsibility for operation and maintenance and relieves him of direction of administration, training, engineering, radiation protection and chemistry functions.
TECHNICAL FUNCTIONS The Technical Functions Group, directed by Mr. R. F. b'ilson, provides off-site technical support to TMI operations.
This includes engineering and design support for Unit 1 equipment modifications, systems engineering and safety analysis.
The Engineering and Design Department of the Group is organized into
.the following sections:
Electrical Power and Instrumentation Mechanical System Engineering Engineering Mechanics Mechanical Components Engineering The System Engineering Department is organized into the following sections:-Control and Safety Analysis Process Computer Nuclear Analysis and Fuels
, Plant Analysis 1323 342..p---%-..._g-.. - - - -
.-3-The Plant Analysis section has been specifically established to focus or.
systematic review of the performance of plant systems and to provide corporate direction of site engineers who will be monitoring, independent of operation personnel, plant performance en a daily basis.
A TMI Engineering Management section has also been established in the Technical Functions Group to provide direct liaison and coordination between corporate engineering support and the plant engineering activities.
In addition, a very experienced engineer, formerly in a supervisory position, has been assigned on a full time basis as Chairman of the Generation Review Committee to direct independent technical review of site modifications, procedute changes and plant experiences relating to nuclear safety.
MAINTENANCE The Director-Maintenance, Mr. J. L. C. Bachofer, Jr., is heading the on-site maintenance organization which has the responsibility to support TMI Unit 1 in the areas of Corrective Maintenance, Emergency Maintenance,>Sintenance Procedures and Methods, Tools and Equipment, and Machinery His to ry.
Additionally, Mr. Bachofer is providing assistance to IMI Unit 1 in the construction of plant modifications, controls estimating / cost engineering, craft labor relations, and the coordination of transportation requirements.
ENVIRONMENT. HEALTH AND SAFETY The Director - Environment, Health and Safety, Mr. J. R. Thorpe, provides both on-site and off-site support to TMI Unit 1 in the functional areas of Nuclear Licensing, Environmental Engineering, and Environmental Impact Assessment.
RELIABILITY ENGINEERING Thn Reliability Engineering Group, directed by Dr. R. L. Long, provides off-site and on-site Quality Assurance and System Laboratory support to the
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..-4-TMI Unit 1 operations. The Quality Assurance Department provides technical assistance to TMI Unit 1 in Methods and Operations, Materials Technology, Auditing, Design Assurance, Manufacturing Assurance as well as conducting appropriate quality control activities. The System Laboratory provides technical assistance to TMI Unit 1 in Environmental and Operational Chemistry and Chemistry.
T'4E TMI-2 RECOVERY ORGANIZATION The Acting Director, TMI-2 Recovery, Mr. R.
F. Wilson, provides overall management and direction ror activities associated with the restoration of TMI-2 to operation. This orgaaization will have an independent dedicated on-site staff necessary to conduct clean-up activities.
These changes have structured the organization so that substantially
-greater management resources are focused directly on TMI activities to insure adequate control of safety related activities. The current organi:ation includes about 250 professional people with an average experience of about 13 years, composed with the approximately 75 professionals contained in the Met-Ed organization prior to the accident.
To provide necessary involvement of corporate management and staff in operational activities, all the previously described groups have significant portions of their staffs located full time at TMI.These changes, as well as improvements made in training, shif t staffing, organizational status and staffing of the health physics departments of the two units, and strengthened administrative controls, are substantive and clear indications of Met-Ed's commitment to insure the safe operation of TMI-1.
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.-5-The upgrading of the Operational Quality Assurance Program is discussed in Section 5.4, page 5-32 to 5-38 and Figure 5.4-1 and 5.4-2 of the TMI-1 Restart Report (Amendment 4).
Major improvements have been made in the audit function with the establishment of an on-site QA Audit staff to better coordinate and manage audit activities and provide management with increased awareness of the adequacy and implementation of the QA Program.
The following actions are being taken:
A.Current auditing procedures are being revised to better define responsibilities, provide simplified audit reporting and better follow-up of problem areas.
B.Surveillance and audit scheduling practices / procedures are being upgraded to provide an improved approach to coverage of activities affecting safety.
C.Corrective action procedures for QA Audits are being put in place to provide guidance so that correct 1ve actions result in measures which preclude recurrence.
D.A computerized audit status system is being established to provide better management visibility of problem areas and to determine trends.
E.A conserted effort to establish priorities of audit findings
'and to commit the appropriate level of management, via the post audit conference, is being put in place to provide corrective cetions that insure the commitment of sufficient resources.
Independent verification of operational activities effecting safety are being assured by the following specific procedur-1 requirements. These
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..-6-requirements essentially provide a check and cross check system which provides the assurance that SFAS and EFW Systems will perform in accordance with established requirements whenever challenged.
These procedural requirements are outlined below:
A.At each operations shift relief control r om turnover, SFAS and EFW checklists that have been completed by the of f going watch during shift are signed by both the on coming and off going control room operators.
Completion of these SFAS and EFW checklists, which indicate both required and actual control room valve and switch position indications insures that all control room indications have been double checked to verify that SFAS and EFW Systems are in their ready to actuate status.
To verify in plant SFAS and EFW System valve positions, formal log sheets, indicating both required and as found SFAS and EFW valve positions will be completed by primary, secoadary and out building auxiliary operators.
SFAS and EFW valve positions in major SFAS and EFW System flow paths, which do not have control room position indication, will be verified and recorded on the log sheets either once a shift or once a day, depending on ease of accessibility and existing plant radiation levels.
Separate system status checklist requirements are also completed by the control room watch, primary' plant, secondary plant and out building auxili.ry operators during their i i32L3 346
.-7-shift. These system status checklists are also reviewed and signed at shift turnover by the on coming and of f going auxiliary operators and control room watch.
B.At the completion of maintenance on SFAS and EFW Systems on independent system checklist is required to return the system maintained to full operational status.
This checklist will encompass a specific system valve and breaker lineup within the boundaries in which maintenance was conducted. Additionally this checklist will require two independen* review and signature verifications for correctness prior to its sse in aligning the system in the field.
Following this dual verification, the checklist will then be used in the field to return the system to full operational status.
C.Following survcillance tests or special operations ca SFAS and EFW Systems, two independent valve and breaker lineups will be conducted within the boundary of the system affected by the tests or special operations to provide assurance .Nat
-the system is returned to full operational status.
D.Surveillance testing and the required testing following maintenance on instrumentation associated with SFAS, EFW, Reactor Protection System (RPS), and Radiation Monitoring System (RMS) instrumentation, will be accomplished according to procedural requirements which will require the technician performing the instrumentation test steps to initial each procedure step as it is accomplished.
Fellowing the completion
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..-8-and sign of f of the Surveillance test by the technician, a supervisor will review the completed procedure to verify all steps have been initialed, and that data is appropriately recorded and is within the required procedure authorized limits.Folicwing this review the supervisor will also sign the completed procedure and related data sheets.
Signed data sheets and initialed procedures will be retained.
Changes to review and approval provisions for plant and emergency procedures have been improved by the assignment,as mentioned previously, of a full time Generation Review Committee (CRC) Chairman who has extensive utility engineering experience, a degree in Electrical Engineering and was formerly a member of the Oyster Creek GOR 3.
The full time GRC Chairman will be responsible for executing review activities related to safety evaluations, procedure changes and violations of regulations.
The function, composition, qualifica-tions, quorum and meeting frequency of the GRC will be specified in a proposed change to the Unit 1 Technical Specifications.
In summary, the GRC will be composed of at least five memSers.
Each will have an academic degree in Engineering or Physical Science with tive years of technical experience.
In view of the significant increase in both numbers of assigned professional personnel and years of experience the Generation Review Committee will have a strong technical base to provide in-depth support to insure that its functions are adequately executed.
In addition to the previously required Plant Operation Review Committee (PORC) review and Unit Superintendent approval required for nuclear safety related procedures, the Radiation Protection and Chemistry St pervisor or
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..._9_another individual knowledgeable in Radiological Controls will attend all PORC meetings where Radiological Control procedures and practices are reviewed.
Following the TMI-2 accident, an experienced consultant who formerly held the position of Branch Chief of NRC Operator Licensing, conducted a review of operating and emergency procedures as well as plant training practi<es.
As a result of this review, several signifi' ant recommendations were-incorporated into the plant emergency procedures. These included an " objectives section" for each emergency procedure outlining in a clear, concise sum =ary, the overall intent, goal, and directional thrust intended by the execution of the emergency procedure and its followup action.
Additionally, as a result of this review, emergency procedure follow-up actions will reverify importart plant parameters utilized to categorize plant symptoms and initiate immediate action. These key parameters will be verifiec a second time in the followup action utilizing, where possible, an alternate means of readout or indication.
This will minimize the potential for misreading instruments and will provide a check on the accuracy of instruments read initially when evaluating e=ergency symptoms and executing the immediate ac: ion steps of emergency procedures.
This effort has resulted in the emergency procedures being revised to provide a sharply focused emphasis on maintenance of adequate core cooling at all times.
As a part of our review, key emergency procedures were used by shift crews at the B&W Lynchburg Simulator. Where required, procedure changes were
~initiated to insure technical accuracy, clarity and consistence with actual plant simulator response. Additionally, guidelines from B&W have been incorporated in the emergency procedures relative to e 2ii break LOCA, natural circulation, inadequate core cooling, prevention of void formation, and the
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..-10-high and low pressure injection modes of core cooling.
Finally, the follow-up section of the emergency procedures has been expanded to include specific long term actions wherever appropriate.
Additional emphasis is beinr, given to the area of training.
The positica of Manager of Training aas established, reporti,ng directly to the Vice President-Nuclear Operations with the responsibility to organize, develop and conduct training programs to meet the training requirements of the TMI Nuclear Station Unit 1.
To assist the Manager of Training, a Supervisor of
__Operator Training and a Supervisor of Technical Trsining have been assigned to implement the operator and technician training pro, rams.
Major emphasis has been placed on the establishment of a Management Training Program developed for management positions in the TMI-l organization.
The course content will include:
A.Technical Specifications, Section 6.0 B.Kemeny Commission Report C.Operational Quality Assurance Plan D.TMI Emergency Plan E.Health Physics F.Decay heat removal and heat t ansfer mechanisms including core decay heat generation G.Safety Analysis Other training programs are outlined in Appendix I to this letter.
The above managerial and operational changes reflect our ongoing commitment to operational safety and awareness of the need to give clear visibility to that commitment. Safety will remain the chief concern of the
.I 1323 ,50l: i a
..-11-TML Generation Group.
T?e recommendations of the President's Commission on the Accident at Three Mile Island are being reviewed, as will be the fs.thcoming recc=mendations of the NRC/IMI Special Inquiry Group and other investigatory agencies, to assure the Company is appr3priately responsive to all recorr.nendations which relate to nuclear safety.
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....APPENDIX I
_A.Operator Training 1.Operator Accelerated Training Program This program was established to train the operators to meet the restart requirements of TMI Unit 1.
The OARP will be reviewed by a coc=ittee from the Nuclear Engineering Department,._Penn State University to:
_a.Insure Technical and teaching quality b.Monitor and evaluate the program c.Critique the program goals and objectives in ecmparison to current practices, NRC Guideliges and the TyI-II cycnt.
2.Operator Replacement Training This program will be revised, as necessary, to incorporate the selected objectives of the Operator Accelerated Retraining Program.
3.Operator Requalification Program This program will be revised, cs necessary to meet the reaualifica-tion standards set by the Nuclear Regulatory Commission.
4.Requalification of Operators in Radiological Controls This program has been revised to better qualify the opera or with respect to his responsibility in radiation protection.
5.Auxiliary Operator Training Auxiliary Operator Training vill be expanded in the following areas:
.Heat tranafer
-- ~ ~ ~ ~ ~ ~ ~ ~
~~a.b.Mechanical system and components
~~c.Electrical systems and components
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o eMew-_e-O e4 m e e ep.,, , ,, ,,m,m,_,
..-._-2--B.Radiation / Chemistry Technicians 1.Initial Radiation / Chemistry Technician Training This program will be revised to increase the scope and quality of training.2.Radiation /Chemistr Technician Requalification
.Th!s program will be improved to insure the qualifications of the technicians are maintained at an acceptable level.
_C.Maintenance Personnel Training This two year recurring training program has been established.
Maintenance Personnel will be trained in four phases, each of six months duration as follows:
=, 4-a.Maintenance Fundamentals b.Plant Systems Training c.Skills Specialty Training d.Practical Application Training In addition, a special lesson is being given to indoctrinate maintenance personnel in the TMI-II transient. The lesson will also stress the ALARA concept.D.Emergency Plan Training 1.Emergency Plan Training
-This program will train all personnel designated in the revised Emergency Plan and the Emergency Plan Implementation procedures.
~~.- - . . - .. . -_ .- ..2.ECS Coordinator Training This program was established to train the coordinator in his
..specific responsibilities during the various emergency levels s3: f.::1. n tha Tian.
.--1323 353 AM1Q.,~ _ _. _ ._.
_ _ . _ _ _ _ _ . =
.......-3-E.Technical Training for Shift Technical Advisors This program has been established to train assigned personnel in their assigned accident and operating experience assessment functions.
F.General E=ployee Training The General Employee Training Program has been revised to reflect
.revisions in:
A.Security.B.Site Emergency Plan C.Quality Assurance e r<J323 354.i.-em-.-- - - . . - . - .
.@q 4...