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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:INCOMING CORRESPONDENCE
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 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 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 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 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 ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl 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 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 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 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 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 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 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 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 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 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 ML20205H4051999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3891999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included ML20205A9441999-03-25025 March 1999 Forwards VEGP Unit 1 Cycle 9 Colr,Per TS 5.6.5.d ML20205H3811999-03-24024 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3621999-03-22022 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81, as Requested IAW 10CFR50.75(f)(1) ML20204G4361999-03-18018 March 1999 Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Vegp,Iaw Requirements of 10CFR50.54(w)(3) ML20204C0591999-03-17017 March 1999 Forwards Rev 0 to WCAP-15160, Evaluation of Pressurized Thermal Shock for Vegp,Unit 2 & Rev 0 to WCAP-15159, Analysis of Capsule X from Vegp,Unit 2 Reactor Vessel Radiation Surveillance Program ML20207K9551999-03-11011 March 1999 Forwards Response to Rai,Pertaining to Positive Alcohol Test of Licensed Operator.Encl Info Provided for NRC Use in Evaluation of Fitness for Duty Occurrence.Encl Withheld,Per 10CFR2.790(a)(6) ML20207L9721999-03-10010 March 1999 Forwards Rev 15 to EPIP 91104-C of Manual Set 6 of Vogtle Epips.Without Encl ML20207B0191999-02-25025 February 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 980701-1231,IAW 10CFR26.71(d) 05000424/LER-1998-009, Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 9812291999-01-27027 January 1999 Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 981229 ML20199F7701999-01-13013 January 1999 Submits Revised Response to RAI Re Licensee 980713 Proposed Amend to Ts,Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Protection Channels. Corrected Copy of Table,Encl ML20199F7981999-01-13013 January 1999 Forwards Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage. Change Bar in Margin of Affected Pages Denotes Changes to Rept ML20199G1381999-01-13013 January 1999 Forwards Copy of Permit Renewal Application Package for NPDES Permit Number GA0026786,per Section 3.2 of VP Environ Protection Plan 05000424/LER-1998-007, Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.731999-01-13013 January 1999 Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.73 ML20198F6131998-12-18018 December 1998 Forwards Revised Certification of Medical Exam Form for License SOP-21147.Licensee Being Treated for Hypertension. Util Requests That Individual License Be Amended to Reflect Change in Status ML20198L6631998-12-18018 December 1998 Forwards Amend 37 to Physical Security & Contingency Plan. Encl 1 Provides Description & Justification for Changes & Encl 2 Contains Actual Amend 37 Pages.Amend Withheld,Per 10CFR73.21 ML20198D9291998-12-16016 December 1998 Forwards Requested Info Re Request to Revise TSs Elimination of Periodic Pressure Sensor Response Time Tests & Elimination of Periodic Protection Channel Response Time Tests ML20198D9991998-12-16016 December 1998 Forwards Responses to 980916 RAI Re Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations ML20198D8171998-12-14014 December 1998 Forwards NRC Form 396 & Form 398 for Renewal of License OP-20993.Without Encls ML20206N3051998-12-0808 December 1998 Submits RAI Re Replacement of Nuclear Instrument Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys 1999-09-20
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20012D3741990-03-15015 March 1990 Requests Encl Proprietary Suppl 2 to WCAP-12218, Supplementary Assessment of Leak-Before-Break for Pressurizer Surge Lines of Vogtle Units 1 & 2, Be Withheld (Ref 10CFR2.790).Affidavit Also Encl ML20012D0981990-02-23023 February 1990 Forwards Presentation Matls Used During 900226 Meeting Re Pressure Surge Line Stratification Issue.Encl Withheld (Ref 10CFR2.790) ML20005E8251989-12-20020 December 1989 Requests That Proprietary Suppl 1 to WCAP-12218, Supplementary Analysis to Address Thermal Stratification for Vogtle Unit 1 Pressurizer Surge Line Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20247M7111989-05-22022 May 1989 Requests Proprietary Rev 1 to WCAP-11312, Westinghouse Owners Group Tech Spec Subcommittee Reactor Trip Breaker Maint/Surveillance Optimization Program, Be Withheld (Ref 10CFR2.790(b)(4)) ML20247E6511989-03-21021 March 1989 Requests That Proprietary WCAP-12218, Evaluation of Thermal Stratification for Vogtle Unit 2 Pressurizer Surge Line Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20235G9401989-02-10010 February 1989 Requests That Proprietary WCAP-12132, Surge Line Stratification Presentation Overheads - Georgia Power/Nrc Meeting 890124, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20147D2771988-02-0303 February 1988 Requests That Encl to Util Re LOFTTR2 Analysis for Steam Generator Tube Rupture Event Be Withheld from Public Disclosure,Per 10CFR2.790 & Encl Affidavit ML20236X8061987-12-0303 December 1987 Forwards Affidavit Requesting NRC to Withhold Proprietary Rev 0 to WCAP-10856, Westinghouse NSSS Mechanical Equipment Qualification for Georgia Power Co Plant Vogtle-Unit 1, Per 10CFR2.790(b)(4) ML20236B4081987-10-12012 October 1987 Submits Application for Withholding WCAP-11583, Technical Bases for Eliminating Accumulator Line Rupture as Structural Design Basis for Vogtle Unit 2. Affidavit Encl ML20236C7521987-10-12012 October 1987 Requests Proprietary WCAP-11599, Technical Bases for Eliminating RHR Line Rupture from Structural Design Basis for Vogtle Unit 2, Be Withheld (Ref 10CFR2.790).Affidavit Encl ML20237J8441987-08-17017 August 1987 Requests That Proprietary WCAP-11531, Addl Info in Support of Elimination of Postulated Pipe Ruptures in Pressurizer Surge Line of Vogtle Unit 2, Be Withheld (Ref 10CFR2.790) ML20235X0281987-07-13013 July 1987 Requests That Proprietary WCAP-11531, Technical Bases for Eliminating Pressurizer Surge Line Rupture as Structural Design Basis for Vogtle Unit 2, Be Withheld (Ref 10CFR2.790).Affidavit Encl ML20207K8441986-12-0101 December 1986 Requests Withholding of Proprietary Westinghouse Setpoint Methodology for Protection Sys - Vogtle Station, (Ref 10CFR2.790).Affidavit Encl ML20215L3881986-09-25025 September 1986 Requests Withholding Proprietary Version of Main Steam Line Break Info Used for Superheat Study for Votgle Units 1 & 2, (Ref 10CFR2.790).Rept of Same Technical Type as in Previously Submitted Affidavit AW-76-45 ML20203N4891986-09-22022 September 1986 Requests Withholding of Proprietary WCAP-11269, Westinghouse Setpoint Methodology for Protection Sys - Vogtle Station, from Public Disclosure Per 10CFR2.790. Affidavit Encl ML20115G5561985-04-10010 April 1985 Requests Withholding of Proprietary Info from Public Disclosure,Per 10CFR2.790.Affidavit Encl NRC-85-3008, Discusses Steam Superheating During Steam Line Break for Dry Containments.Reanalysis Not Required for Mass & Energy Releases Inside Large Dry & Subatmospheric Containments. Encls Withheld (Ref 10CFR2.790)1985-02-19019 February 1985 Discusses Steam Superheating During Steam Line Break for Dry Containments.Reanalysis Not Required for Mass & Energy Releases Inside Large Dry & Subatmospheric Containments. Encls Withheld (Ref 10CFR2.790) ML20090K6661984-05-0909 May 1984 Requests Proprietary WCAP 10551, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Aw Vogtle Units 1 & 2, Be Withheld ML20084F9461984-03-29029 March 1984 Requests Withholding Proprietary Response to NRC Question 491.2 from Public Disclosure.Affidavit Encl ML20077G6661983-07-27027 July 1983 Part 21 Rept Re Circuit Breakers Mfg Between Nov 1981 & Feb 1982.Breakers Should Be Inspected for Broken Puffer Linkage Studs.Stud Identified as Part Number 192247A.List of Circuit Breakers for Nuclear Plants Encl ML19345B7561980-10-31031 October 1980 Responds to 801001 Ltr Re Environ Qualification of safety- Related Equipment.Qualification Test Schedules Encl 1990-03-15
[Table view] |
Text
, _ - _ _ _ _ - _ _ _ . __ _ . - _ _ _ _
s Westinghouse Electric Corporation PowerSystems geygo 1
Box 355 .
Pittsbutgh Pennsytvania 15230 0355 February 3, 1988 CAW-88-011 Dr. Thomas Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20555 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Subject:
LOFTTR2 Analysis for a Steam Generator Tube Rupture Event for the Vogtle Electric Generating Plant Units 1 and 2
Dear Dr. Murley:
The proprietary material for which withholding is being requested in the reference letter by Georgia Power Company is further identified in an affidavit signed by the owner of the proprietary information, Westinghouse Electric Corporation. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10CFR Section 2.790 of the Commission's regulations.
The proprietary material for which withholding is being requested is of the same
- technical type as that proprietary material previously submitted as Affidavit AW-76-31.
l . Accordingly, this letter authorizes the utilization of the accompanying affidavit ,
by Georgia Power Company.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-88-011, and should be addressed to the undersigned. ,
Very-truly yours,
)
8803030278 800229 i
p DR ADOCK O 4y4 gg rt . n, Yanager Regulatory & Legislative Affairs i cc: E. C. Shomaker, Esq.
Office of the General Counsel, NRC '
i h
PROPRIETARY INFORMATION NOTICE
~
! TRANSMITTED HEREWITH ARE PROPRIETARY AND/OR NON-PROPRIETARY VERSIONS OF
. DOCUMENTS FURNISHED TO THE NRC IN CONNECTION WITH REQUESTS FOR GENERIC AND/OR i PLANT SPECIFIC REVIEW AND APPROVAL.
I IN ORDER TO CONFORM TO THE REQUIREMENTS OF 10CFR 2.T90 0F THE COMMISSION'S i
RE6ULATIONS CONCERNING THE PROTECTION OF PROPRIETARY INFORMATION SO SUBMITTED TO THE NRC. THE INFORMATION WHICH IS PROPRIETARY IN THE PROPRIETARY VERSIONS IS CONTAINED WITHIN BRACKETS AND WHERE THE PROPRIETARY INFORMATION HAS BEEN DELETED IN THE NON-PROPRIETARY VERSIONS ONLY THE BRACKETS REMAIN, THE INFORMATION THAT WAS CONTAINED WITHIN THE BRACKETS IN THE PROPRIETARY VERSIONS HAVING BEEN DELETED. TXE JUSTIFICATION FOR CLAIMING THE INFORMATION S0 DESIGNATED AS PROPRIETARY IS INDICATED IN BOTH VERSIONS BY MEANS OF LOWER CASE I LETTERS (a) THROUGH (g) CONTAINED WITHIN PARENTHESES LOCATED AS A SUPERSCRIPT IMMEDIATELY FOLLOWING THE BRACKETS ENCLOSING EACH ITEM OF INFORMATION BEING IDENTIFIED AS PROPRIETARY OR IN THE MARGIN OPPOSITE SUCH INFORMATION. THESE LOWER CASE LETTERS REFER TO THE TYPES OF INFORMATION WESTINGHOUSE CUSTOMAR1LY HOLOS IN CONFIDENCE IDENTIFIED IN SECTIONS (4)(ii)(a) through (4)(ii)(g) 0F THE AFFIDAVIT ACCOMPANYING THIS TRANSMITTAL PURSUANT TO 10CFR2.T90(b)(1).
l 4
AW 31 AFFIDAVIT C99tDNWEALTH OF PENNSYLVANIA: -
as COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared Robert A. Wiessmann, who, being by se duly sworn according to law. de- ,
poses and says that he is authortred to execute this Affidavit on behalf of Westinghouse Electric Corporation ("Westinghouse") and that the aver-ments of fact set forth dn this Affidavit are true and correct to the best of his knowledge information, and belief:
bAl(La4&tG Robert A. Wiesemann. Manager Licensing Programs Sworn to and subscribed befo is 7 day of '
1976.
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3 AW 76-31
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! (1) I am Manager. Licensing Programs. in the Pressurized Water Reactor Systens Division, of Westinghouse Electric Corporation and as such.
l I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public dis-closure in connection with nuclear power plant licensing or rule-making proceedings, and an authorized to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions.
(2) I en asking tMs Affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Connission's regulations and in con-junction with the Westinghouse application for withholding ac-corpanying this Affidavit.
(3) I have personal knowledge of the critaria and procedures utilized by Westinghouse Nuclear Energy Systess in designating information as a trade secret, privileged cr as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.793 of the Comission's regulations, the following is furnished for consideration by the Comission in determining whether the in-formation sought to be withheld from public disclosure should be erithheld.
(1) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
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-> M 76-31 (ii) The infomation is of a type customarily held in confidence W Westinghouse and not customarily disclosed to the public.
. Westinghouse has a rational basis for detemining the types of infomation customarily held in confidence by it and, in that connection, utilizes a system to detemine when and
,dether to hold certain types of infomation in confidence.
The application of that system and the substance of that system constitutes Westinghouse policy and provides the ,
rational basis requind. l Under that system. init,. nation is held in confidence if it falls in one or more of several types, the release of which ,
l sight result in the loss of an axisting or potential com-petitive advantage, as follows:
(a) The infomation nyeals the distinguishing aspects of a process (or component, structure, tool. method etc.)
dere prevention of its use by av of Westinghouse's.
competitors without license from Westinghouse consti-tutes a competitive economic advantage over other companies.
(b) It consists of supporting data. including test data, n1stive to a process (or component structure, tool, method etc.), the application of which data secures a ;
- competitive economic advantage, e.g. by optialzation
( or taproved marketability.
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AW-76-31 (c) Its use by a cogetitor would reduce his exper:diture of resources or taprove his cogetitive position in the design, manufacture, shipment tuta11ation, assurance -
of quality, or licensing a similar product.
(d) It reveals cost or price information, production cap-acities, budget levels, or comercial strategies of Westinghouse its customers or suppliers.
(e) It reveals aspects of past, present. or futurt West- -
. inghouse or customer funded development plans and pro-l grams of potential comercial value to Westinghotse.
(f) It contains patentable ideas, for which patent pro-taction may be desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage ever its com-petitors. It is, therefore, withheld from disclosure to, protect the Westinghouse competitive position.
AW-76-31 (b) It is infomation which is marketable in may ways.
The extent to which such infomation is available to _
competitors diminishes the Westinghouse ability to sell products and services involving the use of the infomation. ,
l' (c) Use by ocr competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
i (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantagc. If competitors acquire components of proprietary infer-nation, av ene component may be the key to the entiry puzzle. thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market.
and thereby give a market advantage to the competition in those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage. :
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AW 76-31 (iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR 5ection 2.790, it is to be received in confidence by the Commission. -
j (iv) The information is not available in public sources to the best of our knowledge and belief.
(v) The pmprietary information sought to be withheld in this submittal is that which is appropriately marked in the attach-ment to Westinghouse letter No NS CE-1142 Eicheldinger to Eisent ,c dated July 27. 1976 concerning reproductions of view-grqhs used in the Westinghouse presentation to the NRC during the meeting on July 27, 1976 on the subject of Westinghouse Reload Safety Evaluation Methodology.
This information enables Westinghouse to:
(a) Justify the design for the reload core (b) Assist its castomers to obtain licenses (c) pleet contractual requirements l
(d) Provide greater flexibility to customers assuring them of safe and reliable operation.'
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l AW-76-31 Further, this infomation has substantial commercial value ~
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as follows:
(a) Westinghouse sells the use of the information to its customers for purposes of meeting 80tc requirements for licensing docaentation.
(b) Westinghouse uses the information to perform and justify anatyses which are sold to customers.
(c) Westinghouse uses the information to sell nuclear fuel and related services to its customers.
Public disclosure of this informathi is likely to cause sub-stantial harm to the competitivo position of Westinghousi in selling nuclear fuel and relates services.
Westinghouse retains a marketing advantage by virtue of the ,
knowledge, experience and competence it has gained through
' long involvement and considerable investment in all aspects l
of the nuc~ fear power generation industry. In particular Westinghouse has developed a unique understanding of the factors and parameters which are variable in the process of design of nuclear fuel and which do affect the in service performance of the fuel and its suitability for the purpose for editch it was provided.
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-S- AW-76-31 In c11 cases that purpose is to generate energy in a safe and efficient manner uhile enabling the operating nuclear gener-
. ating station to meet all regulatory requirements affected by -
the core loading of nuclear fuel. Confidence in being able to accomplish this comes from the exercise of judgement based on expe *-noe.
Thus, the essence of the cometitive advantage in this field lies in an understanding of which analyses should be performed and in the methods and andels used to perform these analyses.
A substMttal part of this competitive advantage will be lost if the cogetitors of Westinghouse are able to use the results of the Westinghouse experience to normalize or verify their em process or if they are able to clata an equivalent under-standing by demonstrating that they can arrive at the same or similar conclusions. Its use by a cogetitor would veduce his s@nditure of resources or improve his competitive
. position in the design and licensing of a similar product.
~This'information is a product of Westinghouse design technology.
As such, it is broadly applicable to the sale and licensing of fuel in pressurtred water reactors. The development of this information is the result of many years of Westinghouse effort and the expenditure of a considerable sist of money. In order for competitors of Westinghouse to duplicate this process l
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AW 76-31 would require the investment of substantially the same amount of effort and expertist that hstinghouse possesses and which was acquired over a period of more thsn fifteen years and by the investment of millions of dollars.
Further the deponent sayeth not.
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