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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
[Table view] |
Text
GPU Nuclear Corporation Nuclear :::, ors:r8o Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Nurnber:
(717) 948-8461 44~,t L-0140 Dc. ment ID 0280A June 27, 1985 Office of Nuclear Reactor Regulation Attn: Mr. D. G. Eisenhut Director, Division of Licensing US Nuclear Regulatory Commission 5920 Norfolk Avenue Bethesda, to 20014
Dear Mr. Eisenhut:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Generic Letter 84-15 Attached is TMI-2's response to Generic Letter 84-15, " Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability". Tables 1 and 2 of the Enclosure provide a time history of the last 100 valid starts of each TMI-2 diesel generator.
Sincerely, \
' / \ U sk.
g Q , I mw..
F. R. Standerfer
& Vice President / Director, TMI-2 FRS/RDW/eml Attachment cc: Program Director - TH1 Program Office, Dr. B. J. Snyder Deputy Program Director - TMI Program Office, Dr. W. D. Travers 0507150317 050627 b PDR ADOCK 05000320 P PDR \\
Nf)\ ll OPU Nuclear Corporation is a subsidiary of the Gonoral Public Utilities Corporation u
ATTACHMENT (4410-85-L-0140)
NRC Item 1 - Reduction in Number of Cold Fast Start Surveillance Tests for Diesel Generators This item is directed towards reducing the number of cold fast start surveillance tests for diesel generators which the staff has determined results in premature diesel engine degradation. The details relating to this subject are provided in Enclosure 1. Licensees are requested to describe their current programs to avoid cold fast start surveillance testing or their intended actions to reduce cold fast start surveillance testing for diesel generators.
GPU Nuclear Response During the recovery mode, TMI-2 is not required to perform cold fast starts on the emergency diesel generators CF-X-1A and B. The diesel generators are operated and surveilled in accordance with TMI-2 Procedures 4210-0PS-3860.01,
" Emergency Diesels and Auxiliaries", and 4303-M16A/B, " Emergency Diesel Generator Operability Test", respectively. These procedures include the manufacturer's (Fairbanks/ Morse) recommendations for prelubing and warming prior to starting the diesel generators.
NRC Item 2 - Diesel Generator Reliability Data This item requests licensees to furnish the current reliability of each diesel generator at their plant (s), based on surveillance test data. Licensees are requested to provide the following information:
... include the number of failures in the last 20 and 100 valid demands indicating the time history for these failures. Licensees are requested to indicate whether they maintain a record which itemizes the demands and failures experienced by each diesel generator unit, in the manner outlined in Regulatory Guide 1.108 position C.3.a. for each diesel generator unit. Licensees should also indicate whether a yearly data report is maintained for each diesel generator's reliability."
GPU Nuclear Response The reliability of the diesel generators at TMi-2 is shown below:
DIESEL FAILURES IN THE FAILURES IN THE GENERATOR LAST 20 TESTS RELIABILITY LAST 100 TESTS RELIABILITY DF-X-1A 0 1.0 Test Nos. 52 & 74 .98 DF-X-10 0 1.0 Test No. 18 .99 The above figures were derived from the enclosed Tables 1 and 2 which include the last 100 valid starts for each diesel generator. Valid starts were classified in accordance with Regulatory Guide 1.108; invalid tests are marked "NA".
r ATTACHMENT l (4410-O-L-0140)
The information listed in Tables 1 and 2 were obtained from the Control Room Operator's log. This information is also obtainable from the following TMI-2 documents:
l 0 Licensee Event Reports l
l o Technical Specification completed surveillance procedures l 0 Machinery computer history of corrective maintenance, preventive l
maintenance, and test results of the diesel generators TMI-2 does not maintain records of diesel generator operational and failure data as outlined in position C.3.a of Regulatory Guide 1.108. Additionally, TMI-2 does not maintain a yearly data report of each diesel generator's reliability. GPU Nuclear believes, however, that the above listed documents provide an accurate historical account of any events relating to the TMI-2 diesel generators.
l 1
1 NRC Item 3 - Diesel Generator Reliability Licensees are requested to describe their program, if any, for attaining and maintaining a reliability goal for their generators. An example of a l performance Technical Specification to support a desired diesel generator
- reliability goal has been provided by the staff in Enclosure 3. Licensees are
! requested to comment on, and compare their existing program or any proposed I program with the example performance specification.
1
( GPU Nuclear Response i
As indicated in the response to Item 2, the reliability figures for the diesel
! generators indicate that there is currently no need for an improved diesel generator reliability program. Futhermore, the NRC's Amendment Order dated December 19, 1984, reduced the number of surveillance runs from once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to once every 7 days when a redundant diesel generator or offsite power source is out of service. Reducing the frequency of unnecessary diesel generator starts results in improved reliability by decreasing the possibility of premature diesel engine degradation.
GPU Nuclear is currently developing a Technical Specification Cnange Request (TSCR) which proposes deleting the diesel generator requirements at TMI-2.
This proposed TSCR is based on a Safety Evaluation Report which demonstates that the diesel generators are not required for safe operation of TMI-2 during the recovery mode.
Therefore, pending the submittal and approval of the above TSCR, LiPU Nuclear does not intend to alter the surveillance and maintenance programs of the THI-2 diesel generators.
l l
TABLE I Pag 2 1 cf 12 TMI-2 EMTRMCY CIESEL CE ERATOR DF-I-1A START DATA START IAAD TI?E RUN
[ m, DATE TIME REASON FOR RUN t YJ) AT N COMMENTS 100 04-22-85 0345 3YJ l HR. Nuthly Surveillance (Procedure 4303-M16A) 99 03-2% 85 0110 3Ya' I HR.
' "E I ""*I ""C" (Procedure 4303-M16A) l l 93 02-25-85 0310 33G 1 HR. y unell ance (Procedure 4303-M16A) 97 02-14-85 0414 3YJ l HR. S rveillance run prior to taking redun-dant diesel out of service.
96 01-30-85 1515 3YJ HR.
I Post Maintenance surveillance.
1 NA 01-29-85 1132 Started for maintenance.
! 95 01-28-85 0355 3a' ' " I ""*I I""*"
I HR.
(Procedure 4303-M16A) 94 12-26-84 0159 3YJ I HR.
ont y uneillance (Procedure 4303-M16A) 93 12-03-84 0320 3YJ l HR.
nthly Surveillance <
(Procedure 4303-MI6A) 92 1 0-31-34 II i5 3YJ ! HR.
- I * * #*
(Procedure 4303-M16A) 91 10-30-84 0333 3YJ l HR. Surveillance run due to redundant diesel IB diesel generator annual being out of service. preventive maintenance.
L
r_ __ _ _ _ _ _ - ---__------- --__ - - _ _ _ - - - - - - - -
TABLE 1 Pega 2 cf 12 I TMI-2 EMERCENCY CIESEL CD;ERATOR DF-I-1A START DATA -
l START LOAD TUtE RUN DATE TI!F- REASON FOR Ring COMMENTS KO. OG) AT LDAD 93 10-29-84 0340 M .5 ER. Surveillance run due to redundant diesel IB diesel generator annual being out of service. preventive maintenance.
89 10.-29-84 1532 3W 1 ER.
O 83 10-28-84 1534 3W .5 ER.
87 10-28-84 0335 3W .5 HR.
1 86 10-27-84 1635 3W .5 ER.
85 10-27-84 0436 3W .5 ER.
84 10-26-84 1631 M .5 ER.
83 10-26-84 0433 35 .5 ER.
82 10-25-84 1640 M .5 ER.
81 10-25-34 05UO 3W .5 ER.
80 10-24-84 1640 3W .5 ER.
)[ \f
TAELE 1 Pcg3 3 cf 12 TMI-2 D'FRf31rCY DIESEL CENERATOR DF-I-1A START DATA -
STAEI 14AD TIME RUN m, DATE TDF- gg) g REASON FOR RUN COMMENTS Suneillance run Prior to taking redun-79 10-24-84 0400 3W 1 HR.
dant diesel out of service.
78 10.-23-84 1102 3N 1 HR.
operability.
5A 10-23-84 1 032 Overspeed trip testing 4
NA 10-23-84 1032 Overspeed trip testing.
See See Annual preventive maintenance break-in 1 HR. @ .75W 2 HR @ 1.86W l
NA 10-20-84 1358 Comments Comments run. 1 HR. @ 1.11W 3 HR @ 2.25W 2 HR. @ 1.5 g 3 Hg g g.61W Freventive maintenance break-in run due KA 10-20-84 1140 to liner replacement.
l NA 10-20-84 1128 NA 10-20-84 1042 NA 10-2O-84 0955 .
1 f 77 10-08-84 $ 0451 3m 1 ER. M nthly surveillance (Procedure 4303-M16A) .
76 09-10-84 1315 3m 1 HR.
M nthly surveillance (Procedure 4303-M16A) l l
TABLE I Pcga 4 ef 12 TMI-2 EMERCENCY DIESEL CENERATOR DF-I-1 A START DATA START LOAD TDfE RCI g, DATE TIME A (MJ) AT LOAD I CO M S NA 0S-18-84 0500 Started for troubleshooting purposes.
74 05-18-84 0135 Start failure - diesel failed Started for monthly surveillance.
to come up to speed and voltage.
Operator error in timing diesel NA 03-18-84 0428 -
Started for monthly surveillance start - Diesel was shtdom h-mediately after start.
73 03-06-84 1356 M HR.
1 Post maintenance surveillance run.
72 08-02-84 1737 3M2 HR.
I Post maintenance surveillance run.
71 08-02-84 1415 3rd 2 HR.
being out of service. -
70 07-16-84 0425 3YJ l HR.
"E I """*III*"C' (Procedure 4303-M16A) l 69 C613-84 1555 3YJ u e a ce e an
.5 ER. esel being out of service for relay maintenance.
68 06-13-84 G103 3".4 .5 ER.
67 CG 12-84 1610 3M2 .5 HR.
y - -
66 Cbl2-84 0416 3MJ l ER.
I* * ## # #*
(Procedure 4303-M16A) f I
l
TA3LE 1 Pag 3 5 cf 12 TMI-2 EMERGENCY DIESEL CENERATOR CF-I-1 A START DATA -
ST m DATE TIE REASON FOR RIN
- 50. OG) AT I.DA3 COMMENTS 65 06-11-84 1659 3FJ * #### "" * *
being out of service for relay maintenance.
64 06-11-84 0500 3 73 .5 HR.
If 63 06-06-84 1650 Surveillance run due to redundant diesel 3'm .5 BR. being out of service for maintenance.
62 06-06-84 0513 'b 2 .5 HR.
61 06-05-84 1758 3FJ .5 HR.
60 C6-05-84 0523 3.'M .5 HR.
59 06-04-84 1740 3 73 .5 HR.
58 06-04-84 Surveillance run prior to taking redun-0522 3"J HR.
l dant diesel out of service for mainten-ree.
) 57 05-31-84 1410 3'N I HR.
s intenance suneillance mn for
56 05-22-84 0 50 3YJ .5 HR. Surveillance run due. to reduntant diesel being out of service. ,
55 05-21-84 1617 3FJ .5 HR.
l
TABI.E 1 Pag 2 6 cf 12 TMI-2 EMERCENCY CIESEL CE: ERATOR DF-I-1A START DATA t
i START IRAD TIME RI*N TM REASON FOR RUN
- 50. (M:J) AT IDAD CO E WS 54 05-21-64 0444 3S Surveillance run prior to taking redun-43 BR. dant diesel out of service 53 05-18-84 1931 3W I Post maintenance surveillance /conthly ER. surveillance. (Procedure 4303-M16A)
KA 05-18-84 1911 Started for =aintenance to troubleshoot output breaker malfunction.
KA 05-IS-34 1634
%A 05-15-84 1415 If 52 05-15-S4 1140 St art failure - Diesel generator Started for nonthly surveillance output breaker failed to close.
51 05-17-84 1206 3W HR.
I Post maintenance surveillance run.
50 05-11-84 1412 3W ER.
I Post naintenance surveillance run.
49 05-01-84 0533 Survelliance run prior to taking redun-3W .5 ilR. dant diesel out of service. .,
48 04-23-84 0203 3W I HR.
" I """* #**
(Procedure 4303-M16A) 47 04-13-84 2053 3W I HR. Post maintenance surveillance run.
9
I TAELE 1 Peg 2 7 ef 12 I
TMI-2 EMERCENCY CIESEL CEXERATOR DF-I-1A STARI DATA l
START I. DAD TIME RCN g, DATE TIME REASON FOR RLN g CO E Yrs KA 04 % 1823 Started for naintenance.
KA 04-I S-M 1746 XA M-18-M 1700 NA C4-18-% 1620 hf 46 04-16-81 1648 M 1 HR. Post naintenance surveillance run.
45 C4-13-M 1410 M 1 HR. Post maintenance surveillance run.
Heat-up run prior to changing governor 44 04-13-A 0805 M .5 HR. oil.
43 0 4- 0 % 84 0315 3MlJ 1 HR. I """ * # **
(Procedure 4303-MI6A) 42 Surveillance run due to a station ser-03-1 % S4 1241 M .5 HR. vice transformer being out of service. **
03-1 %%
Started after shutdown to verify correct XA 0334 f requency setting for emergency standby.
41 03-1%M U230 Surveillance run due to a station service 3M:s .5 HR. transformer being out of service.
I TABLE I Pcg2 8 cf 12 '
TMI-2 EMERGENCY DIESEL CENERATOR DF-X-1A STARI DATA DATE TIME *
- 50. MJ) AT LOA 3 REASON FDR RUN COMMENTS i
39 03-14-E4 2033 3MW .5 ER. Surveilla ce run prior to taking a statfor service transformer out of service.
I 33 03-10-84 C415 3MW .5 ER.
Surveillance run due to redundant diesel being out of service for instrunent calibrart-n_ -
i l
37 33-08-84 0510 3%*
Surveillance run due to redundant diesel
.5 ER. being out of service.
i 36 03-C7-84 2021 Nnthly surveillance - Post nalatenance l 3NJ 1 HR.
l surveillance - (Procedure 4303-MI6A) l
& nthly surveillance 35 C:2-10-84 1255 35' i
1 1 ER. (Procedurc 4303-M16A) 31 01-30-84 II16 3W I HR. Post maintenance surveillance run.
I l
33 01-27-34 1130 3W HR.
I Post maintenance surveillance run.
' &nthly surveillance 32 01-16-84 0100 3W 1 ER. (Procedure 4303-M16A) l 31 12-23-83 2325 357 HR.
I Post r.ainten' nee surveillance run.
KA 12-22-83 2050 3&T 2 ER. Run for maintenance purposes. Troubleshooting governer problem KA 12-22-83 2016 -
Started for maintenance purposes.
\f 9
TABLE I Pega 9 ef 12 TMI-2 EMIRGINCY CIESEL GC;ERATOR DF-I-1 A START DATA STAII IDAD TIME RUN g, DATE TI.wE g ,) REASON FOR RUN COMMEVIS AT IDA3 5A 12-22-S3 1425 3FJ 1 HR. Run for nalatenance purposes Troubleshooting governor problem Started and run for maintenance testing sa 12-22-83 IMS --
purposes.
KA 12-21-83 2115 KA 12-21-83 1910 3*J 1.5 HR.
KA 12-21-53 1347 NA 12-21-83 1115 3W . 3 HR.
Y if Surveillance run to determine if there Governor was determined not to l
- 30 12-20-83 1330 3Fi 1 ER. was a problem with the governor. be functioning properly.
l l mathly surveillance 29 12-19-83 0%5 37; I HR. (Procedure 4303-M16A) ll 29 12-02-83 1255 3*i I HR. Post maint enance surveillance run.
27 11-30-83 1710 3?i 1 HR. Post naintenance surveillance run.
2 4
&nthly surveillance 26 11-23-4J 0345 M' 1 HR. (Procedure 4303-M16A)
TABLE 1 Pago 10 cf 12 <
TEI-2 NSCY DIESEL CUETOR DF-I-1A START DATA I
START IJCAD TIME R*.'.N g, DATE TIME REASON FOR RUN COMMENTS (FJ) AT E 25 11-11-EJ 1410 3W I ER. Post Maintenance surveillance run.
21 11-C2-S] 1726 3*2 1 ER. Post maintenance surveillance run.
l l Surveillance run due to a station service 23 10-27-BJ 1$23 3Fi .5 HR. transformer being out of service.
22 10-27-8] 0530 3*J .5 ER.
21 10-26-3] 1732 3*J .5 HR.
l l
20 10-26-8: 0510 3m .5 ER.
I 1
19 10-25-8: IEai 3"i .5 HR.
l IS 10-24-8: ,
1910 3s .5 HR.
! t l 17 1G-24-83 0706 3*J .5 HR. -
l l
l 16 10-21-33 ~1245 3FJ .5 HR.
l ,s l }
l 15 10-21-53 0120 3wJ .5 ER.
II
I TAELE 1 pegg 11 of 12 TMI-2 DERGENCY CIESEL CENERATOR DF-X-1A START DATA -
START LCA3 TUIE R3 m, DATE TIME g ) g REASON FOR RUN COMMENTS i Monthly surveillance l 14 10-20-33 1433 35 I ER. (Procedure 4303-M16A) l Surveillance run due to a station service 13 10-19-83 2124 3W .5 ER. transformer Feing out of service.
I q
l 12 10-19-83 1014 35 .5 ER.
11 10-19-83 0%5 3L I ER.
10 10-18-83 1300 M 1 ER.
9 10-15-83 0110 3W .5 RR.
l .
8 10-17-83 1300 M .5 ER.
7 10-17-83 0225 3m .5 ER.
1 I
""" # #* " E# # # "E "~
6 10-13-83 0510 M .5 ER. .:
dant diesel out of service.
5 09-27-83 T715 M .5 ER.
dant diesel being out of service. ,,
Surveilla ce run Prior to taking a 4 09-27-83 0535 3W .5 ER. station service transformer out of .
service.
l , _ _ - __ _ - .-. -
r . ,
l TABLE 1 Paga 12 cf 12 l TMI-2 DCERCENCY CIESEl. CE::IRATOR DF-I-I A START DATA 1
l STAII IDA3 TIME Kr5 g, DAIE TI!E gg) REASON FOR RUN COMMENTS 7 ~{
Surveillance run due to redundant diesel 3 09-2 b83 1323 35 .5 HR. being out of service.
Started for surveillance run due to Operator error in timing diesel XA 0%2b83 1255 redundant diesel being out of service. start - diesel was shutdown im-mediately after start.
2 0%2bS3 CO5O E.2 .5 Hl.
""* **## "" " * * ** "" #"* I***
beleg out of service.
1 09-23-53 1213 3N .5 HR.
if l
J
~
l i
g ,- ,,n., --- ,-- -
-- -- , , - - - - - - - -n - - --- --- ---- ,m- , - -
, r
TABLE 2 Paga 1 ef 10 TMI-2 IwumCT CIESEL CENERATOR DF-I-1B STARI DATA -
DATE TIMt REASON FOR RUN C0fetENTS M:2nthly surveillance 100 05-C M S m 3N 1 HR.
(Procedure 4303-MI65) 99 C4-CS-85 1800 3W I HR. '
l l
l 93 03-11-35 0335 35 1 HR.
l If I
N Post maintenance surveillance run for C2-It-85 1332 3W 1 HR.
operability.
Monthly surveillance 96 C2-11-85 0105 3E 1 HR. (Procedure 4303-M16A) 95 01-29-85 Survelliance run prior to taking redun-0403 3W I HR. dant diesel out of service for mainten-ance.
Monthly surveillance 9% 01-14-85 04C5 3W I HR. (Procedure 4303-M16A) 93 12-31-85 C643 3W I HR. Run for operations surveillance Nathly surveillance 92 12-17-84 0306 3s 1 HR. (Procedure 4303-M16A) 91 12-03-84 1225 3m 1 HR. Run for operations surveillance. .
Monthly surveillance 90 11-19-84 0358 3W HR.
1 (Procedure 4303-MI6A)
TABLE 2 Pega 2 of 10 s TMI-2 EMERGENCY CIESEL CENERATOR DF-I-IB STARI DATA ,
START !4A3 TDfE RUN i
go, DATE M '
(W) AT LDA3 REASON FOR RUN COMMENTS 89 11-07-84 1015 3W I HR. Operations surveillance 83 11-05-54 1241 3N 1 HR. Run for operations surveillance
- 87 10-31-54 Surveillance run prior to taking redun- 5
! 0100 3N 1 HR. dant diesel out of service for mainten-ance.
86 1%3W IMS M 1 HR. Post maintenance surveillance run for operability.
85 IG-23-84 1325 3N .5 HR. Suncilla e mn d e to redundant diesel IA diesel generator annual pre-being out of service. ventive maintenance.
84 10-23-84 0333 3N .5 HR.
83 10.-22-84 1535 3N .5 HR.
82 10-22-84 0335 3N .5 HR.
If 81 10-21-S; 1535 3N 1 HR. y su nei ance sune1 Hance mn due to redundant diesel being out of ser- .
vice - (Procedure 4303-MI6B) .
80 10-21-84 0.337 3N .5 HR. une a ce mn ue re un ant diesel being out of service.
i.,
79 10-20-84 153S 3N 1 HR.
?
3f
TABLE 2 Prg'2 3 ef 10 TMI-2 EMERCENCY DIESEL CENERATOR DF-I-1B START DATA DATE TIME g REASON FOR RUN COMMENTS '
Surveillance run due to redundant diesel IA diesel generator annual pre-78 10-20-84 0348 3N .5 HR. being out of service. ventive maintenance.
5 77 10-19-34 1550 3N .5 HR. ,
76 10-19-84 0337 3W .5 HR.
75 10-18-84 1537 3W 1 HR.
74 10-18-84 0333 3N .5 HR.
73 10-17-84 1539 3N .5 HR.
72 10-17-84 0340 3W .5 HR.
71 10-16-84 1548 3,W .5 HR.
70 10-16-84 0348 3W .5 HR.
69 10-15-84 1549 3N .5 HE. f 68 10-15-84 0350 3W .5 HR.
If If
TABLE 2 Pcg2 4 ef 10 TMI-2 EMERCENCY EIESEL GENERATOR CF-I-1B START DATA CATE TIME g REASON FOR RUN COMMENTS Surveillance run due to redundant diesel IA diesel generator annual 67 10-14-84 1613 3W .5 HR. being out of service. preventive maintenance.
66 10-14-84 0415 3W .5 HR. .
65 10-13-84 1640 3W .5 HR.
64 10-13-84 0443 3W .5 HR.
63 10-12-84 1706 3W .5 HR.
62 10-12-84 0508 3W .5 HR.
61 10-11-84 1728 3W I HR.
If If Operator error in timing diesel NA 10-11-84 1722 Started for surveillance. start - diesel was shutdown and restarted.
Surveillance run due to redundant diesel IA diesel generator annual 60 10-11-84 0455 3W .5 HR. being out of service preventive maintenance.
59 10-10-84 1700 3W .5 HR. p, 58 10-10-84 0508 3W .5 HR.
)[ \ [
1 1 TABLE 2 Peg 2 5 cf 10 TMI-2 EMERGENCY DIESEL CENERATOs CF-X-1B START DATA DATE TIME g REASON FOR RUN COMMENTS Surveillance run due to redundant diesel 1A diesel generator annual 57 10-09-84 1724 3MW .5 HR. being out of service preventive maintenance.
f 56 10-09-84 0503 3MW .5 HR.
1f 1f Operator error in timing diesel' NA 10-09-84 0500 start - diesel was shutdown and Started for surveillance restarted.
Surveillance run due to redundant diesel 55 10-08-84 1710 3MW .5 HR. being out of service.
Operator error in timing diesel NA 10-08-85 1700 Started for surveillance start - diesel was shutdown and restarted.
~
Surveillance run prior to taking redun-54 10-08-84 0420 3MW 1 HR. dant diesel out of service. .
Monthly surveillance 53 09-24-84 0115 3MW 1 HR. (Procedure 4303-M16B) i 52 09-10-84 0105 3MW 1 HR. Operations surveillance Monthly Surveillance 51 03-27-84 0415 3MW 1 HR. (Procedure 4303-M16B) l 50 08-18-84 1705 3MW 1 HR. Post maintenance surveillance run. ,
Surveillance run due to redundant diesel 49 08-18-84 0603 3MW 1 HR. being out of service.
TABLE 2 Pag 2 6 ef10 TMI-2 EMERGENCY DIESEL CENERATOR DF-X-1B START DATA DATE TIME REASON FOR RUN COMMENTS AT LO t
48 08-13-84 1706 3W l HR. Operations surveillance .
Surveillance run prior to taking redun- ,
47 08-06-84 0452 3W I HR. dant diesel out of service.
Post maintenance surveillance run to 46 08-02-84 1612 3W 1 HR. verify operability.
Monthly surveillance 45 07-30-84 0450 3W 1 HR. (Procedure 4303-M16B) 44 07-16-84 1226 3W I HR. Operations surveillance Operator error in timing diesel NA 07-16-84 1218 -
Started for operations surveillance. start - diesel was shutdown and restarted.
Monthly surveillance 43 07-02-84 0230 3W l HR. (Procedure 4303-M16B) 42 06-18-84 0928 3W I HR. Operations surveillance.
41 06-14-84 0100 3W I HR. Post maintenance surveillance run.
.. Monthly surveillance / post maintenance 4 40 06-06-84 1925 3W I HR. surveillance run - (Procedure 4303-M16B) *;
. Surviellance run prior to taking redun-39 05-31-82 0404 3W l HR. dant diesel out of service.
TABLE.2 Page 7 of 10 THI-2 EMERGENCY DIESEL GENERATOR DF-X-1B START DATA
^
DATE TIME REASON FOR RUN COMMENTS N0. , AT LO ,
38 05-22-84 1435 3MW 1 HR. Post maintenance surveillance run.
37 05-18-84 2129 3MW I HR. Post maintenance surveillance run.
t 36 05-18-84 1227 3MW 1 HR. Post maintenance surveillance run.
Surveillance run due to redundant diesel 35 05-11-84 1245 3MW .5 HR. being out of service.
Monthly surveillance / post maintenance 34 05-01-84 1315 3MW 1 HR. surveillance (Procedure 4303-M16B) 33 05-01-84 0813 3MW .5 HR. Run for maintenance purposes. Governor oil change.
Surveillance run due to redundant diesel 32 04-18-84 1719 3MW .5 HR. being out of service.
31 04-18-84 0511 3MW .5 HR.
30 04-17-84 1707 3MW .5 HR.
.c 29 04-17-84 0435 3MW 1 HR.
. .1f 28 04-16-84 1738 3MW .5 HR.
1Y
_ _ _ _ _ _ _ _ _ _ _ . _ . U
TABLE 2 Pagn 8 of l0 THI-2 EMERGENCY DIESEL GENERATOR DF-X-1B START DATA
^ "
DATE TIME REASON FOR RUN COMMENTS N0. AT LO Surveillance run prior to taking redun-27 04-16-84 0425 3MW 1 HR. dant diesel out of service.
Surveillance run prior to taking redun-
- 26 04-13-84 0525 3MW .5 HR. dant diesel out of service, o
Monthly surveillance 25 04-08-84 0335 3MW 1 HR. (Procedure 4303-M16B) 24 03-26-84 1145 3MW 1 HR. Operations surveillance.
Surveillance run due to one station-23 03-19-84 1353 3MW .5 HR. service transformer being out of service.
Surveillance run prior to taking a 22 03-19-84 0347 3MW .5 HR. station service transformer out of i service.
Surveillance run due to one station 21 03-16-84 0923 3MW .5 HR. service transformer being out of service.
Surveillance -run prior to taking one 20 03-15-84 2135 3MW .5 HR. station service transformer out of service.
Monthly surveillance / post maintenance 19 03-08-84 1110 3MW 1 HR. surveillance run - (Procedure 4303-M16B) .
- stopped NA 03-08-8/ 1055 --- ---
No information r aren n.
Surveillance run due to redundant Start failure - diesel taken 18 03-07-8L 1655 ---
diesel being out of service. out of service for trouble-shooting.
- _ _ _ _ - - - _ . _ - - _ . - . _ = . .. --. . . - . _ _ _ - . - . - . ~ . _ -
TABLE 2 Page 9 of 10 TMI-2 EMERGENCY DIESEL GENERATOR DF-X-1B START DATA 1 START LOAD TIME RUN NO.
^ REASON FOR RUN COMMENTS l (HW) AT LOAD Surveillance run due to redundant diesel 17 03-07-84 0456 3MW .5 HR. being out of service.
a I
Surveillance run due to redundant diesel ,
16 03-06-84 1645 3MW 1 HR. being out of service. ,
y o
Surveillance run prior to taking redun-15 03-06-84 0500 3MW 1 HR. dant diesel out of service.
14 02-27-84 0855 3MW 1 HR. Operations surveillance.
Monthly surveillance
.13 02-12-84 1205 3MW 1 HR. (Procedure'4303-M16B).
Surveillance run due t'o redundant diesel 12 01-30-84 1435 3MW 1 HR. being out of service.
Surveillance run prior to taking l 11 01-30-84 -515 3MW 1 HR. redundant diesel out of service.
J l
Surveillance' run prior to taking redun-10 01-27-84 -344 3MW 1 HR. dant diesel out of service.
n y surveillance 9 01-16-84 0230 3MW 1 HR.
(Procedure 4303-M16B)
.- .?
8 01-02-82 0935 3MW 1 HR. Operations surveillance ,p Surveillence run due to redundant diesel 7 12-22-8:l 1735 3MW .5 HR. being out of service.
i e
TABLE 2 page 10 of 10 THI-2 EMERGENCY DIESEL GENERATOR DF-X-1B START DATA
^ I" N0.
DATE TIME REASON FOR RUN COMMENTS T LO Surveillance run due to redundant diesel 6 12-22-83 0520 3MW .5 HR. being out of service.
t 5 12-21-83 1725 3MW .5 HR.
C 4 12-21-83 0521 3MW .5 HR.
3 12-20-83 1830 3MW .5 HR.
- )f Monthly surveillance 2 12-18-83 1935 3MW 1 HR. (Procedure 4303-M16B)-
1 12-05-83 1049 3MW 1 HR. Operations surveillance.
M 9
4
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