ML20141H062
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| ML20141H062 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 01/07/1986 |
| From: | Miraglia F Office of Nuclear Reactor Regulation |
| To: | Tucker H BABCOCK & WILCOX OPERATING PLANTS OWNERS GROUP, DUKE POWER CO. |
| References | |
| NUDOCS 8601130399 | |
| Download: ML20141H062 (1) | |
Similar Documents at Three Mile Island | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M0721999-10-19019 October 1999
[Table view]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 Category:NRC TO UTILITY MONTHYEARML20062E7811990-11-14014 November 1990
[Table view]Forwards Summary of NRC Understanding of Current Status of Unimplemented Generic Safety Issues at Plant,Per Generic Ltr 90-04 ML20058G1271990-11-0606 November 1990 Forwards Amend 39 to License DPR-73 & Safety Evaluation. Amend Modifies Tech Specs to Revise Administrative Requirements Re Periodic Audits of Activities ML20058D3021990-10-29029 October 1990 Forwards Safety Insp Rept 50-289/90-17 on 900924-28.No Violations Noted.Data from Independent Measurements Will Be Reported in Subsequent Insp Rept ML20058A6091990-10-19019 October 1990 Forwards Safety Insp Repts 50-289/90-15 & 50-320/90-08 on 900807-0921 & Notice of Violation ML20058A4591990-10-16016 October 1990 Informs of Pending Requalification Program Evaluation on 900128.Ref Matls Listed in Encl 1 Requested.Nrc Rules & Guidance for Examinees & Administration of Requalification Exams Also Encl ML20058A9861990-10-15015 October 1990 Discusses Review Approving Rev 23 to Organization Plan Submitted in Conjunction W/Tech Spec Change Request 65 ML20062B8771990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062B8741990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20058B2781990-10-0909 October 1990 Forwards Final SALP Rept 50-289/89-99 for 890116-900515 ML20062B0941990-10-0303 October 1990 Forwards Safety Insp Rept 50-289/90-80 on 900912-14. Violations & Exercise Weaknesses Noted.Util Demonstrated Ability to Implement EPIP in Manner to Provide Adequate Protective Measures for Health & Safety of Public ML20059H1491990-09-12012 September 1990 Ack Receipt of & Payment in Amount of $50,000 for Civil Penalty Proposed by NRC ML20059E3141990-08-24024 August 1990 Forwards Safety Insp Repts 50-289/90-16 & 50-320/90-07 on 900806-10.No Violations Noted IR 05000289/19890821990-08-15015 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-289/89-82 ML20058P4631990-08-0909 August 1990 Forwards Safety Evaluation Accepting Util 900307 Proposed Changes to Table 4.3-3 of Recovery Operations Plan.Changes Will Modify Surveillance & Operability Requirements of Specific Criticality Monitors ML20059A7651990-08-0909 August 1990 Forwards Review of B&W Owners Group Pressurizer Surge Line Thermal Stratification BAW-2085 Analysis Per IE Bulletin 88-011.Continued Operation Justified Until Final Rept Complete But Issues Needing Resolution Noted ML20056A6011990-08-0606 August 1990 Requests Addl Info Re Evaluation of post-defueling Monitoring Storage Proposed License Amend & SAR ML20058N0771990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum to Share Experiences ML20058M3791990-08-0303 August 1990 Forwards Initial SALP Rept 50-289/89-99 for 890116-900515. Evaluation Will Be Discussed W/Util on 900813 at Plant Training Ctr.Util Should Be Prepared to Discuss Assessments & Plans for Improvement of Performance ML20058M2721990-08-0101 August 1990 Forwards Safety Insp Repts 50-289/90-12 & 50-320/90-05 on 900515-0626.No Violations Noted.Decline Noted in General Housekeeping for Facility Unit 2 Which May Warrant Increased Mgt Attention ML20056A1891990-07-31031 July 1990 Approves Proposed Rev 25 to TMI-2 Organizational Plan Submitted in Util .Change Reflects Reduced Work Activity Associated W/Mode 3 & Lack of Need for Two Separate Organizations to Perform Similar Functions ML20058L3521990-07-30030 July 1990 Discusses Investigation Rept 1-87-008 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 ML20058L2271990-07-26026 July 1990 Forwards Exam Rept 50-289/90-14OL Administered During Wk of 900716.Results of Exam Discussed ML20055D3151990-06-29029 June 1990 Advises That Rev 24 to TMI-2 Organization Plan Approved.Rev Deletes Existing Safety Review Group & Recognizes Independent Onsite Safety Review Group.Changes Will Not Eliminate Any Vital Position or Functions within Plant ML20055D0801990-06-27027 June 1990 Forwards Insp Rept 50-289/90-10 on 900507-11 & Notice of Violation.Insp Generally Noted Compliance W/Reg Guide 1.97 ML20055C9031990-06-21021 June 1990 Ack Receipt of Encl Final Rept of TMI-2 Safety Advisory Board ML20059M8321990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248G7881989-10-0202 October 1989 Informs of NRC Intention to Perform Team Insp of Maint Program at Facility.Insp Will Focus on Performance of Maint & Whether Components,Sys & Structures of Plant Adequately Maintained & Properly Repaired ML20248C4581989-09-27027 September 1989 Forwards Amend 11 to Indemnity Agreement B-64,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, Effective 890701 ML20248B6181989-09-22022 September 1989 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for 900109-11 & Requests Ref Matls by 891106.Rules & Guidelines for Exam Encl IR 05000289/19890171989-09-19019 September 1989 Forwards Reactive Insp Rept 50-289/89-17 on 890815-16 & Notice of Violation ML20247M9021989-09-18018 September 1989 Forwards Exam Rept 50-289/89-19OL of Exam Administered on 890810 ML20247K9961989-09-13013 September 1989 Forwards Safety Insp Rept 50-320/89-05 on 890603-0818.Good Response by Util to Two Operational Events Noted ML20247L0221989-09-11011 September 1989 Forwards Amend 35 to License DPR-73 & Safety Evaluation. Amend Modifies Tech Specs by Deleting Prohibition Imposed by 3.9.13 & on Disposal of Accident Generated Water ML20247E8201989-09-0606 September 1989 Forwards Safety Insp Repts 50-289/89-15 & 50-320/89-06 on 890724-28.No Violations Noted.Several Areas for Improvement Identified,Including Inadequate Critique Process Following Incidents ML20247B9181989-09-0101 September 1989 Forwards Insp Rept 50-289/89-13 on 890626-0707.No Violations Noted ML20247A3861989-08-30030 August 1989 Forwards Environ Assessment & Finding of No Significant Impact Re 870225 Application for Amend to License DPR-23, Modifying App a Tech Specs by Deleting Prohibition on Disposal of Accident Generated Water ML20246L5751989-08-30030 August 1989 Forwards Safety Insp Repts 50-289/89-16 & 50-320/89-07 on 890814-18.No Violations or Deviations Noted ML20246D5441989-08-22022 August 1989 Forwards Request for Addl Info Re Evaluation of post- Defueling Monitored Storage SAR ML20246J4151989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits,Per Info Notice 81-26.Util Should Ensure Procedures Incorporate Applicable Dose Limits of 10CFR20 ML20246H3251989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits,Per Info Notice 81-26.Util Should Ensure That Procedures Incorporate Applicable Dose Limits of 10CFR20 ML20246C6771989-08-16016 August 1989 Forwards Insp Rept 50-289/89-12 on 890610-0714.No Violations Noted ML20246A6391989-08-15015 August 1989 Advises That Requalification Program Evaluation Visit Scheduled for Wks of 891106 & 13.Ref Matl Requirements, Administration of Requalification Exams & NRC Rules & Guidance for Examinees Encl ML20246K9481989-07-14014 July 1989 Forwards Request for Addl Info Re post-defueled Monitored Storage SAR for Response,Per Util 880816 Submittal ML20246P3471989-07-13013 July 1989 Forwards Insp Rept 50-289/89-08 on 890401-0508.No Violations Noted ML20246H5951989-07-0707 July 1989 Forwards Insp Rept 50-289/89-80 on 890306-17.No Violations or Deviations Noted.Corrections to Stated Exam Rept Noted ML20246B8171989-06-29029 June 1989 Comments on Licensee 881017 Response to Generic Ltr 88-17 Re Expeditous Actions for Loss of DHR During Nonpower Operation ML20246E0121989-06-28028 June 1989 Forwards Safety Insp Rept 50-289/89-11 on 890510-0609.Two Violations for Which Enforcement Discretion Applied, Identified ML20246B0491989-06-28028 June 1989 Forwards Final SALP Rept 50-289/87-99 for 871101-890115 ML20246B0171989-06-27027 June 1989 Commends Util for Exemplary Hospitality Extended to Visiting Soviet Technical Working Group on 890608 ML20245J4321989-06-23023 June 1989 Forwards Safety Evaluation Accepting Licensee 850823 Response to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Reliability - On-Line Functional Testing of Reactor Trip Sys 1990-09-12 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217M0721999-10-19019 October 1999
[Table view]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 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 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 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 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 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 ML20212J0011999-09-27027 September 1999 Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted 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 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 ML20210B8231999-07-21021 July 1999 Forwards Exemption from Certain Requirements of 10CFR50.54(w) for Three Mile Island Nuclear Station,Unit 2 in Response to Licensee Application Dtd 990309,requesting Reduction in Amount of Insurance for Unit to Amount Listed ML20209H9401999-07-15015 July 1999 Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Application for Exemption Dtd 990309. Proposed Exemption Would Reduce Amount of Insurance for Onsite Property Damage Coverage as Listed 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) 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 ML20209F2571999-07-0909 July 1999 Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1 ML20209G5861999-07-0909 July 1999 Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted 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 ML20196J5631999-07-0101 July 1999 Informs That Util 981203 Joint Application with Amergen Energy Co Marked Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196J5741999-06-30030 June 1999 Informs That as Result of Staff Review of Util Response to GL 92-01,rev 1,suppl 1,info Provided in Support of PT Limits License Amend & B&W Topical Rept,Staff Revised Info for Plant,Unit 1,in Reactor Vessel Integrity Database ML20196H6811999-06-29029 June 1999 Forwards Insp Rept 50-289/99-03 on 990425-0605.No Violations Noted.However,Adequacy of Assessment of Reactor Bldg Emergency Cooler Operability Prior to Conducting Maintenance on One Reactor Bldg Spray Sys,Questionable ML20212H8711999-06-21021 June 1999 Discusses Updated Schedule Commitment Submitted by Gpu on 990602 for Implementing Thermo-Lag 330-1 Fire Barrier C/As & Completion of Thermo-Lag Effort at TMI-1.Informs NRC Will Incorporate Commitment Into Co Modifying License ML20195K2821999-06-17017 June 1999 Forwards Request for Addl Info Re Kinetic Expansion Region Inspection Acceptance Criteria ML20212H6621999-06-0404 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Three Mile Island Nuclear Station ML20207E7201999-05-27027 May 1999 Discusses Reorganization of Nrr,Effective 990328. Organization Chart Encl ML20207B6541999-05-27027 May 1999 Forwards SER Accepting Util Program to Periodically Verify design-basis Capability of safety-related MOV at TMI-1 & That Util Adequately Addressed Actions Requested in GL 96-05 ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206S3411999-05-14014 May 1999 Forwards Insp Rept 50-289/99-02 on 990314-0424.Violations Occurred & Being Treated as non-cited Violations.Security Program Was Inspected During Period & Found to Be Effective ML20206N5831999-05-13013 May 1999 Requests Description of Proposed Corrective Actions for Fire Zones AB-FZ-3,AB-FZ-5,AB-FZ-7,FH-FZ-2,CB-FA-1 & FH-FZ-6. Confirmation That Corrective Actions & Commitments Made Will Be Completed by 991231,requested IR 05000298/19980091999-05-12012 May 1999 Refers to Insp Rept 50-298/98-09 Conducted Between 981227-990130.During Insp,Apparent Violation of 10CFR50.50 Identified & Being Treated as non-cited ML20206H3571999-05-0606 May 1999 Forwards RAI Re 981203 Application & Suppls & 0416,requesting Review & Approval of Revised Core Protection SL & Bases for TMI-1 to Reflect Average of 20% of Tubes Plugged Per Sg.Response Requested within 10 Days of Receipt ML20207A5401999-04-29029 April 1999 Informs That Licensee 980930 Response to GL 96-06,appears to Be Reasonable & Appropriate for Specific Design & Configuration of RB Emergency Cooling at Plant,Unit 1 & That Staff Satisfied with Licensee Resolution of Waterhammer ML20206D4001999-04-20020 April 1999 Informs of Completion of Review of Gpu Request for Exemption Submitted on 961231,970908,971230,980521,981014,981125 & 981223 from Requirements of 10CFR50,App R,Section III.G.2 for TMI Unit 1.Forwards Exemption & Safety Evaluation ML20205S6791999-04-16016 April 1999 Forwards Insp Rept 50-289/99-01 on 990131-0313.No Violations Noted.Identification by Licensee Staff of Elevated Tritium Activity in Monitoring Well Led to Investigation & Identification of Leak from Buried Radwaste Path ML20205P3391999-04-0909 April 1999 Discusses Results of Plant Performance Review for Three Mile Island Completed on 990225.Historical Listing of Plant Issues That Were Considered During PPR Encl IR 05000289/19980061999-03-26026 March 1999 Ack Receipt of 981112 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-289/98-06 .Action Does Not Change NRC Determination That Change to Hpis Valve Configuration Involved URI ML20204E3911999-03-17017 March 1999 Informs That Region I Plans to Conduct Open Predecisional Enforcement Conference to Discuss Apparent Violations Re Efs Issues as Described in Insp Rept 50-289/98-09,per ML20204B6771999-03-15015 March 1999 Submits Withdrawal of Amend Request for Operating License DPR-46.Proposed Change Would Have Modified Facility TSs Pertaining to Neutron Monitoring Neutron Detectors ML20207H7391999-03-0505 March 1999 Forwards Insp Rept 50-289/98-09 on 981227-990130.Two Apparent Violations Being Considered for Enforcement Action.First Violation Deals with Failure to Follow Procedures for Control of Emergency Boration Source ML20203F4911999-02-0505 February 1999 Forwards Request for Addl Info Re Licensee 981125 Amend Application Re TS Change Request 277 for OTSG Inservice Insp During 13R for Three Mile Island,Unit 1 ML20202H6771999-02-0303 February 1999 Documents Basis for NRC Staff Generic Approval of Requests to Relocate TS Requirements from Tss.Staff Generic SER Finding Relative to Relocated TS Requirements Encl ML20196K3511999-01-22022 January 1999 Refers to Gpu Responses to Second NRC RAI Re GL 92-08 & Review of Gpu Analytical Approach for Ampacity Derating Determinations.Forwards SE & SNL Technical Ltr Rept Concluding That No Outstanding Safety Concerns Identified ML20199H6471999-01-20020 January 1999 Forwards RAI Re Gpu TS Change Request 277 OTSG Cycle 13 for Plant Unit 1.NRC Has Determined That Addl Info Needed to Complete Review ML20199G7401999-01-12012 January 1999 Forwards Insp Rept 50-289/98-08 on 981101-1226.No Violations Noted.Operator Workaround Program Found to Be Acceptable ML20206S0221999-01-0808 January 1999 Responds to Re Changes to Physical Security Plan Identified as Rev 38,submitted Under Provisions of 10CFR50.54(p).Based on NRC Determination,Changes Do Not Decrease Overall Effectiveness of Security Plan 1999-09-30 |
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l)lhE-M6 Mr. Hal B. Tucker DISTRIBUTION BGrimes Gray File B&W Owners Group NRC PDR JPartlow EBrach Executive Committee L PDR WPaulson H0rnstein Duke Power Company PBD-6 Rdg JThoma RConte P. O. Box 33189 FMiraglia JTaylor'(!!&W) 422 South Church Street 0 ELD RIngram Charlotte, North Carolina 28242 EJordan ACRS-10
Dear Mr. Tucker:
SUBJECT:
REPETITIVE LIFTING 0F STEAM SAFETY VALVES During recent planned reactor trips at TMI-1, repetitive lifting of the once through steam generator (OTSG) safety valves occurred. Our understanding of the events at TMI-1 is as follows. During the reactor trips at both 40% and 75% reactor power, there was a pressure surge on the secondary side which caused the OTSG safety valves to lift. This is an expected occurrence.
Following the initial pressure relief via the OTSG safety valves, the secondary pressure should be controlled at 1010 psig by the turbine bypass valve; instead, some of the safety valves relieved pressure several times.
In the case of the A-0TSG, the safety valves relieved pressure three or four times after the initial surge. The operator then manually changed the setting for turbine bypass control from 1010 psig to 975 psig and pressure control was achieved without further safety valve lifts.
At TMI-1, the lowest safety valve setpoint is 1040 psig. It is our understanding that after the initial lift, the safety valve setpoints drift down by about 3 or 4%. As a result of this setpoint drift, the safety valve can lift before the turbine bypass control can achieve pressure control. We understand that other B&W plants have similar experience.
While we view the repetitive lifting of the steam safety valves as an operational concern at this time rather than a significant safety concern, we do not consider repetitive challenges to the safety valves as a normal, acceptable long-term mode of operation. Accordingly, we request that the B&W Owners Group include this issue as a concern requiring appropriate resolution.
Sincerely, Original signud by Trank J. ElPMlia Frank Miraglia, Director Division of PWR Licensing-B Pb@! -
PBD-6 PB ,6
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WPaulson;cr J JS ( FMir lia 1/s/ /86 1/ /86 1/ /86 1/ /86 9601130399 B60107 PDR ADOCK 05000289 9 PDR i
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