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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 ML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area 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 ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections 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 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 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 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 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 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 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 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 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 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 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station 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 ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant 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 ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V 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 ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl 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 ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 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 ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area 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 ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 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 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058H9421990-11-16016 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facility,Per Generic Ltr 90-04 ML20062E7811990-11-14014 November 1990 Forwards Summary of NRC Understanding of Current Status of Unimplemented Generic Safety Issues at Plant,Per Generic Ltr 90-04 ML20058J0451990-11-0909 November 1990 Forwards Insp Rept 50-219/90-20 on 901022-26.No Violations Noted.Review of Preparations for Drywell Occupancy During Fuel Movement Identified Areas of Concern 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 ML20058C7291990-10-24024 October 1990 Discusses Insp Rept 50-219/90-80 on 900625 & 29 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Violation Considered Severity Level III & Involved Unqualified Operators at Reactor Controls ML20058A6091990-10-19019 October 1990 Forwards Safety Insp Repts 50-289/90-15 & 50-320/90-08 on 900807-0921 & Notice of Violation ML20058A6381990-10-18018 October 1990 Forwards SE Conditionally Accepting Util Insp & Repairs for Igscc,Per Generic Ltr 88-01 ML20058A8241990-10-18018 October 1990 Forwards Safety Insp Rept 50-219/90-16 on 900823-0922 & Notice of Violation IR 05000219/19890811990-10-18018 October 1990 Ack Receipt of Informing NRC of Actions Taken to Correct Violations Noted in AIT Insp Rept 50-219/89-81 Re RPS Low Vacuum Setting 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 ML20058A6601990-10-16016 October 1990 Forwards Request for Addl Info Re Drywell Corrosion Program, Including Sampling of Shell Surfaces for UT Measurements ML20058A9861990-10-15015 October 1990 Discusses Review Approving Rev 23 to Organization Plan Submitted in Conjunction W/Tech Spec Change Request 65 ML20062B8641990-10-12012 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 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 ML20062A6871990-10-11011 October 1990 Documents Review of Util 900921 Integrated Schedule ABC List Update.Listed Projects Acceptable Except for Items B/A-328 ADA & B/A-402946 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 ML20058F3211990-10-0303 October 1990 Forwards Safety Insp Rept 50-219/90-17 on 900918-21.No Violations Noted.Schedule for Identification & Disposal of Contents of Tanks in Old Radwaste Bldg Requested within 45 Days of Ltr Date IR 05000219/19900091990-10-0101 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/90-09 ML20059M5201990-09-21021 September 1990 Forwards Safeguards Insp Rept 50-219/90-15 on 900820-24.No Violations Noted ML20059H1491990-09-12012 September 1990 Ack Receipt of & Payment in Amount of $50,000 for Civil Penalty Proposed by NRC ML20059J8021990-09-11011 September 1990 Advises That Util 900621 Response to Open Item Re USI A-46 & Schedule,Acceptable.Requests That Util Confirm Seismic Adequacy of CRD Hydraulic Control Units within 30 Days of Completion of Walkdown ML20059H3291990-09-0606 September 1990 Advises That 900831 Commitment to Install Hardened Wetwell Vent at Plant Acceptable ML20059G3911990-09-0505 September 1990 Recognizes Efforts of G Bond & W Douglas Re Implementation of Emergency Response Data Sys (ERDS) Link at Facility. ERDS Link at Facility Operational & Should Be Implemented in Emergency Response Planning 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 ML20058Q4361990-08-15015 August 1990 Forwards Safety Insp Rept 50-219/90-11 on 900610-0711. Unresolved Item Noted 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 ML20058P0801990-08-0909 August 1990 Forwards Requalification Program Evaluation Rept 50-219/90-05OL on 900409-0608.Util Should Respond within 30 Days of Receipt of Ltr Confirming Corrective Actions Committed to During 900424 Interim Exit Meeting ML20058M3581990-08-0808 August 1990 Requests Addl Info Listed in Encl Re Util 900521 & 0720 Responses to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Info Requested within 10 Days of Receipt of Ltr 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 ML20056A6071990-07-20020 July 1990 Forwards Insp Rept 50-219/90-09 on 900422-0609 & Notice of Violation.Util Should Identify & Correct Any Programmatic Weaknesses Re Failure to Perform Adequate Radiation Surveys ML20055G4141990-07-11011 July 1990 Requests Util Provide Ref Matls Listed in Encl for Senior Reactor Operator Licensing & Requalification Exams Scheduled for 901015 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 ML20058K5061990-06-28028 June 1990 Forwards Supplemental Safety Evaluation for Plant Dcrdr. NRC Concludes That Licensee Submittal Meets NUREG-0737, Suppl 1 Dcrdr Requirements & Therefore,Issue Considered Resolved 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 ML20055E3021990-06-15015 June 1990 Forwards Backfit Analyses for Plant Re Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 ML20059M8321990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20055C3171990-02-16016 February 1990 Forwards Safety Insp Rept 50-219/89-29 on 891203-900106 & Ack Receipt of 900115 & 19 Responses to Insp Repts 50-219/89-21 & 50-219/89-27 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
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 ML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area 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 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 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 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 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 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 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 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 ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20212J0011999-09-27027 September 1999 Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl 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 ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area 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 ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 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 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) 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 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 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 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 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 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 ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against 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 ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart 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 1999-09-30
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i JUN 181996 Docket No. 50-219 GPU Nuclear Corporation ATTN: Mr. P. B. Fiedler Vice President and Director Oyster Creek Nuclear Generating Station P. O. Box 388 Forked River, NJ 08731 Gentlemen:
Subject: Combined Inspection Report Nos. 50-219/86-15 and 50-289/86-08 This refers to the routine safety inspection conducted by Mr. G. Napuda of this office on April 30 - May 2, 1986, at your Parsippany, New Jersey Corporate offices, of activities authorized by NRC License No. DPR-16 and to the dis-cussions of our findings held by Mr. Napuda with Mr. I. Finfrock at the conclusion of the inspectio Areas examined during this inspection are described in the NRC Region I Inspection Report which is enclosed with this letter. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspecto Within the scope of this inspection, no violations were observe No reply to this letter is require Your cooperation with us in this matter is appreciate
Sincerely, Original Signed By:
Lee H. Bettenhausen
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Stewart D. Ebneter, Director
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Division of Reactor Safety
Enclosure:
Combined Inspection Report Nos. 50-219/86-15; and 50-289/86-08
REGION I==
Report No /86-15 50-289/86-08 Docket No License Nos. DPR-16 DPR-50 Category C a
Licensee: GPU Nuclear Corporation 100 Interpace Parkway Parsippany, New Jersey 07054 GPU Nuclear Corporation Post Office Box 480
. Middletown, Pennsylvania 17057 Facility Names: Oyster Creek Nucinr Generatino Station Three Mile Island Nuclear Station, Unitj Inspection At: Parsippany, New Jersey Inspection Conducted: April 30 - May 2, 1986 Inspector:
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G'.fapoda,LeadReactorEngineer da'te Approved by:
Dr. P. K. Eapen, hief h37/76
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- Quality Assurance Section, OB, DRS
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Inspection Summary: Routine announced inspection on April 30-May 2, 1986 (CombinedReportNos. 50-219/86-15; 50-289/86-08)
Areas Inspected: Independent safety reviews and overviews by the General Office
Review Board (G0RB), audits and previously identified items by one region-based inspecto Results: No violations were identifie e i
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DETAILS ,
1.0 Persons Contacted GPU Nuclear Corporation
- Finfrock, Jr., Chairman General Office Review Boards (G0RBs)
i R. Markowski, QA Program Development / Audit Manager R. Whitesel, Vice Chairman GORBs i Other licensee administrative and technical persennel were also contacted during the inspection.
- * Denotes those present at the exit meeting held May 2, 1986
, Previously Identified Items (0 pen) Violation (289/85-27-07). Failure to properly implement the onsite independent safety review proces l Based on the review of the status of the corrective action and program
- implementation discussed in paragraph 4.0 this item remains open pending further review of program implementatio ' Offsite Independent Review 3.1 Program A General Office Review Board (GORB) has been established for the Oyster Creek (OC) Station and another for Three Mile Island, Unit 1 (TMI-1). The primary responsibility of the GORB is to independently i consider potentially significant nuclear and radiation matters in-cluding related management aspects of those matters. A secondary responsibility to consider potentially significant industrial safety
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matter The GORBs provide advice and report directly to the Office 1 of the President. The GORB makes written recommendations to the
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Chief Operating Officer or appropriate Vice President and requires
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written responses by the addressees.
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The documents listed in Attachment A were reviewed to determine the following had been accomplishe Procedures were established in accordance with regulatory requirements and licensee commitment The organization was structured and staffed to meet QA Program requirement Organizational independence existed and interfaces were delineated.
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Appropriate. responsibilities were established and assigned.
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Procedures were established for the control of GORB activities; 1
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Provisions were established to assure that records are properly maintained and transferred to a storage facility;
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Administrative controls and human resources were established to
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support the required organizational responsibilities;
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Provisions were established to assure that GORB receives infor-j mation and intelligence gathering resource materials upon which
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to base its reviews and activitie .2 Organization and Staffing ;
Each GORB has eleven members including the Chairman and Vice Chair-man. One but not more than two members are from the operating organization, one from the engineering organization and five from outside the General Public Utilities (GPU) employee group. Admi-nistrative and technical resources are provided by the Nuclear Safety Assessment Department (NSAD). The collective expertise of each GORB includes nuclear station design, nuclear power plant operation, materials, engineering (nuclear, mechanical, electrical), instrumen-tation and controis, quality assurance, training and human factor analysis, safety analysis and accident control, radiation safety, metallurgy, chemistry and radiochemistry. The four permanent GORB major issue committees that have been established are Risk and
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Control Process, Human Factors, Hardware and Radcon, and Modifica-tions and Maintenanc .3 Implementation and Findings i
GORB meeting minutes between November 1984 to March 1986 (Nos. 105-113) and December 1984 to April 1986 (Nos. 62-70) for OC and TMI-1 respectively were reviewed and the following were note GORB met every second month;
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Meetings were held onsite and lasted a minimum of two days;
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Presentations were given by the plant Review Group, Independent Onsite Safety Review Group, GORB committees and Quality Assurance;
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Subjects reviewed and discussed included Licensee Event Reports, Technical Specification changes, response to NRC IE inspection
- reports, industrial safety, plant status, outage schedule, Ap-
- pendix R modifications, non-licensed training, reliability and
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risk assessments, and QA audit adverse findings and responses; i
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Recommendations and Action Items were discussed at each meeting, documented, and tracked through close out;
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Meeting minutes were formatted to the standard agenda;
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The Chairman of the GPU Board of Oirectors and board members observed a number of GORB meetings and on occasion attended the full two day sessions;
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GORB members had extensive experience and most held post gra-j duate university degrees;
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Recommendations were well formulated, received prompt attention j and close out actions were adequate (random samples);
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GORB was persistent in pursuit of the satisfactory close out of their item No violations were identifie , Nuclear Safety Assessment The independent technical and safety review of procedures and other deve-loped documents (e.g. modifications, specifications, Technical Specifica-tion changes) are performed by individuals in a pool of reviewers. Master matrices contain the names of qualified technical and independent safety reviewers at both stations and the corporate office Each organization division has a Technical Review Coordinator who assigns the reviews to individuals selected from the matrices. The technical reviewer may be from the same division as the originator but the independent safety review-
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er must be from another division.
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A review of the limited amount of work accomplished since recent revisions to implementing procedures (see paragraph 2) indicated the following- .
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A bi-monthly report was transmitted to the NSAD Director; i --
The Independent Onsite Safety Review Group (ISORG) has had no recent recommendations;
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The ISORG reviewed TS Change Request No. 112 and " signed off" the !
cover sheet;
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The annual review cycle for the review of trends in functional area performance is not yet du l No items violations were identifie l l
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j Audits Audit packages S-0C-83-13, Safety Review; S-TMI-86-04, TMI-I Safety
- Review (a draft); and 0-0C-85-04, Safety Review Program were reviewed and i
verified that:
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The audits were conducted in accordance with a written checklist
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covering the scoped audit area;
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The audits were conducted by qualified / trained personnel independent
- of the authority over the area audited; i
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The identified deficiencies were documented and reviewed; i
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Corrective action followup was adequate and timely;
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Audit frequency and general audit conduct were in accordance with the
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established schedule and procedure No violations were identifie . Management Meetings Licensee management was informed of the scope and purpose of the inspec-
) tion at the entrance interview on April 30, 198 The findings of the i inspection were discussed with licensee representatives during the course
{ of the inspection and presented to licensee management at the May 2,1986
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exit interview (see paragraph I for attendees).
At no time during the inspection was written material provided to the licensee by the inspectors.
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ATTACHMENT A Documents Reviewed General Office Review Boards (GORBs) Responsibility, Authority, Organization and Resources, Revision 2 GORBs Administrative Procedures, Revision 2 6310-ADM-1010.01, Independent Onsite Safety Review Group Procedure-TMI-1, Revision 4 Resumes of GORB members GPU Review and Approval Matrix GPU Nuclear Corporate Policy and Procedures Manual,1000-PLN-1291.01 GPU Nuclear and Radiation Safety Plan, Revision 0-00
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GPU Nuclear Corporation 2
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cc w/ encl:
R. J. Toole, Operations and Maintenance Director, TMI-1 C. W. Smyth, Manager, TMI-1 Licensing R. J. McGoey, Manager, PWR Licensing E. L. Blake, Jr., Esquire TMI-1 Hearing Service List Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania l
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