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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217D2901999-10-13013 October 1999 Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G2631999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted ML20217G0401999-10-0707 October 1999 Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20216G0251999-09-24024 September 1999 Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant ML20216H3641999-09-20020 September 1999 Forwards NRC Form 536 in Response to AL 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted HL-5839, Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-5731999-09-16016 September 1999 Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-573 ML20212A6411999-09-13013 September 1999 Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program HL-5837, Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification1999-09-13013 September 1999 Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl HL-5832, Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC1999-09-0101 September 1999 Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant HL-5825, Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations1999-08-20020 August 1999 Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations HL-5788, Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 141999-08-19019 August 1999 Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 14 HL-5827, Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d)1999-08-19019 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d) HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.111999-08-18018 August 1999 Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11 ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-5281999-07-30030 July 1999 Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528 05000366/LER-1999-007, Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown1999-07-27027 July 1999 Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20210E1601999-07-20020 July 1999 Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage1999-07-15015 July 1999 Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions1999-07-15015 July 1999 Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy 1999-09-24
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G6171990-11-19019 November 1990 Forwards Insp Repts 50-321/90-22 & 50-366/90-22 on 901015- 19.No Violations or Deviations Noted ML20062F8171990-11-14014 November 1990 Forwards Insp Repts 50-321/90-20 & 50-366/90-20 on 900915- 1020 & Notice of Violation ML20217A2921990-11-13013 November 1990 Advises That Kn Jabbour Assigned as Project Manager for Plant ML20058H8421990-11-13013 November 1990 Forwards Insp Repts 50-321/90-21 & 50-366/90-21 on 901001- 05.No Violations or Deviations Noted ML20217A7441990-11-0707 November 1990 Forwards Insp Repts 50-321/90-16 & 50-366/90-16 on 901001-12.No Violations or Deviations Noted ML20058E8811990-10-29029 October 1990 Forwards Insp Repts 50-424/90-27 & 50-425/90-27 on 901016-17.Violations Noted ML20058F6541990-10-25025 October 1990 Forwards Insp Repts 50-424/90-20 & 50-425/90-20 on 900825- 0928 & Notice of Violation ML20058E8491990-10-23023 October 1990 Forwards Insp Repts 50-321/90-19 & 50-366/90-19 on 900925-28.No Violations or Deviations Noted ML20058E8451990-10-23023 October 1990 Advises That Rev 12 & Proposed Rev 13 to Plant Emergency Plan Appear to Be Inconsistent w/10CFR50.47(b).Changes Should Not Be Implemented Until Addl Justification Provided Per Encl ML20058F0351990-10-19019 October 1990 Forwards Insp Repts 50-424/90-26 & 50-425/90-26 on 901009-12.Noncited Violation Noted ML20062B2631990-10-12012 October 1990 Requests That Analyses of Liquid Samples Spikes W/ Radionuclides Be Completed as Soon as Practicable,But No Later than 60 Days from Receipt of Samples.Results Should Be Sent to DM Collins at Listed Address ML20062B2461990-10-12012 October 1990 Requests That Analyses of Liquid Samples Spiked W/ Radionuclides Be Completed as Soon as Practicable,But No Later than 60 Days from Receipt of Samples.Results Should Be Sent to DM Collins at Listed Address ML20058A3431990-10-0505 October 1990 Ack Receipt of 900925 Response to Notice of Violation in Insp Repts 50-424/90-15 & 50-425/90-15 ML20062A8951990-10-0404 October 1990 Confirms 901003 Telcon Granting Regional Waiver of Compliance from Tech Specs 3.6.1.1,3.6.1.2 & 3.6.3 ML20062E9091990-10-0303 October 1990 Discusses NRC Operator Requalification Exam Process ML20059M7861990-09-20020 September 1990 Forwards Insp Repts 50-424/90-17 & 50-425/90-17 on 900630-0824.No Violations or Deviations Noted.Attention to Unresolved Item Identified in Insp Rept Requested ML20059K4471990-09-17017 September 1990 Advises That Ds Hood Assigned as Project Manager for Plant ML20059H1441990-09-12012 September 1990 Ack Receipt of & Payment in Amount of $50,000 for Civil Penalties Imposed by NRC in ML20059J9151990-09-0707 September 1990 Forwards Guidance for Reporting of Events Under Requirements of 10CFR50.73.W/o Encl ML20059K1071990-09-0505 September 1990 Requests Listed Info in Preparation for Reactor & Senior Operator Exams Scheduled for 901210.Preliminary License Applications Should Be Submitted at Least 30 Days Prior to Exam in Order to Review Training & Experience of Candidates ML20059E9091990-08-31031 August 1990 Forwards Exemption from Restriction of 10CFR20,App a, Footnote d-2(c) & Grants Authorization for Use of Solvent Iodine Canisters at Facility,Per 890928 Request.Safety Evaluation Also Encl ML20059H3311990-08-29029 August 1990 Forwards Insp Repts 50-424/90-15 & 50-425/90-15 on 900730- 0803 & Notice of Violation ML20059C9111990-08-23023 August 1990 Forwards Requalification Exam Rept 50-424/OL-90-03 During Wks of 900723 & 900730 ML20058M3561990-08-0808 August 1990 Discusses Util Response to Generic Ltr 89-10, Safety- Related Motor-Operated Valve (MOV) Testing & Surveillance. Recommends That Licensees Test MOVs in Situ Under Design Basis Conditions ML20058L5031990-08-0303 August 1990 Advises That 900727 Response to Generic Ltr 88-14 Re Instrument Air Supply Sys Problems Affecting safety-related Equipment,Acceptable ML20058L6731990-07-26026 July 1990 Forwards Insp Repts 50-424/90-16 & 50-425/90-16 on 900709-13.Violations Noted But Not Cited ML20055H3581990-07-23023 July 1990 Advises That Util Provided Acceptable Resolution to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs ML20056A4991990-07-23023 July 1990 Ack Receipt of 900712 Response to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10 ML20058L7081990-07-23023 July 1990 Forwards Insp Repts 50-424/90-13 & 50-425/90-13 on 900519- 0629.Violations Noted But Not Cited ML20055H6451990-07-13013 July 1990 Forwards Insp Repts 50-321/90-14 & 50-366/90-14 on 900512-0622.No Violations or Deviations Noted ML20055E8841990-07-10010 July 1990 Advises That EAS-28-0589, Edwin I Hatch Nuclear Plant Basis for Use of Homogeneous Equilibrium Model for Environ Qualification & Radiological Release Evaluation, Withheld from Public Disclosure (Ref 10CFR2.790),per 900628 Request ML20055H6071990-07-0606 July 1990 Forwards Insp Repts 50-424/90-14 & 50-425/90-14 on 900611-15.No Violations or Deviations Noted ML20055H3981990-06-29029 June 1990 Ack Receipt of 900525 & 0608 Ltrs Forwarding Objectives & Scenarios for Emergency Exercise Scheduled for Wk of 900730 IR 05000424/19900111990-06-27027 June 1990 Discusses Insp Repts 50-424/90-11 & 50-425/90-11 on 900430-0501 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Insp Reviewed Incident Re Unsecured Cabinet W/Safeguards Info ML20055D5481990-06-25025 June 1990 Advises That 890711 Response to Generic Ltr 89-08, Erosion/ Corrosion Induced Pipe Wall Thinning, Acceptable ML20055H3451990-06-21021 June 1990 Responds to Re Basis for Employment Action Involving Former Util Employee Reporting Safety Concerns. Concurs W/Request to Defer Further Discussion Until Completion of Dept of Labor Process ML20059M9561990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055F7111990-06-12012 June 1990 Advises That Util 900315 Response Adequately Addresses Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 'Safety Implication of Control Sys in LWR Nuclear Power Plants' & Provides Sufficient Basis for Closure of Review ML20055D0021990-06-11011 June 1990 Discusses Util 900514 Application for Amend to License NPF-47,increasing Suppression Pool Temp from 95 F to 100 F. Requests That Util Demonstrate Applicability of Items Addressed in Encl Hatch Safety Evaluation to Facility ML20055G0231990-06-11011 June 1990 Advises That Util 890113,0331,1106 & 900328 Responses to NRC Bulletin 88-010 & Suppl 1, Non-Conforming Molded-Case Circuit Breakers Adequately Addresses Bulletin Requirements ML20055C5131990-05-17017 May 1990 Authorizes Restart of Facility When Identified Flaws in Welds Repaired W/Overlay Designs,Per Util & Generic Ltr 88-01.Full Rept of outage-related Insp Activities Should Be Submitted Following Restart ML20055C4771990-05-11011 May 1990 Forwards Insp Repts 50-321/90-13 & 50-366/90-13 on 900430-0504.No Violations or Deviations Noted ML20248D1821989-09-20020 September 1989 Forwards Insp Repts 50-321/89-16 & 50-366/89-16 on 890722- 0825.Violations Noted But Not Cited Since All Criteria of licensee-identified Violations Met ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248D1111989-09-20020 September 1989 Ack Receipt of 890830 Response to Violations Noted in Insp Repts 50-424/89-19 & 50-425/89-23 ML20247P4401989-09-18018 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-424/89-20 & 50-425/89-20 IR 05000424/19890221989-09-18018 September 1989 Forwards Insp Repts 50-424/89-22 & 50-425/89-26 on 890708- 0818 & Notice of Violation ML20247M1891989-09-12012 September 1989 Forwards Partially Withheld Insp Repts 50-424/89-23 & 50-425/89-27 on 890731-0803 & Notice of Violation.Notice Withheld (Ref 10CFR2.790(d) & 10CFR73.21) ML20247C9281989-09-0606 September 1989 Forwards Exam Rept 50-321/OL-89-01 Administered on 890612-16.Concerns Raised Re pre-exam Review Ineffective in Ensuring site-specific Exam Validity & Operator Generic Weaknesses ML20247B3931989-09-0505 September 1989 Forwards Insp Repts 50-321/89-17 & 50-366/89-17 on 890612-16 & 0731-0804.No Violations or Deviations Noted 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D2901999-10-13013 October 1999 Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G2631999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted ML20217G0401999-10-0707 October 1999 Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20216G0251999-09-24024 September 1999 Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted ML20212A6411999-09-13013 September 1999 Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210E1601999-07-20020 July 1999 Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209E4801999-06-30030 June 1999 Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101 ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20196H8811999-06-25025 June 1999 Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207E7561999-06-0303 June 1999 Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206Q0751999-05-0606 May 1999 Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted ML20206G1611999-05-0404 May 1999 Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii) ML20206P6921999-04-27027 April 1999 Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T1831999-04-0909 April 1999 Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205M3181999-04-0707 April 1999 Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999 ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20205M3011999-04-0202 April 1999 Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified ML20205D3211999-03-24024 March 1999 Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25 ML20205B9601999-03-24024 March 1999 Seventh Partial Response to FOIA Request for Documents. Records in App N Already Available in Pdr.App O Records Being Released in Entirety & App P Records Being Withheld in Part (Ref FOIA Exemptions 7C,2 & 5) ML20205A2771999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Vogtle PPR on 990208.PPR for Plant Involved Participation of All Technical Divs in Evaluating Insp Results & Safety Performance Info for Period of Dec 1997 - Jan 1999 ML20205A2991999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Hatch PPR on 990202.PPR Involved Participation of All Technical Divs in Evaluating Insp Results & Safety Performance Info for Period of Feb 1997 - Jan 1999.Insp Plan for Future Encl ML20204E6601999-03-11011 March 1999 Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned ML20207M1771999-03-11011 March 1999 Forwards SE Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Welds 1999-09-24
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UNITED STATES
, ' [OR M Ggo, NUCLEAR REGULATORY COMMISSION
[ ,,
REGloN il 5 g 101 M ARIETTA STREET. N.W.
' 8 ATLANTA. GEoRGtA 30303
- .* NOV In Reply-Refer To:- 3 1973 j RII:SCEwald -~
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Georgia Power Company ATTN: Mr. John H. Miller, Jr.
Executive Vice President 270 Peachtree Street, N.W.
Atlanta, Georgia 30303 Gentlemen: I I
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t The U.S. Nuclear Regulatory Commission will conduct a one-day seminar in Atlanta on December 5,1978, to discuss new Model Radiological Effluent Technical Specifications for Nuclear Power Plants. Representatives from the Office of Nuclear Reactor Regulation will make presentations on background, development, and implementation of the effluent technical specifications and will discuss the major changes from existing specifi-cations. A question and answer period will follow the prepared presentations.
All utilities which hold operating licenses or have applied for licenses to operate nuclear power reactors are invited to attend. We encourage you to send those members of your staff most closely involved in your radiological effluent program. Information on time, location, accommoda-tions, and an attendance registration form are enclosed. A copy of the agenda is also enclosed.
If you have questions beyond the scope of the agenda, please submit them
( with your registration foms so that the speakers will be able to provide answers to those questions that apply to the entire audience. We will attempt to answer any questions pertaining to radiological effluents and environmental monitoring; however, if the problem is only specific to your case and not of general interest to the entire audience, we will communicate with you directly, rather than at this seminar.
Sincerely, i
af. o- -
mes P. O'Reilly
- C Di ctor Enclosures.
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Seminar Information Sheet Registration Form Proposed Agenda g
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4 Georgia Power Company DV g 7979 cc w/ enclosures:
Mr. M. Manry, Plant Manager l Plant E. I. Hatch i Post Office Box 442 Baxley, Georgia 31513 !
Mr. W. M. Johnston Project Construction Manager Vogtle Nuclear Plant Post Office Box 282 Waynesboro, Georgia 30830 1
Mr. E. D. Grover
,^
QA Site Supervisor Vogtle Nuclear Plant Post Office Box 282 .
F
(. Waynesboro, Georgia 30830 I
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- j SEMINAR INFORMATION SHEET SUBJECT Model Radiological Effluent Technical Specifications and Environmental Monitoring '
i DATE l
December 5, 1978 TIME 8:00 a.m. to 5:00 p.m. j LOCATION
( Stadium Hotel, Braves Room 450 Capitol Avenue, S.E.
Atlanta, Georgia 30312 TRANSPORTATION Limousine service to and from the Atlanta airport is available.
ACCOMMODATIONS '
A number of rooms have been set aside for seminar participants at the Stadium Hotel for the night of December 4, 197b. Rates for seminar participants are $20.00 per night (single), and $26.00 per night (double),
plus 4% sales tax. Reservations are the responsibility of the attendee (s) and should be made no later than November 22, 1978.
( LUNCHEON A buffet luncheon has been arranged for participants at a charge of
$6.00 per person (includes tax and gratuity). In addition, coffee will be served during morning and afternoon breaks at a charge of $1.00 per person. Money for lunch and coffee will be collected during registrat2on on December 5.
lI NRC CONTACT S. C. Ewald 404/221-4181
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l 4 SEMINAR REGISTRATION '
i
! Please submit the following information for each representative planning i to attend:
l
.'1 NAME i
! TITLE i.
1 4
REPRESENTING
] .
1 Do you plan to take advantage of:
(
LUNCHEON (S6.00) Yes: No: 1
! C0FFEE SERVICE ($1.00) Yes:
i No:
i i
I l To assist us in making preparations for the seminar, please return all l registration forms by November 27, 1978, to:
i j S. C. Ewald i(
i U.S. Nuclear Regulatory Commission Region II 101 Marietta Street l 1 Suite 3100 i
) Atlanta, Georgia 30303 i
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AGENDA FOR REGIONAL SEMINAR ON RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS I
I. INTRODUCTION AND BACKGROUND A. Standard Technical Specifications B. Appendix A vs. Appendix B C. Implementation of Appropriate Regulations
- 1. 10 CFR Part 20
- 2. 10 CFR Part 50
- 3. 40 CFR Part 190 II. SCHEDULE FOR IMPLEMENTATION
( A. OL Applications B. Operating Reactors III. IhTERFACES WITH NRR IV. DEVELOPMEhT OF STANDARD TECHNICAL SPECIFICATIONS A. NRC Task-Force B. AIF Task Foreg C. Approval by R C D. Deviations from Standard Technical Specifications V. METHOD OF IMPLEMENTATION A. Amendment to Operating License B. Amendment to FSAR VI. MAJOR CHANGES FROM PRESENT TECHNICAL SPECIFICATIONS A. 10 CFR Part 50, Appendix I B. 40 CFR Part 190 C. Maintenance and Use of Equipment D. Solidification - Process Control Program E. Special Reports (40 CFR Part 141)
F. Environmental Monitoring VII. DISCUSSION OF NUREG-0133 i i
VIII. DISCUSSION OF TECHNICAL SPECIFIC /.TIONS A. LCO !
B. Action C. Surveillance !
IX. QUESTION AND ANSWER' PERIOD I