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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:OTHER U.S. GOVERNMENT AGENCY/DEPARTMENT TO NRC
MONTHYEARML20246H9631989-08-28028 August 1989 Discusses Allegations of Noncompliance W/Antitrust License Conditions.Util Has Not Cited Any Legitimate Reasons for Excluding Oglethorpe from Market for off-sys Transactions ML20206F3071988-10-28028 October 1988 Forwards Vogtle Electric Generating Plant Exercise Rept for Exercise Conducted on 880524. No Deficiencies Identified. Rept Identifies One Area Requiring Corrective Action ML20151V2151988-08-0808 August 1988 Forwards Vogtle Electric Generating Plant Site-Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification, Based on 870714 Full Sys Activation.Requirements Satisfied ML20154C3251988-05-0303 May 1988 Forwards Vols I & II to DPSPU-88-30-1, Savannah River Plant Environ Rept for 1987 ML20215F0681987-06-0909 June 1987 Reviews States of Ga & Sc Local Plans for Radiological Emergencies for Vogtle Plant.Subj to Condition Stated,Local Plans & Preparedness Found Adequate ML20214J0921986-11-20020 November 1986 Advises That Facility Emergency Exercise Rept for 860430- 0501 Should Be Corrected to Indicate That State of Sc Fully, Not Partially,Participated in Exercise ML20215B0231986-09-25025 September 1986 Forwards Interim Findings Rept on Adequacy of Radiological Emergency Response Preparedness for Plant Vogtle,Ga. Emergency Response Plans Adequate ML20210J7671986-09-23023 September 1986 Forwards Radiological Emergency Preparedness Exercise Rept for 860430-0501 Full Participation Joint Exercise of States of Ga & Sc & Counties of Aiken,Allendale & Barnwell. No Deficiencies Identified ML20215B3211986-09-15015 September 1986 Advises That SM Rochlis No Longer Regional Counsel for FEMA & Name Should Be Removed from Svc List.Certificate of Svc Encl ML20204G6181986-07-24024 July 1986 Requests Response to Encl Kw Brinson Re Safety of Savannah River Reactors & Startup of Vogtle ML20137E8901986-01-14014 January 1986 Responses to 851115 Request to Review Emergency Preparedness Public Info Matls for Plant.Map & Draft Brochure Submitted W/Public Info Matl Address Only That Part of Plume Emergency Planning Zone in State of Ga ML20132B7171985-09-23023 September 1985 Forwards Radified Memorandum of Agreement Re Transmission Line,Per Section 106 of Natl Historic Preservation Act. Agreement Also Sent to State of Ga Historic Preservation Officer ML20133F1711985-07-24024 July 1985 Responds to Re Potential Effects of Proposed Facility Operation on Endangered Shortnose Sturgeon.Based on NRC Biological Assessments & Supplemental Documents, Population Not Adversely Affected by Proposed Action ML20127J4491985-05-15015 May 1985 Comments on Fes Re Facility Operation.Modified Plan for Routing High Voltage Transmission Line Through Ebeneezer Creek Swamp Utilizing Taller Towers Should Minimize Impact ML20133A5121985-04-30030 April 1985 Forwards PA Bradley FOIA Request for Documents Re Vogtle & Ei Hatch Antitrust Reviews ML20100A4161985-03-15015 March 1985 Discusses Des,Received on 850306,as Part of Review of OL Application.Biological Assessment in Des Contains Insufficient Info to Assess Project Impacts on Shortnose Sturgeon ML20101T1911985-01-22022 January 1985 Expresses Appreciation for Transmitting Des OL Stage.Comments on Discrepancy Re Average Rate of Groundwater Use on Pages 4-3 & 5-5.Map Similar to Figure 4-10 Suggested to Show Locations of Deep Wells ML20112H8001985-01-10010 January 1985 Forwards Detailed Comments on Des Re Air Quality,Water Quality,Wetland Impacts & Noise.Addl Info & Clarification Requested Re Water Quality & Supplemental Measures Suggested for Potential Wetland & Noise Impacts ML20101C2781984-12-14014 December 1984 Comments on Des ML20100J7631984-11-30030 November 1984 Ack Receipt of Des.No Comments Offered ML20093M4591984-10-16016 October 1984 Discusses Plans & Guidelines in Util Re Proposed Transmission Line Crossing Ebenezer Creek.Recommends Culverts Be Included as Condition in Review of Corps of Engineers Permit for Work ML20093C5091984-09-24024 September 1984 Responds to NRC 840912 Request for Views on Transmission Line Crossing of Ebenezer Creek Swamp,Ga,Designated Natl Natural Landmark.Use of Alternative Routes a or B or Const of Larger Towers Recommended.Site Evaluation Encl ML20093D1371984-07-11011 July 1984 Responds to 840618 Request for Info on Federally Listed Threatened & Endangered Species That May Be Affected by Facility & Transmission Corridors.Status of red-cockaded Woodpecker Should Be Determined During Evaluations ML20092L2661984-06-26026 June 1984 Ack Receipt of 840618 Request for Comments on Ol.Ltr & Encl Documentation Forwarded to Endangered Species Field Station, Jacksonville,Fl for Review & Response.W/O Encls ML20106A0681984-01-27027 January 1984 Discusses Savannah District Dam Safety Plan.Plan & Related Maps Forwarded Under Separate Cover.Plan Addresses Emergencies Re Above Normal Reservoir Water Levels &/Or Rapid Release of Large Vol of Water Past Dam ML20246D8771974-05-0101 May 1974 Recommends That Applications Be Made Subj of Evidentiary Hearings.Applicant Agreed to Inclusion in Hatch & Vogtle Licenses of Conditions Providing for Access to Plants Scheduled to Commence Operation Prior to 890101 1989-08-28
[Table view] |
Text
a f to sm, f AMb g y UNITED STATES ENVIRONMENTAL PROTECTION AGENCY g gc REGloN IV 345 COURTLAND STREET ATLANTA GEORGIA 30365 7 JAN 101935 5$ /
4PM-EA/HOM Ms. Melanie Miller Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
Draft Environmental Impact Statement Related to the operation of Vogtle Electric Generating Plant, Units 1 & 2 EPA Log No.: D-NRC-E0004-GA .
Dear Ms. Miller:
Pursuant to Section 309 of the Clean Air Act and Section 102(2)(C) of NEPA, EPA has reviewed the Draft Environmental Impact Statement (DEIS) on the operation of the Vogtle Electric Generating Plant, Units 1 and 2. Our review of this project has primarily concentrated oa air quality, water quality, wetland impacts, and noise. We encourage you to also coordinate with other agencies for their review of other environmental and non-environmental factors.
Based on the discussion in the attached " Detailed Comsnents," we rate this DEIS an "LO-2", i.e., lack of major objections to the proposed action. However, some additional information and clarification has been requested in the attachment for water quality as well as supplemental mitigation measures suggested for potential wetland and noise impacts.
We appreciate the opportunity of commenting on.this DEIS.
Please contact us if you have any questions regarding our comments. The contact person on my staff for this project is Chris Hoberg at FTS 257-7901.
Sincerely yours,
'Sheppard N. Moore, W/
ief W
-NEPA Review Staff Environmental Assessment Branch
Attachment:
" Detailed Comments" h
8501180045 850110 '
I fI PDR ADOCK 05000424 D PDR
l cc: Mr.~W. Thomas Brown Associate Regional Director ,
Planning and External Affairs
'U.S. Department.of_the Interior National Park Service Southeast Regional Office 75 Spring Street,'S.W.
Atlanta,' Georgia 30303 Mr'. Edwin M. Eudaly Acting Field Supervisor U.S. Department of the Interior Fish and Wildlife. Service Federal Building.
810 Gloucester Street Brunswick,' Georgia 31520 d
4 C'
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- DETAILED' COMMENTS AIR"OUALITY We have reviewed the DEIS for non-nuclear, ambient air quality impacts. Since this is a nuclear plant, the only non-radioactive pollutants (e.g., sulfur dioxide and nitrogen oxides) are those produced by the operation of.the emergency diesel generators and auxiliary boilers. The emissions from these sources are suffi-ciently low and the diesel generators are exempt from the State of Georgia air quality permitting requirements. -The auxiliary boilers are proposed to.be operated in accordance with Georgia permit emission limitations. Visible emissions from the cooling towers should not degrade visibility of any class I area with the plume dissipating near the plant.
We, therefore, find no ambient air quality concerns for any non-nuclear pollutants if the plant is operated as proposed.
WETLANDS Our major wetland concern involves the proposed routing of a high
. voltage transmission line through Ebenezer Creek Swamp, an area designated by the U.S. Park Service as a National Natural Landmark.
The original alternative to clear-cut a ISO-foot wide corridor through the swamp would have had a significant adverse environmental impact on the ecosystem. However, the modified plan, developed by the applicant in response to the concerns of the U.S. Fish and Wildlife Service and the National Park Service, should minimize the impact on the swamp. By the use of taller towers, the clearing can be limited to a 100 by 100 foot area for the base of the tower at Station 124.00.
Best Management Practices should be used to minimize construction impacts on the water quality of wetlands adjacent to the work site.
Access roads for construction should avoid filling wetland. areas.
Any permanent sloughs and water channels should be crossed by bridging or open-bottom box culverts adequately sized to accommodate the natural flow. To minimize additional clearing, existing logging roads should be used whenever possible for access roads.
In addition, for areas in or adjacent to the swamp, we would prefer mechanical means used for any necessary right-of-way maintenance.
.Any herbicides used, of course, should be EPA approved and applied in accordance with label directions.
WATER' OUALITY Our water quality review has identified the need.for some additional clarification and information. Our detailed water quality concerns are as follows:
o Outfall Serial No. 001B7 of the NPDES permit' limit's the non-radiological components of the radwaste discharge and should be discussed in Section 4.2.5, page 4-5 or Section 4.2.6, page 4-6.
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w o Page 4-6 and 4-7, Section 4. 2.6. Under 40 CPR Part 423, " chemical metal cleaning wastes" are not included in the " low volume waste" category. To.the extent that " start up and equipment cleaning" wastes are conducted using chemicals such as acids, alkaline phosphate solutions, etc., they are prc'erly designated " chemical 1 metal cleaning. wastes" and not " low volume wastes." If wastes result from water wash only, they would properly be designated low volume wastes and could be combined with other low volume wastes for co-treatment in one of the designated facilities.
However, " chemical metal cleaning wastes" are designated for treatment in the start-up pond prior to combination with treated
" low volume wastes." Metal cleaning wastes are limited in terms of total iron, total copper, and oil and grease as well as total suspended solids (See Part III.B.3, page 14 of the NPDES permit).
(Note: Effluent' guidelines limitations are properly presented in Table'5.1.)
o Section 5.3.2.3., page 5-7 and 5-8. Discussions should include assessments of the impact of continuous chlorination for Asiatic clam control on concentrations of chlorine released as well as time of detectable discharge of total residual chlorine (TRC).
This discussion should address one unit operation where dilution from the second unit is not available and assume a limit of detection of 0.03 mg/1.
NOISE The DEIS considered both'on-site generated noise and off-site transmission line noise impacts. On-site noise generators, based on model predictions, are expected to increase noise levels at receptor sites located at the perimeter of the facility from 1 to 12 dBA over ambient levels. None of the sites, however, are pre-dicted to experience noise levels exceeding 40 dBA. Using the composite noise rating versus community response scale (DEIS, Figure 5.23), Sites No. 5 and 6 would be expected to generate considerable community complaints based on noise level increases of 11 and 12 dBA, respectively. However, since no residential receptors are currently located near'these' sites, no noise impacts are expected.
One off-site residential receptor along the transmission line corridor is expected to experience noise level increases of 12 to 20 dBA over ambient levels. These noise level increases.are expected to be generated by the transmission line-during and for several hours after_ wet weather conditions. Because'of its hearing-frequency range and tonal nature, the expected 49 dBA L10:le' vel at the home site can be considered to be. equivalent to a 58-dBA level in terms of intrusion and annoyance. The magnitude of the noise' level increase and its intrusive nature may result in considerable annoyance, and we would consider it to be a significant ~ impact.- Therefore,~ feasible mitigation' measures for this residentiala site should be considered by the' applicant and the U.S. Nuclear-Regulatory Commission.
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