Letter Sequence RAI |
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MONTHYEARML20059A5301993-12-21021 December 1993 Forwards Request for Addl Info Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, Per 10CFR50.54(f) for Plant Units 1 & 2 Project stage: RAI ML20063G3181994-02-11011 February 1994 Responds to 931221 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers & NRC Bulletin 92-001, Failure of Thermo-Lag 330 Fire Barrier Sys to Maintain Cabling in Wide Cable Trays & Small Conduits Free from Fire Damage Project stage: Other ML20072P9421994-08-30030 August 1994 Corrects Statement Made to NRC Re Plant Emergency Planning Procedures Contained in 910401 Transmittal to NRC Project stage: Request ML20078H8871994-11-16016 November 1994 Responds to ASLB 941109 Order for Util to Serve Copies of All Relevant Procedures Used at Plant from 1988 to Present & Addl Training Matls Used by Plant.Util Procedures & Telephone Directories Encl Project stage: Request ML20078S7021994-12-19019 December 1994 Submits Response to Request for Addl Info Re GL 92-08, Thermo-Lag Fire Barriers Project stage: Request ML20077P5591994-12-30030 December 1994 Informs That Copies of Georgia Power Co Exhibit 1 for Hearing on Illegal License Transfer Allegation , Were Provided to Board & Parties on 940801 Project stage: Request ML20078F2541995-01-23023 January 1995 Provides Minutes of Overview Committee Meetings Between March 1988-Jan 1991 to Board.W/Certificate of Svc Project stage: Request ML20078N7521995-02-0909 February 1995 Forwards Meeting Minutes of Nuclear Operations Overview Committee of Georgia Power Board of Directors for Period 1991-1994.Informs That Minutes Have Been Redacted to Delete Confidential INPO Evaluation Ratings Project stage: Request ML20081B1361995-03-13013 March 1995 Util Reply to Intervenor Illegal License Transfer Allegation.* Requests That Licensing Board Adopt Util Proposed Findings of Fact & Conclusions of Law.W/Certificate of Svc & Svc List Project stage: Other ML20082B0661995-03-30030 March 1995 Responds to NRC 941230 RAI Re Testing & Properties of Thermo-lag Matls at Plant Project stage: Other ML20083C9811995-04-19019 April 1995 Applicant Exhibit A-20,consisting of Summary of Professional Qualifications for G Beckhold Project stage: Request ML20083L7481995-05-10010 May 1995 Forwards Response to NRC 941230 RAI Re GL 92-08 Concerning Thermo-Lag Fire Barriers Project stage: Other ML20134G6141996-11-0505 November 1996 Submits Progress Rept Concerning Removal of Thermo-Lag Matl Used as Fire Barrier Project stage: Other 1995-01-23
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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 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 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 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 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 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 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 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 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 ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 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 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 ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl 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 ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage 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 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 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 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 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 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 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 ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl 1999-09-20
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G1071999-10-0707 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 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 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 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 ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 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 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 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 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 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 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 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 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 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 ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa 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 ML20207L8281999-03-0808 March 1999 Forwards Partially Withheld Insp Repts 50-424/99-01 & 50-425/99-01 & Notice of Violation ML20207J0431999-03-0303 March 1999 Forwards Insp Repts 50-424/98-10 & 50-425/98-10 on 981227- 990213.No Violations Noted.Licensee Conduct of Activities at Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices ML20203G5691999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam ML20202H9691999-01-29029 January 1999 Forwards Safety Evaluation Authorizing Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant, Unit 1 ML20199J7931999-01-20020 January 1999 Forwards Insp Repts 50-424/98-09 & 50-425/98-09 on 981115-1226 at Vogtle Units 1 & 2.No Violations Were Identified.Conduct of Activities at Vogtle Was Generally Characterized by safety-conscious Operations ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20198S1601998-12-31031 December 1998 Forwards SER of Licensee Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Vogtle Electric Generating Plant Submitted on 970529. INEEL/EXT-98-01007 Rept Also Encl ML20199E4741998-12-23023 December 1998 Provides Summary of 981105 Training Managers Conference Held in Atlanta,Georgia.Conference Agenda,List of Conference Attendees,Presentation Slides & Preliminary Schedule for FY99 & FY00 Encl ML20199J9781998-12-22022 December 1998 Responds to 981209 Meeting Re Installation of Seismic Clips on Cutler Hammer Electrical Circuit Breakers.Forwards List of Attendees & Handouts ML20198F6711998-12-11011 December 1998 Forwards Insp Repts 50-424/98-08 & 425/98-08 on 980927-1114. No Violations Identified ML20198N9431998-12-10010 December 1998 Ack Receipt of Response, to NOV Issued on 980112 Re Surveillance Testing of Reactor Trip Sys P-4 Interlock Feature at Licensee Facility.Nrc Agrees That Surveillance Testing Not Required ML20196J2181998-12-0101 December 1998 Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Historical Listing of Plant Issues Called Plant Issues Matrix & Insp Plan,Including Specific Insps Such as in Security & Radiological Protection Areas Encl ML20196J2581998-12-0101 December 1998 Confirms Arrangements Made Between J Bailey & B Holbrook, Re Info Meeting Scheduled for 990210 to Discuss Licensee Performance,New Initiatives & Other Regulatory Issues Pertaining to Listed Facilities ML20196B1231998-11-23023 November 1998 Confirms Telephone Conversation Between J Bailey & P Skinner on 981120 Re Info Meeting Which Has Been Scheduled for 981209 in Atlanta,Ga,To Discuss Issues Re Seismic Retainer Clips ML20196D4981998-11-13013 November 1998 Informs That on 981007,NRC Administered Gfes of Written Operator Licensing Examination.Copy of Answer Key & Master Bw/Pwr GFE Encl,Even Though Facility Did Not Participate in Exam.Without Encl ML20195B3391998-11-0909 November 1998 Forwards Partially Withheld Insp Repts 50-424/98-12 & 50-425/98-12 on 981005-09 (Ref 10CFR73.21).No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations & Sound Engineering ML20155H2501998-10-21021 October 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-424/98-05 & 50-425/98-05 Issued on 980723.Concluded for Reasons Stated That Example 2 Violation Occurred as Stated in NOV ML20155A7491998-10-15015 October 1998 Forwards Insp Repts 50-424/98-07 & 50-425/98-07 on 980816-0926 & Nov.Insp Generally Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML20155B7771998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference on 981105 in Atlanta,Georgia.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Effect Licensing of Reactor Plant Operators ML20155B4621998-09-25025 September 1998 Discusses OI Investigation Which Completed on 980728. Investigation Reviewed Circumstances Surrounding Apparent Disabling of Fire Computer Trouble Alarm by Unit Shift Supervisor.Concludes Enforcement Discretion Warranted ML20153B0401998-09-17017 September 1998 Responds to 980904 e-mail Message Making Certain Observations Re Apparent Increase in Reactor Trips at Plant, Units 1 & 2.NRC Concluded That Licensee post-trip Reviews Adequately Conducted & That No Adverse Trends,Apparent ML20153B9311998-09-16016 September 1998 Forwards RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations, Responses for Plant,Units 1 & 2 ML20153F7081998-09-11011 September 1998 Provides Summary of 980909 Meeting Held to Discuss TS & Other Regulatory Issues Re Vogtle Electric Generating Plant. List of Meeting Attendees & Copy of Presentation Slides Encl ML20154C4871998-09-10010 September 1998 Forwards Insp Repts 50-424/98-06 & 50-425/98-06 on 980628-0815 & Nov.One Violation Involved Failure to Implement Adequate C/As for Repeated Failures to Enter Applicable TS Limiting Conditions for Operation ML20151U7901998-09-0909 September 1998 Discusses 980615 Request for Exemption from Requirement of 10CFR73.55(e)(1) & (f)(1) to Provide Continuous Staffing of Plant CAS During Contingency Events.Request Denied ML20151S7291998-09-0202 September 1998 Discusses Evaluation of Util Response to GL 97-05 for Plant, Units 1 & 2.NRC Did Not Identify Any Concerns W/Sg Tube Insp Techniques Employed at Plant ML20239A4251998-08-27027 August 1998 Informs of Change Being Implemented by Region II Re Administrative Processing of Licensee Responses to Nov.Nov Responses Will Be Formally Ack as Part of Periodically Issued Integrated Insp Repts 1999-09-01
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Text
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y pu arcvq p
1 1 _E UNITED STATES i I 'f NUCLEAR REGULATORY COMMISSION .l
(*****j# WASHINGTON, D.C. 2055$4001 December 21, 1993 y
Docket Nos. 50-424 l and 50-425 ;
Mr. C. K. McCoy :!
Vice President - Nuclear l Vogtle Project ;
Georgia Power Company
- p. O. Box 1295 :
Birmingham, Alabama 35201 Dear Mr. McCoy-
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-08, i
" THERM 0-LAG 330-1 FIRE BARRIERS," PURSUANT T0 10 CFR 50.54(f) V0GTLE !
ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (TAC NOS. M85619 AND M85620)- j In your response of April 16, 1993, to Generic Letter (GL) 92-08, "Thermo-Lag 330-1 Fire Barriers," you indicated that actions necessary to restore the operability of these barriers at the Vogtle' Electric Generating Plant '(Vogtle) i would be based on the results of the industry test program being coordinated by c the Nuclear Management and Resources Council (NUMARC). During recent meetings :
with the U.S. Nuclear Regulatory Commission (NRC). staff, the Executive Director ~!
for Operations and the Commission, NUMARC described the scope'9f its Thermo-Lag fire barrier program, the results of the Phase 1 fire tests, and planned Phase 2 tests. The-program is limited to certain 1-hour and 3-hour conduit and cable '
tray fire barrier configurations and the development ~ of guidance for applying. ,
the test results to plant-specific fire barrier configurations. However, ,
NUMARC's program is not intended to bound.all in-plant Thermo-Lag fire barrier configurations. During a NUMARC-sponsored industry workshop on December 1 i and 2, 1993, NUMARC presented the scope of its program and the Phase I test results to the licensees.
In view of the limited scope of the NUMAf.C program and the limited success of-the. Phase I tests, it is clear to the NRC staff that the NUMARC program will not ;
be sufficient to resolve all Thermo-Lag fire barrier issues. identified in !
GL 92-08. Therefore, licensees may need to take additional actions to address fire endurance and ampacity derating concerns with their in-plant Thermo-Lag 1 barriers. i To help ensure timely resolution of the fire barrier issues at Vogtle, the NRC I staff requires additional-information on the configurations and amounts of. ,
Thermo-Lag fire barriers installed in the plant and the. cable loadings within .
particular Thermo-Lag configurations- This information is necessary to review NUMARC's guidance for applying the test results to plar.t-specific barrier ..
configurations and to identify configurations that are outside the scope;of -
NUMARC's +est program. For those configurations that are'outside'the scope of .
the program or for those configurations that you deem are impractical to upgrade, we request that you provide plans and schedules for resolving'the g. -
technical . issues identified in GL 92-08.
~
- 200024 g=gggggg;ggg E ME CENTER C8PY P- pogg .
p j Mr. C. K. McCoy You are required, pursuant to Section 182(a) of the Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f), to submit a written report that contains the information specified in the enclosure to this letter within 45 days from receipt of this letter. Your response must be submitted under oath or affirmation. Please submit your response to the undersigned, with a copy to the appropriate Regional Administrator. _ Please retain all information and ,
documentation used to respond to this request on site for future NRC audits or ,
inspections. ,
This request is covered by Office of Management and Budget Clearance Number 3150-0011,. which expires June 30, 1994. The estimated average number of burden hours of 300 person-hours is anticipated to increase by an additional 120 person-hours for each addressee's response, including the time required to assess the requirements for information, search data sources, gather and analyze the data, and prepare the required letters. This revised estimated average ,
number of burden hours pertains only to the identified response-related matters and does not include the time to implement the actions required to comply with :
the app'icable regulations, license conditions, or commitments. Comments on the accuracy of this estimate and suggestions to reduce the h:rden may.be directed to the Office of Information and Regulatory Affairs (315;'-0011), NE0B-3019, Office of Management and Budget, Washington, D.C. 20503, and to the U.S. Nuclear Regulatory Commission, Information and Records Management Branch (MNBB-7714), ,
Division of Information Support Services, Office of Information and Resources Management, Washington, D.C. 20555.
If you have any questions about this matter, please contact C. E. Carpenter at 301-504-1465 or Patrick Madden at 301-504-2854.
Sincerely, Original signed by: +
L. J. Callan Acting Associate Director for Projects Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page DISTRIBUTION Docket File CMcCracken MGamberoni CECarpenter NRC PDR PMadden RIngram, PMSB LGBerry Local PDR CBerlinger LCallan LRPlisco PD 11-3 Rdg RJenkins OGC EPawlik (RIII/01)
SAVarga GMulley (OIG) ACRS (10) GClainas E.Merschoff, RII d\ y } Al 0FFICE LA:PD23:DRPE PM:PD23:DRPE (A)PD:PDU:JRPE (A)ADP, NAME LGBerryh/ /,n CECarpenterj ; LRPlisk[ LJCa N I DATE 12/ 2 / /93 12/ 2/ /93 h 12/ 2 / /93 12/Zl/93' '
0FFICIAL RECORD COPY FILENAME: G:\V0GTLE\V0G85619.LTR ,
v ,
. j Mr. C. K. McCoy Georgia Power Company Vogtle Electric Generating Plant i
CC:
Mr. J. A. Bailey Harold Reheis, Director !
Manager - Licensing Department of Natural Resources '
Georgia Power Company 205 Butler Street, SE. Suite 1252 P. O. Box 1295 Atlanta, Georgia 30334 Birmingham, Alabama 35201 i Attorney General Mr. J. B. Beasley Law Department .
General Manager, Vogtle Electric 132 Judicial Building I Generating Plant Atlanta, Georgia 30334 !
P. O. Box 1600 ,
Waynesboro, Georgia 30830 Mr. Alan R. Herdt i Project Branch #3 ;
Regional Administrator, Region II U. S. Nuclear Regulatory Commission '
U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 -
101 Marietta Street, NW., Suite 2900 Atlanta, Georgia 30323 Atlanta, Georgia 30323 Mr. Dan H. Smith, Vice President I Office of Planning and Budget Power Supply Operations i Room 6158 Oglethorpe Power Corporation ,
270 Washington Street, SW. 2100 East Exchange Place Atlanta, Georgia 30334 Tucker, Georgia 30085-1349 ;
i Office of the County Commissioner Charles A. Patrizia, Esquire :
Burke County Commission Paul, Hastings, Janofsky & Walker ,
Waynesboro, Georgia 30830 12th Floor '
1050 Connecticut Avenue, NW.
Mr. J. D. Woodard Washington, DC 20036 Senior Vice President - ;
Nuclear Operations Arthur H. Domby, Esquire t Georgia Power Company Troutman Sanders P. O. Box 1295 NationsBank Plaza Birmingham, Alabama 35201 600 Peachtree Street, NE. ;
Suite 5200 ;
Atlanta, Georgia 30308-2216 Resident Inspector !
U. S. Nuclear Regulatory Commission i P. O. Box 572 Waynesboro, Georgia 30830 -
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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 92-08 "THERMO-LAG 330-1 FIRE BARRIERS" i PURSUANT TO 10 CFR 50.54(f) i I. Thermo-Lag Fire Barrier Configurations and Amounts A. Discussion i
Generic Letter (GL) 92-08,"Thermo-Lag 330-1 Fire Barriers," applied to all 1-hour and all 3-hour Thermo-Lag 330-1 materials and barrier systems constructed by any assembly method, such as by joining ,
preformed panels and conduit preshapes, and trowel, spray, and !
brush-on applications. This includes all fire barriers, all' ~
barriers to achieve physical independence of electrical systems, ,
radiant energy heat shields, and barriers installed to enclose l intervening combustibles.
B. Required Information
- 1. Describe the Thermo-Lag 330-1 barriers installed in the plant to e
- a. meet 10 CFR 50.48 or Appendix R to 10 CFR Part 50,
- b. support an exemption from Appendix R,
- c. achieve physical independence of electrical systems,
- d. meet a condition'of the plant operating license, ;
- e. satisfy licensing commitments.
The descriptions should include the following information:
the intended purpose and fire rating of the barrier (for example, 3-hour fire barrier, 1-hour fire barrier, radiant energy heat shield), and the type and dimension of the .
barrier (for example, 8-ft by 10-ft wall, 4-ft by 3-ft by 2-ft equipment enclosure, 36-inch-wide cable tray, or 3-inch-diameter conduit).
- 2. For the total population of Thermo-Lag fire barriers ,
descHbed under Item I.B.1, submit an approximation of:
- a. For cable tray barriers: the' total linear feet and '
square feet of 1-hour barriers and the total linear feet and square feet of 3-hour barriers. +
- b. For conduit barriers: the total linear feet of 1-hour barriers and the total linear feet of 3-hour barriers.
- c. For all other fire barriers: the total square feet of 1-hour Darriers and the total square feet of 3-hour barriers. !
- d. For all other barriers and radiant energy heat .
shields: the total linear or square feet of 1-hour
- barriers and the total linear or square feet of 3-hour barriers, as' appropriate for the barrier configuration or type.
GL 92-08 RAI - 2 of 7 - ENCLOSURE II. Important Barrier Parameters A. Discussion In a letter of July 29, 1993, from A. Marion, NUMARC, to C. McCracken, NRC, NUMARC stated: " Relative to bounded configurations, ... (i]t will be the utilities' responsibility to verify their baseline installations are bounded." Furthermore, NUMARC stated that the parameters of importance for utility use of data from the industry Thermo-Lag fire barrier test program are:
- 1. Raceway orientation (horizontal, vertical, radial bends) '
- 2. Conduit
- 3. Junction boxes and lateral bends .
- 4. Ladder-back cable tray with single layer cable fill
- 5. Cable tray with T-Section
- 6. Raceway material (aluminum, steel)
- 7. Support protection, thermal shorts (penetrating elements) >
- 8. Air drops
- 9. Baseline fire barrier panel thickness ,
- 10. Preformed conduit panels
- 11. Panel rib orientation (parallel or perpendicular to the :
raceway) -j
- 12. Unsupported spans
- 13. Stress skin orientation (inside or outside) :
- 14. Stress skin over joints or no stress skin over joints
- 15. Stress skin ties or no stress skin ties -
- 16. Dry-fit, post-buttered joints or prebuttered joints
- 17. Joint gap width i
- 18. Butt joints or grooved and scored joints
- 19. Steel bands or tie wires
- 20. Band / wire spacing
- 21. Band / wire distance to joints j
- 22. No internal bands in trays
- 23. No additional trowel material over sections and joints or additional trowel material applied
- 24. No edge guards or edge guards Each NUMARC cable tray fire test specimen includes 15 percent cable ,
fills (i.e., a single layer of cables uniformly distributed across the bottom of the cable tray). This approach requires consideration of >
plant-specific cable information during the assessments of tested configurations and test results in relation to plant-specific Thermo-Lag configurations; for example, cable trays with less thermal mass (cable fill) than the NUMARC test specimens, different cable types, and the proximity of the cables to the Thermo-Lag (e.g., cables may be installed in contact with the unexposed surface of the i
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GL 92-08 RAI. - 3 of 7 - ENCLOSURE-
[
- Thermo-Lag or may come into contact during a fire if the Thermo-Lag :
material sags). In its letter of July 29, 1993, NUMARC stated:
" Utilities using the results of the NUMARC testing will need to ;
evaluate their installed cable fill and ensure that it is' bounded by <
the tested cable fill." NUMARC is not conducting any cable a functionality tests or evaluations and stated that cable functionality evaluations will be performed by utilities using data from the generic .
program.
The parameters of importance concerning cables protected by fire barriers are:
- 1. Cable size and type (power, control, or instrumentation). ;
- 2. Cable jacket type (thermoplastic, thermoset) and materials. ;
- 3. Cable conductor insulation type (thermoplastic, thermoset :
plastic) and materials.
- 4. Cable fill and distribution of cables within the protected conduit or cable tray. <
- 5. Proximity of cables to the unexposed (inside) surfaces of the e fire barrier. !
- 6. Presence of materials between the cables and the unexposed :
side of the fire barrier material (for example, Sealtemp cloth, which is used in the NUMARC test specimens).
- 7. Cable operating temperature.
- 8. Temperatures at which the cables can no longer perform their .
intended function when energized at rated voltage and current. !
Other parameters that are unique to particular barriers, such as .
interfaces between Thermo-Lag materials and other fire barrier materials or building features (walls, etc.) and internal supports, are also important. In addition, because of questions about the uniformity of the Thermo-Lag fire barrier materials produced over time, NUMARC stated in its letter of July 29, 1993, that "[c]hemical analysis of Thermo-lag materials provided for the program, as well as samples from utility stock, will be performed, and a test report- -
prepared comparing the chemical composition of the respective s ampl es . " The results of the chemical analyses may indicate that variations in the chemical properties of Thermo-Lag are significant l and may require additional plant-specific information in the future.
B. Required Information j
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- 1. State whether or not you have obtained and verified each of '
the aforementioned parameters for each Thermo-Lag barrier installed in the plant. If not, discuss the parameters you have not obtained or verified. Retain detailed information on .
site for NRC audit where the aforementioned parameters are :
known. l
- 2. For any parameter that is not known or has not been verified, describe how you will evaluate the in-plant barrier.for acceptability.
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- 3. To evaluate NUMARC's application guidance, an understanding of the types and extent of the unknown parameters is needed.
Describe the type and extent of the unknown parameters at your .
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plant in this context.
III. Thermo-Lag Fire Barriers Outside the Scope of the NUMARC Program A. Discussion 1
In your response of to GL 92-08, you indicated that actions necessary to restore the operability of these barriers would be based on the results of the NUMARC test program. During recent meetings with the :
NRC staff, the Executive Director for Operations and the Commission, . t NUMARC described the scope of its Thermo-Lag fire barrier program, the
- results of the Phase I fire tests, and planned Phase 2 tests. The program is limited to certain 1-hour and 3-hour conduit and cable tray fire barrier configurations and the development of guidance for applying the test results to plant-specific fire barrier
- configurations. However, NUMARC's program is not intended to bound :
all in-plant Thermo-Lag fire barrier configurations. In view of the i scope of the NUMARC program and the limited success of the Phase 1 tests, it is clear that the NUMARC program will not be sufficient to ;
resolve all Thermo-Lag fire barrier issues identified in GL 92-08, j Therefore, licensees may need to take additional actions to address fire endurance and ampacity derating concerns with in-plant Thermo-Lag ,
barriers. '
P B. Required information
- 1. Describe the barriers discussed under Item I.B.1 that you have determined will not be bounded by the NUMARC test program. :
- 2. Describe the plant-specific corrective action program or plan you expect to use to evaluate the fire barrier configurations .
particular to the plant. This description should include a discussion of the evaluations and tests being considered to resolve the fire barrier issues identified in GL 92-08 and to demonstrate the adequacy of existing in-plant barriers.
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- 3. If a plant-specific fire endurance test program is i anticipated, describe the following: 1
- a. Anticipated test specimens.
- b. Test methodology and acceptance criteria including cable functionality.
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GL 92-08 RAI 5 of 7 - ENCLOSURE IV. Ampacity Derating A. Discussion !
NUMARC has informed the staff that it intends to use the Texas i Utilities (TV) Electric Company and Tennessee Valley Authority (TVA)-
ampacity derating test results to develop an electrical raceway component model for the industry. Additicnal information is needed to determine whether or not your Thermo-Lag barrier configurations (to protect the safe-shutdown capability from fire or to achieve physical independence of electrical systems) are within the scope of the NUMARC program and, if not, how the in-plant barriers will be evaluated for j the ampacity derating concerns identified in GL 92-08.
B. Required Information
- 1. For the barriers described under Item I.B.1, describe those that you have determined will fall within the scope of the NUMARC program for ampacity derating, those that will not be- :
bounded by the NUMARC program, and those for which ampacity derating does not apply.
- 2. For the barriers you have determirad fall within the scope of the NUMARC program, describe what additional testing or evaluation you will need to perform to derive valid ampacity derating factors. j l
- 3. For the barrier configurations that you have determined will not be bounded by the NUMARC test program, describe your plan for evaluating whether or not the ampacity derating tests j relied upon for the ampacity derating factors used for those 1 electrical components protected by Thermo-Lag 330-1 (for i protecting the safe-shutdown capability from fire or to )
achieve physical independence of electrical systems) are i correct and applicable to the plant design. Describe all corrective actions needed and submit the schedule for completing such actions. ;
- 4. In the event that the NUMARC fire barrier tests indicate the need to upgrade existing in-plant barriers or to replace existing Thermo-Lag barriers with another fire barrier system, describe the alternative actions you will take (and the schedule for performing those actions) to confirm that the ;
ampacity derating factors were derived by valid tests and are !
applicable to the modified plant design.
Your response to Section IV.B may depend on unknown specifics of the 1 NUMARC ampacity derating test program (for example, the final barrier l upgrades). However, your response should be as complete as possible. ,
in addition, your response should be updated as additional information becomes available on the NUMARC program.
r GL 92-08 RAI - 6 of 7 - ENCLOSURE V. Al ternatives A. Discussion t
On the basis of testing of Thermo-Lag fire barriers to date, it is not clear that generic upgrades (using additional Thermo-Lag materials) -
can be developed for many 3-hour barrier configurations or for some 1-hour barriers (for example,1-hour barriers on wide cable trays, with post-buttered joints and no internal supports). Moreover, some upgrades that rely on additional thicknesses of Thermo-Lag material (or other fire barrier materials) may not be practical due to the effects of ampacity derating or clearance problems.
B. Required Information Describe the specific alternatives available to you for achieving compliance with NRC fire protection requirements in plant areas that contain Thermo-Lag fire barriers. Examples of possible alternatives to Thermo-Lag-based upgrades include the following:
- 1. Upgrade existing in-plant barriers using other materials.
- 2. Replace Thermo-Lag barriers with other fire barrier materials or systems.
- 3. Reroute cables or relocate other protected components.
- 4. Qualify 3-hour barriers as 1-hour barriers and install detection and suppression systems to satisfy NRC fire protection requirements.
VI. Schedules A. Discussion The staff expects the licensees to resolve the Thermo-Lag fire barrier issues identified in GL 92-08 or to propose alternative fire protection measures to be implemented to bring plants into compliance with NRC fire protection requirements. Specifically, as test data hecomes available, licensees should begin upgrades for Thermo-Lag barrier configurations bounded by the test results.
B. Required Information Submit an integrated schedule that addresses the overall corrective action schedule for the plant. At a minimum, the schedule should address the following aspects for the plant:
- 1. implementation and completion of corrective actions and fire barrier upgrades for fire barrier configurations within the scope of the NUMARC program,
y GL 92-08 RAI - 7 of 7 - ENCLOSURE
- 2. implementation and completion of plant-specific analyses, testing, or alternative actions for fire barriers outside the scope of the NUMARC program.
VII. Sources and Correctness of Information Describe the sources of the information provided in response to this request for information (for example, from plant drawings, quality assurance documentation, walk downs or inspections) and how the accuracy and validity of the information was verified.