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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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GPU Nuclear Corporation 3 Nuclear ;;;,omg -
'Middletown, Pennsylva'nla 17057 o191 717 944 7621 l
, ' TELEX 84 2386 Writer's DI. rect Dial Number:
November 9, 1987
-5211-87-2185 k
U.S. Nuclear Regulatory Commission .I Attn: Document Control Desk Washington, DC 20555 i
Dear Sir:
l Three Mile Island Nuclear' Station, Unit 1 (TMI-l)
Operating License No. DPR-50 Docket No. 50-289 ,
Systematic Assessment of Licensee Performance (SALP) )
References:
(1) T.E. Murley letter to H. D. Hukill, Systematic Assessment of Licensee Performance (SALP); Report No. 50-289/86-99, dated January 5,1987.
(2) GPUN letter, P. R. Clark to T. E. Murley, Response to SALP Report 86-99, dated April 1,1987.
The purpose of this letter is to provide the status of corrective actions taken as a result of the SALP Board's recommendations that were provided in Reference 1. Reference 2 contained the GPUN TMI-1 response to Reference 1. ,
In addition, we would also like to take this opportunity to provide j information on other actions taken and our performance over the last year !
which may be useful to the SALP Board in their next assessment of Three Mile Island Unit 1 (TMI-1).
Attachment 1 provides details on the corrective actions taken as the result of the last SALP Report (Ref.1).
Attachment 2 discusses some of the other related GPUN activities taken and our performance over the past year. !
Sincerely, 8711170220 871109 R
ADOCK0500g9 ((, p P. R. Clark President PRC/DVH/spb:1001 A !
Attachments cc: W. Russell G. Edison [g R. Conte >
- l. g GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
Docket No. 50-289 !
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r-L ATTACHMENT 1 GPU NUCLEAR THREE MILE ISLAND - UNIT 1 UPDATE-TO SALP REPORT NO. 86-99 RECOMMENDATIONS i;
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November, 1987
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FUNCTIONAL' AREA: Technical Support BOARD RECOMMENDATION:
Undertake a self-analysis to determine the causes for inconsistent performance in this area. ;
STATUS: !
In July 1987, GPUN initiated a program to perform a scif assessment in the technical support area looking for.both areas of strength and weakness and any supportive information leading to inconsistencies in performance. The scope '
of the assessment includes the total technical support organization, i principally the plant engineering functions within the GPUN Plant Divisions and the Technical Functions Division. This self assessment is looking at both strengths and weaknesses of these organizations and the manner in which the organizations interact with the plant operation and maintenance functions.
The objectives of the self assessment are to factually establish areas of inconsistent performance, if any, and to provide a basis for management focus on any of the weaker performance areas. This program was reviewed with the TMI-1 Senior NRC Inspector and Region I Manager on July 2,1987. Phase I of the program, which includes development of the approach and the initial data collection / preliminary evaluation, is about conplete. Phase II, consisting of screening the initial results, looking for areas of further analysis, conclusions and development of a corrective action plan, has been initiated.
It is anticipated Phase II will be completed in 1987. Phase III and IV will be continued into 1988.
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FUNCTIONAL AREA: Assurance of Quality j BOARD RECOMMENDATION:
i (1 ) Continue efforts in correcting p'rocedure adherence and procedure adequacy ,
proolems.
(2) Independently meet with the NRC to discuss the revised safety review process and corrective actions of the Procedure Compliance Task Group.
STATUS:
(1 ) Management maintains strong emphasis on procedural adherence and adequacy. Initiatives have been made to strengthen this area and make continued improvement. The Quality Assurance Department continues to monitor and address procedure compliance. Item 2B below addresses actions from the Procedure Compliance Task Group (PCTG). This item continues to have management attention to bring the number of compliance problems down. We believe the long term implementation of the PCTG recommendation will improve our procedure compliance. We will continue to follow and monitor this item.
(2) A. On February 12, 1987 GPUN management met with Region I management at the Region I office to discuss the revised GPUN technical and safety review program. Tnis meeting resulted in three commitments by GPUN.
These commitments as identified in Inspection Report 87-04 were:
- 1) The licensee's Technical and Safety (T&S) review process will be revised to assure an explanation of negative answers to the questions on this initial screening process delineated by first form of licensee's two-step process.
- 2) The licensee will continue to evaluate the effectiveness of procedure changes using the new T&S review process.
- 3) More guidance was to be issued by the licensee, especially in the area of what constitutes a " licensing basis document."
The status of these three items is:
- 1) GPUN corporate procedure 5000-ADM-1291.02, Rev. 3 was issued August 25, 1987 which incorporates the requirement to explain 4 negative answers on the first form. I
- 2) GPUN has reviewed the effectiveness of the technical and safety review process. Our reviews to date indicate that the procedure is meeting the intended purpose. However, we have taken actions to enhance the quality of safety reviews. These actions include a revision of the Corporate Procedure to require explicit statements for negative responses on the Safety Determination form and development of guidance with respect to definition of ,
Licensing Basis Documents, j 1-2 l
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- 3) -Extensive discussions on what constitutes a " licensing basis documelit" have taken place. Thi:3 includes in-house, with the 4 industry, and legal counsel. The GPUN position is essentially _i' established and is in final review. The schedule to disseminate this' guidance to the reviewers is within 30 days.
(2) B. At the same February 12,'1987 meeting, GPUN summarized the. results of '
the Procedure Compliance Task Group effort and reported the status-of implementing the group's recommendations. The current status of the recommendations is that six of the seven short term recommendations i have been completed. The remaining item is being worked on and wi'll be completed in 1988.
Of the seven long term recommendations, one has been completed. The remaining six are actively being pursued. Several of the six should be completed by the end of 1987 with the others completed in 1988.
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Docket No. 50-289 I
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ATTACHMENT 2 .
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-t GPU NUCLEAR l THREE MILE ISLAND - UNIT 1 EXAMPLES OF GPUN/TMI-1 ACTIONS AND PERFORMANCE DURING CURRENT SALP PERIOD I
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l November,1987 l
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l 'GPUN is able to evaluate performance based upon input from NRC, INP0 and L; comparison to industry standards. GPUN is constantly striving to learn end H improve from this avaluative process. The. following represents efforts which l' we believe illustrate this ' point and 'are relevant to the .TMI-l SALP evaluation.
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A. . At the start of this SALP period, TMI-l was shutdown for the start of
.the Cycle 6 refueling outage (6R). Key dates for the outage were: j
- October 31, 1986 - The plant commenced a planned shutdown for the l Cycle 6 refueling outage (6R). Startup from the outage was i scheduled for March 21,1987 (on the grid). i
- March 20,1987 - The plant (TMI-1) proceeded to heatup as the 6R outage was' nearing conclusion.
- March 22,1987 - An Integrated Remote Shutdown System test was successfully completed.
- March 23,1987 - The reactor was taken critical and low power physics testing commenced.
- March 24, 1987 - TMI-l was placed back on the grid and the 6R outage was declared over.
SUMMARY
OF 6R OUTAGE The 6R outage contained several major work items. In addition to the refueling work, other work included Reactor Building Integrated Leak Rate Testing, OTSG Inspection and Repair activities, OTSG Emergency Feedwater Nozzle replacement, M0 VATS testing of motor operated valves, Appendix R work, and the Heat Sink Protection System. Successful con >pletion of this major outage was accomplished by close coordination of the different'GPUN Divisions.
Specifically, the following items were the instrumental parts of this close working relationship.
- During the shutdown process, TMI-l utilized off-shift personnel to perform major surveillance tests while the on-shift crew concentrated on the plant shutdown /cooldown.
Although this test failed, it was redone successfully in an "as left" condition.
- By performing this ILRT as the first activity in the outage, we were able to take advantage of this time to allow for decaying radiation levels in the containment. This contributed in a lowering of the man-rem exposure.
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- The outage was scheduled for' 5 months. The pace of activities was ,
demanding but appropriate. The results proved the schedule was l commensurate with the scope of work.
- Assigning a dedicated shift technical advisor to act as a single point of contact beteen Operations and Engineering personnel foi* l the Heat Sink Protection System modification was an initiative that proved very beneficial. j 1
- An integral part of the outage was a cautious, planned approach to !
the work which entailed dry runs where appropriate. Thir resulted l in smooth flow of work and an overall man rem exposure below that I which was originally predicted. )
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- The extensive startup prerequisite list resulted in a smooth startup from the outage.
All of these items coupled with management attention resulted in a well paced, successful outage.
B. The professionalism of our control room operators continued to be high. Along with this, TMI-1 now has six control room operators who I are qualified as senior reactor operators which provides an.added experience level on shift.
C. On June 12, TMI-1 commenced a plant shutdown to replace both letdown coolers. The transition into and out of the letdown cooler replacement outage was relatively smooth and free of major equipment problems. The success of this outage was due to the good pre-planning and staging of material . The welders assigned to the job were chosen based on their proven competence and did an excellent job the first time. The comfort of the work area was improved by use of temporary air conditioning. The pace of activities was appropriately controlled which indicated our proper regard for nuclear safety. This was so despite the urgency to return TMI-l to power operation for power demand reasons. The plant was restarted June 27, 1987.
D. TMI-1 continues to have a high availability factor. Excluding the 6R
' outage and letdown cooler outage, TMI-1 has been shutdown for less than 2 days through the end of September 1987. Including the outages, the availability for the year through the end of September 1987 is i 63.3%. {
- 2. Licensing Activities A. GPUN completed a reorganization in June 1987 which established the Planning and Nuclear Safety Division. This is a relatively small, l highly focused division with the charter of improving safety. The
, groups within this division are nuclear safety, licensing and L planning. The establishment of this division reflects on GpVN's commitment to Nuclear Safety and improvement in this area.
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1 B. Periodic meetings were held between representatives of GPUN Licensing and'the NRC Project Manager to discuss the- status of licensing activities. The dates of these meetings were:
December 8,1986 February 5,1987 j March 11,1987 j April 24,1987 l May 21,'l987 i June 10,1987 j July 8,1987 l September 3,1987 October 9,1987 4
These meetings have proven to be vnry successful in terms of ;
communicating the status of issues, exchanging priorities /needs, and ;
expediting actions as appropriate. The NRC has recently indicated the j industry average time to issue a License Amendment is six months from the time the NRC receives a Technical Specification Change Request. '
For TMI-l this is four h.anths which reflects positively on both the NRC and GPUN's overall management of thJse important licensing issues.
On June 9 and 10,1987, the new NRC Project Managers for TMI-1 and Oyster Creek visited TMI-1 for a tour of the plant. Also on .
July 16 and 17, the TMI-1 Project Manager visited the GPUN Parsippany .
of fice. {
On July 16, 1987, the new NRC Region I Administrator conducted an [
extensive 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> inspection of TMI-1.
l C. GPUN remains active in Industry Activities / Committees to improve !
Licensing and Nuclear Safety performance. This has improved our ,
understanding of the Safety Review Process. It has particularly {
enhanced our work on Tech. Spec. simplification and great progress has ;
f been made in this area with the B&W Owners Group (BWOG).
Technical Activities 3.
A. Throughout the year every opportunity has been taken to meet with the NRC to better explain our technical analysis / basis and operational occurrences. The dates of some of these meetings with the NRC, NRR and Region I were:
- February 4,1987 - A meeting was held between representatives of GPUN and the NRC to discuss Reactor Coolant Inventory Trending System (RCITS).
- February 5,1987 - A meeting was held between representatives of GPUN and the NRC on a fire protection exemption for manual actions.
- February 12, 1987 - A meeting was held between representatives of .
GPUN and NRC Region I management to discuss the revised GPUN Technical and Safety Review Program and the results of the GPUN task
- force on procedure adherence.
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- February 24, 1987 - A meeting was held between representatives of l GPUN and NRC Region I management to discuss'the SALP Report No.
86-99.
- March 10,1987 - A meeting was held between representatives of GPUN and NRC Region I management to discuss the status of GPUN EQ activities as a result of NRC Inspection 87-01.
- May 21,1987 - A meeting was held between representatives of GPUN and the NRC to discuss new information on OTSG as a result of the tubes pulled during the 6R outage.
- June 10,1987 - A meeting was held between representatives of GPUN and the NRC to provide a status report of the NRC ongoing inspection of the GPUN Technical and Safety Review Program.
- August 24, 1987 - A meeting was held between representatives of GPUN and the NRC to discuss Technical Specification Change Request No.112, Revision 1 (Radiological Effluent Tech. Specs.).
- September 10, 1987 - A meeting was held between representatives of GPUN and Region I to discuss the status of GPUN's EQ program which included completion of previously specified performance requirements. .
- September 10, 1987 - A meeting was held between representatives of GPUN and the NRC to discuss the status of work on Appendix R and ,
HVAC systems. I B. GPUN is very active in the BWOG activities. We have.provided significant input in terms of chairing various subcommittees and are highly involved in all issues. This has resulted in the completion of l the development of the Safety Performance Improvement Program (SPIP) i which is an extensive effort to improve performance. j C. Looking at the technical support provided to the plant throughout the year, it becomes evident that this area is effective as evidenced by 1 the overall good technical support involvement for and during the 6R j Outage and startup, involvement and support of the letdown cooler i outage and continued support of plant operations. The above stated i involvement in meetings and BWOG activities also contributes to the !
effectiveness of this area. '
D. The engineering items identified during the NRC PAT I and II l inspections and the Readiness Appraisal Team Inspection have all been addressed. Actions to resolve the items, where required or appropriate, have been taken and completed. j We have used the PAT style approach to review some of our other work and believe it has helped improve our engineering work.
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- 4. Emergency Preparedness Several key items were accomplished in this area throughout the year.
These include:
conducted successfully. i
- The 1987 TMI annual exercise was a full scale exercise that was conducted successfully. All state, county and municipal governments observed by FEMA fully participated in the exercise.
- A major revision to the Corporate Emergency Plan has been undertaken and is near completion. This revision takes into account NRC j comments in addition to changing conditions at Unit 2. GPUN met '
with Region I on June 19, 1987 to discuss the proposed revision. j
- Unannounced shift and quarterly drills have been conducted to !
thoroughly test the availability and readiness of emergency response '
personnel.
- Utilization of the TMI Replica Simulator has been used for drill scencrfo development. It is expected that the simulator will be used for drill conduct starting in 1988. l
- Emergency Plan Training Requalification Program has had a thorough job task analysis conducted which had active input from key emergency response personnel, Emergency Preparedness Department and Training and Education Department, all of which culminated in a more effective requalification program.
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- A site has bee:1 identified for the new TMI Remote Assembly Area !
which provides a facility away from the predominant wind patterns !
and affords better protection for site evacuees. j
- Significant refinement has been made to the offsite dose assessment !
process to include increased reliability and accuracy both in the '
form of software and hardware changes. ;
- 5. Training ;
i GPUN's commitment to training continues to be an important factor in the operating of TMI-1. Although training is usually thought of as licensed operator training, this category involves much more. GPUN has INP0 accredited training programs in the areas of-
- a. Auxiliary Operator ,
- b. Reactor Operator
- c. Senior Reactor Operator
- d. Shift Technical Advisor
- e. Rad. Con, j
- f. Electrical Maintenance 9 Mechanical Maintenance
- h. I&C Maintenance
- 1. Chemistry
- j. Technical Staff and Manager 2-5 l
Additionally, our corporate training has programs for engineers, shift technical advisors and managernc'it. In the past year, a large percentage :
of managers and supervisors have ettended an extensive GPUN Teamwork and Leadership Program. This program builds on the concept of communication across division / department lines and individual accountability to foster ;
the team concept. GPUN firmly believes in this program and that it will '
assist in improving our performance.
The TMI-1 plant specific simulator was placed into service this year. The simulator is now an integral part of training and was used as part of the annual requalification examination.Previously each crew only had one week of training on the plant simulator at B&W. Now each crew has 55 to 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year on the TMI plant specific simulator. GPUN emphasis is on the crew working as a team. This additional time allows for each crew to simulate plant conditions and improve on the team concept.
On March 12, 1987, GPUN completed the administration of the annual requalification examinations for licensed operators (R0 and SRO). These examinations were audited by the NRC and the NRC did substitute NRC questions in about 10% of the examinations. These examinations were the culmination of an extensive training program which emphasized new modifications installed during the 6R outage. In addition to classroom sessions, this training also included plant walk-throughs and easy to read handouts. This aided the operators in becoming familiar with the new modifications.
The revised Operator's Licenses rule, Part 55 became effective in May 1987. GPUN has implemented this revised rule.
- 6. Security and Safeguards The Security Department has taken the following actions to enhance the security program at TMI-1 since their last SALP report:
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- 3. Installed a new Perimeter Intrusion Detection System which provides a '
high level of assurance that unauthorized personnel and/or intrusion attempts would be detected and appropriate response initiated.
- b. Installed new search equipment in personnel processing center.
Realigned search equipment to enhance personnel processing and increase capability of detecting explosive devices.
- c. Eliminated all contract security officers and increased GPUN site protection force. ;
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[ a.i l a, d. In~ addition'to Training and Qualification Program. requirements, a j Strategic Planning. Team Training Program has been implemented. q Instructors for this program have been trained in Strategic Reaction s a Team by:Essex Corp. in Gainsville, Georgia; Response' Team at Pensville ]
Police Dept. and sponsored by the Greater Pittsburgh Police Dept. j
. Association; and Hand Gun Retention Program by Smith and Wesson Corp.- i
- e. Implemented 10CFR73.67 (FBI Criminal Background Checks). Over.2300 personnel who access TMI have been fingerprinted in conjunction with this program,
- f. Submitted Revisions 22, 23 and 24 to the Security Plan. Revision 24 significantly. upgradas the Personnel Security Screening requirements.
The new screening requirements are essentially those approved by NUMARC.
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