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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:UTILITY TO NRC
MONTHYEARELV-02056, Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam1990-09-0606 September 1990 Forwards Operator Exam Schedule for Facility,Per Generic Ltr 90-07 Request,Including Number of Candidates to Be Examined During NRC Site Visits,Requalification Schedules & Number of Candidates to Participate in Generic Fundamentals Exam ELV-01599, Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator1990-09-0404 September 1990 Discusses Mods to HED-1114 Re Plant Dcrdr,Per . Amber Monitor Light Covers Installed for Spare Pumps to Make Status of Pumps Readily Apparent to Operator ELV-02059, Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B1990-08-30030 August 1990 Clarifies 900409 Response to 900323 Confirmation of Action Ltr.Util Made 31 Successful Start Attempts for Diesel Generator (DG) 1A & 29 Successful Start Attempts for DG 1B ELV-01956, Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request1990-08-30030 August 1990 Forwards Listed Documents in Response to Request for Addl Info Re Settlement Monitoring Program,Per 900614 Request ELV-02050, Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required1990-08-30030 August 1990 Responds to Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Administrative Procedures Controlling Verification & Validation of Emergency Operating Procedures Will Be Evaluated & Revised as Required ELV-02028, Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d)1990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for First Six Month Period,Per 10CFR26.71(d) ELV-02022, Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld1990-08-22022 August 1990 Forwards Revised LER Re Apparent Personnel Error Leading to Unsecured Safeguards Info.Ler Withheld ELV-02027, Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively1990-08-20020 August 1990 Forwards Rev 0 to Core Operating Limits Rept, for Cycle 3, Per Amends 32 & 12 to Licenses NPF-68 & NPF-79,respectively ELV-01973, Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical1990-08-14014 August 1990 Submits Rept Re Results of Leakage Exams Conducted During Spring 1990 Refueling Outage,Per TMI Item III.D.1.1.None of Identified Leakage Considered Excessive.Work Orders Issued in Effort to Reduce Leakage to Level as Low Practical ELV-01918, Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion1990-08-0303 August 1990 Responds to NRC 900612 Request for Comments & Suggestions on Draft risk-based Insp Guide.Util Conducting Individual Plant Exam & Will Withhold Comment on risk-based Insp Guide Until Completion ELV-01943, Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned1990-07-27027 July 1990 Responds to Violation & Proposed Imposition of Civil Penalty in Insp Repts 50-424/90-11 & 50-425/90-11.Corrective Action: Complete Audit of Contents of Safeguards Info Container Performed & Unassigned Safeguards Info Dispositioned ELV-01949, Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable1990-07-26026 July 1990 Forwards Info Re Status of Pen Branch Fault Investigation. Investigations Conducted So Far Still Indicate That Pen Branch Fault Not Capable ELV-01500, Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities1990-07-25025 July 1990 Forwards Nuclear Decommissioning Funding Plan for Plant.Info Provides Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Facilities ML20055H6441990-07-23023 July 1990 Submits Summary of Snubber Types & Sample Plans for Functional Testing to Be Performed During Sept 1990 Outage ML20044B0311990-07-13013 July 1990 Forwards Vogtle Electric Generating Plant Unit 1 Reactor Containment Bldg 1990 Integrated Leakage Rate Test Final Rept. ML20044B1541990-07-12012 July 1990 Responds to NRC 900612 Ltr Re Violations Noted in Insp Repts 50-424/90-08 & 50-425/90-08.Corrective Actions:Eop Step Deviation Documents to Be Upgraded,Adding More Justification & Temporary Change Issued to Correct EOP Deficiencies ELV-01867, Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered1990-07-12012 July 1990 Responds to Violations Noted in Insp Repts 50-424/90-10 & 50-425/90-10.Corrective Action:Level Indication Error Corrected After Discrepancy Discovered ML20055F1651990-07-0909 July 1990 Forwards Comments Re NUREG-1410 ELV-01858, Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete1990-07-0606 July 1990 Advises That Full Compliance W/Violation Will Not Be Achieved Until Nov 1990,when Evaluation of VP-2693 Complete ML20044A8851990-07-0606 July 1990 Forwards Response to NRC Question on Steam Generator Level Instrumentation Setpoints,Per Revised Instrument Line Tap Locations.Tap Location Will Be Changed from Above Transition Cone to Below Transition Cone ELV-01834, Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21)1990-06-28028 June 1990 Forwards Response & Comments to Regulatory Effectiveness Review Rept.Encl Withheld (Ref 10CFR73.21) ML20044A2791990-06-25025 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Indicating Status of Each Generic Safety Issue Encl ML20043J0171990-06-22022 June 1990 Discusses Corrective Actions for Plant Site Area Emergency, Per 900514 Ltr.Jacket Water High Temp Switches Calibr for Diesel Generators,Using Revised Calibr Procedure ML20043H3061990-06-15015 June 1990 Forwards Rev 3 to ISI-P-014, Inservice Insp Program, for Review & Approval,Per Tech Spec 4.0.5 Re Surveillance Requirements.Rev Includes Withdrawal of Relief Requests RR-45,47,48 & 54 ML20043G2071990-06-12012 June 1990 Forwards Amend 18 to Physical Security & Contingency Plan. Amend Withheld (Ref 10CFR73.21) ML20043G1021990-06-0606 June 1990 Requests Temporary Waiver of Compliance from Requirements of Action Statement 27 of Tech Spec 3.3.2 for Period of 6 H When Two Operating Control Room Emergency Filtration Sys Trains Shut Down for Required Testing ML20043E6901990-06-0505 June 1990 Forwards Rev 12 to Emergency Plan & Detailed Description & Justification of Changes.W/O Rev ML20043G7651990-06-0505 June 1990 Forwards Rev 13 to Emergency Plan & Description & Justification of Changes ML20043B5991990-05-25025 May 1990 Forwards Scope & Objectives Re 1990 Annual Emergency Preparedness Exercise to Be Conducted on 900801 ML20043B5981990-05-24024 May 1990 Responds to Violations Noted in Insp Rept 50-424/90-05 on 900217-0330.Corrective Actions:Locked Valve Procedure Revised to Eliminate Utilization of Hold Tag on Valves Required by Tech Specs to Be Secured in Position ML20043B6291990-05-22022 May 1990 Forwards Rev 5 to ISI-P-008, Inservice Testing Program, Per Tech Specs 4.0.5 Re Surveillance Requirements & Generic Ltr 89-04 ML20043B6351990-05-22022 May 1990 Forwards Rev 2 to ISI-P-016, Inservice Testing Program, Per Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. ML20042H0601990-05-14014 May 1990 Forwards Summary of Corrective Actions for 900320 Site Area Emergency Due to Loss of Offsite Power Concurrent W/Loss of Onsite Emergency Diesel Generator Capability.Truck Driver Disciplined for Lack of Attention ML20042G7301990-05-11011 May 1990 Forwards Revised Pages for May 1989,Jan & Mar 1990 Monthly Operating Repts for Vogtle Electric Generating Plant,Units 1 & 2.Revs Necessary Due to Errors Discovered in Ref Repts ML20042E2911990-04-18018 April 1990 Forwards Amend 17 to Security Plan.Amend Withheld (Ref 10CFR2.790) ML20042E7481990-04-0909 April 1990 Requests Approval to Return Facility to Mode 2 & Subsequent Power Operation,Per 900320 Event Re Loss of Offsite Power Concurrent W/Loss of Onsite Emergency Diesel Generator Capability ML20012E9001990-03-28028 March 1990 Provides Supplemental Response to Station Blackout Rule,Per NUMARC 900104 Request.Mods & Associated Procedure Changes Identified in Sections B & C W/Exception of Mods to Seals Will Be Completed 1 Yr from Acceptance of Analysis ML20012E8581990-03-28028 March 1990 Suppls Response to NRC Bulletin 88-010,Suppl 1 Re Traceability Reviews on Molded Case Circuit Breakers Installed in safety-related Applications.All Breakers Procured & Installed in Class 1E Equipment Reviewed ML20012E9761990-03-27027 March 1990 Requests Withdrawal of Inservice Insp Relief Requests RR-45, RR-47,RR-48 & Conditional Withdrawal of RR-54 Based on Reasons Discussed in Encl,Per 900206 Conference Call ML20012D8561990-03-22022 March 1990 Submits Special Rept 1-90-02 Re Number of Steam Generator Tubes Plugged During 1R2.One of Four Tubes Exceeded Plugging Limit & Required Plugging.Remaining Three Tubes Plugged as Precautionary Measure.No Defective Tubes Detected ML20012D6641990-03-22022 March 1990 Provides Followup Written Request for Waiver of Compliance to Make Tech Spec 3.04 Inapplicable to Tech Spec 3.8.1.2 to Permit Entry Into Mode 5 W/Operability of Diesel Generator a & Associated Load Sequencer Unverified ML20012D3681990-03-19019 March 1990 Forwards Proprietary & Nonproprietary Suppl 2 to WCAP-12218 & WCAP-12219, Supplementary Assessment of Leak-Before-Break for Pressurizer Surge Lines of Vogtle Units 1 & 2, Per 900226 Request.Proprietary Rept Withheld (Ref 10CFR2.790) ML20012D3401990-03-19019 March 1990 Submits Response to 891121 Request for Addl Info Re Settlement Monitoring Program.Current Surveying Procedures Used by Plant to Monitor Settlement of Major Structures Outlined in Procedure 84301-C.W/41 Oversize Drawings ML20012D6631990-03-15015 March 1990 Responds to Generic Ltr 89-19 Re Resolution of USI A-47 on Safety Implications of Control Sys in Lwrs.Overfill Protection Sys Sufficiently Separate from Control Portion of Main Feedwater Control Sys & Not Powered from Same Source ML20012C4681990-03-0606 March 1990 Provides Summary Rept of Property Damage Insurance Levels, Per 10CFR50.54(w)(1) ML20012B2891990-03-0606 March 1990 Forwards Plant Pipe Break Isometrics,Vols 1 & 2 & Advises That Encl Figures Have Been Revised to Be Consistent W/Pipe Analysis in Effect at Time That Unit 2 Received Ol,Including Revs Through 890930.W/309 Oversize Figures ML20012B2421990-03-0606 March 1990 Forwards Cycle 3 Radial Peaking Factor Limit Rept & Elevation Dependent Peaking Factor Vs Core Height Graph ML20011F5291990-02-26026 February 1990 Withdraws 881107 Proposed Amend to Tech Spec 3.8.1.1, Revising Action Requirements for Inoperable Diesel Generator to Clarify Acceptability of Air Roll Tests on Remaining Operable Diesel Generator ML20011F5261990-02-26026 February 1990 Forwards 1989 Annual Rept - Part 1. Part 2 Will Be Submitted by 900501 ML20011E8911990-02-12012 February 1990 Advises That Hh Butterworth No Longer Employed by Util 1990-09-06
[Table view] |
Text
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Geo'Q a Naef Cornovy Fbst Off c: Du 282 W:yeescoro. Georg a 3c;30 1e e&cco 404 554 9%1 404 724 8114 Souteern Cortpa y Sery ces Inc Nst Off.co Box M25 Bengham, Aabama 35202 b
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Vogtle Project Septembe r 2,1988 U. S. Nuclear Reguistory Cornission Logt GN-1483 Attn Document Control Desk Filet X7N16 Washington, D.C. 20555 NRC DOCKET NUMBER 50-424 CONSTRUCTION PERMIT NUMBER CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNIT 2 PROOF AND REVIEW TECHNICAL SPECIFICATIONS Centlement We hsve reviewe.1 the Proof and Review copy of the combined Technical Specifications for Vogtle Units 1 and 2. Enclosed are our comments for your consideration in developing the final draft. The comments consist mainly of eittorial co m ents, the incorporation of Unit 1 Technical Specification (
amenleents c~1 change requests that are anticipated to be approve $ in the near future, ani the ad11 tion of Unit 2 specific information relative to heatup and cooldown rates.
The encionures inciule a brief description and justification of each proposed I chsnge to the Proof sni Review copy. Since some changes involve more than one page we are also including a table thst lists each page on which we proposed a change anl the justifiestion applicable to that page. The enclosures incluie a list of open items that we have yet to provide to the NRC. ,
The enclosures are t (1) a list of chsngel pages and the justifications for the changes, (2) a list of items to be providei later, and (3) markel-up Proof and Review Technics 1 Specification pages with figures.
Sincerely, i
J. A. Bailey Project Licensing Manager JAB /si Enclosures xet list sttache1 l 'f
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r U. S. Nuclear Regulatory Consission September 2, 1988 Page 2 xc3 NRC Regional Administrator NRC Resident Inspector P. D. Rice J. P. W ne R. A. Thomas B. W. Churchill, Esquire J. B. 11opkins (2)
G. Bockhold, Jr.
R. J. Goddard, Esquire R. W. McManus C. K. McCoy R. P. Mcdonald Vogtle Project File
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Geors'4 PDwee Comoeay .
Poet Ott<e hos 262 Werettora Geor94 30430 Woohcee 4*A SM 9961 404 724 4114 Soutrem Company $ ewes. Inc.
Post Ott<e Son 2625 Beruqum. Alabama 3$202 ve-e 2es m. "
Nh PW September 2,1988 U. S. Nuclear Regulatory Commission Lost GN-1483 Attnt Document Control Desk Filet X7N16 Washington, D.C. 20555 NkC DOCKET NUMBER 50-424 CONSTRUCTION PERMIT NUMBER CPPR-109 a V0GTLE ELECTRIC CENERATING PIMI - UNIT 2 PROOF AND REVIEW TECHNICAL SPECIFICATIONS Centlement We have reviewed the Proof and Review copy of the combined Technical Gpecifications for Vogtle Units 1 and 2. Enclosed are our comments for your
, consideration in developing the final draft. The consents consist mainly of editorial comments, the incorporation of Unit 1 Technical Specification j amendments or change requests that are anticipated to be approved in the near future, and the addition of Unit 2 specific information relative to heatup and cooldown rates.
The enclosures include a brief des.ription and justification of each proposed change to the Proof and Review copy. Since some changes involve note than one page we are also including a table that lists each page on which we proposed a change and the justification applicable to that page. The enclosures include a list of open items that we have yet to provide to the NRC.
The enclosures aret (1) a list of changed pages and the justifications for the changes, (2) a list of items to be provided later, and (3) marked-up Proof '
, and Review Technical Specification pages with figures.
I Sincerely,
! 9 4. My J. A. Railey Project Licensing Manager JAB /ss Enclosures
, set list attached l
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- 11. S. Nuclear Regulatory Coesission fleptester 2,1988 l Page 2 j i
4 f xc NRC Regional Administrator !
NRC Resident Inspector !
4 P. D. Rice i J. P. Kana R. A. Thomas !
- 3. W. Churchill, Esquirs !
J. 3. Hopkins (2) i I
G. Rockhold, Jr.
R. J. Coddard, Esquire j R. W. McManus i C. K. McCoy [
R. P. Mcdonald !
Yostle Project File l 6
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{
ENCLOSURE 1 TO 12TTER GN-1443 i List of pages with proposed changes and justifications.
Change Pages Justification to i IV 3 3/4 3-10 1 VI 1 3/4 3-11 1 VIII 5 3/4 3-13 3 x1 1 3/4 3-14 )
xv1 5 3/4 3-15 1 XXII 2 3/4 3-20 1
]
2-2 20 3/4 3-21 1, 4
- l 2-3 1 3/4 3-25 13 25 1 ,
3/4 3-30 1 3/4 0-4 1 3/4 3-31 1 1
3/4 0-2 1, 11 3/4 3-35 1 j 3/4 1-3a 3 3/4 3-40 1
- 3/4 1-3b 3 3/4 3-44 13 3/4 1-3e 3 3/4 3-50 19 3/4 1-33 3 3/4 3-51 1 3/4 1-4 3 3/4 3-52 1 3/4 1-6 1 3/4 3 -54 1 3/4 1-7 1 3/4 3-56 1 l 3/4 1-11 3 3/4 3-57 1 l 3/4 1-12 3 3/4 3-59 1 i 3/4 1-16 1 3/4 3-40 1 l 3/4 1-18 1 3/4 3-61 1 3/4 1-20 1 3/4 3-42 1 i 3/4 1-21 1 3/4 3-46 1, 19 j 3/4 1-22 20 3/4 3-49 1 3/4 2-1 1 3/4 3-72 1, 19 3/4 2-3 20 3/4 3-74 1 3/4 2-5 20 3/4 3-76 1
! 3/4 3-3 1 3/4 3-80 1 3/4 3-6 1 3/4 4-3 1
l t
l ENCLO8tRE 1 !
Pase 2 t I
3/4 4-5 1 3/4 7-21 1
[
3/4 4-6 1 3/4 7-24 20 3/4 4-10 1 3/4 7-28 1 . l 3/4 4-16 1 3/4 7-31 1
}
3/4 4-21 15 3/4 7-32 1 [
3/4 4-22 1 3/4 8-1 1 I 3/4 4-26 20 3/4 8-2 1 3/4 4-30 5, 1 3/4 8-5 1, it i 3/4 4-31 5, 16 3/4 8-6 1 3/4 4-31a 5, 16 3/4 8-7 1 3/4 4-32 5, 16 3/4 8-9 1
[
3/4 4-32a 5, 16 3/4 6-14 19 3 /4 4 -34 5, 1 3/4 8-21 8 I 3/4 4-35 5 3/4 8-22 1 f 3/4 4-35a 5 3/4 8-23 1 I 3/4 5-1 3, 1 3/4 8-24 1 .
3/4 5-4 12 3/4 9-14 13 L 3/4 5-10 3 3/4 11-1 1 3/4 6-3 1 3/4 11-2 1 f 3/4 6-7 1 3/4 11-3 1 .
3/4 6-8 17 3/4 11-s 1 !
3/4 6-11 1 3/4 11-9 1 f 3/4 6-12 1 3/4 11-10 1
[
3/4 7-1 1 3/4 12*3 1
3/4 7-3 1 3/4 12-4 1 j 3/4 7-8 1 3/4 12-5 1 j 3/4 7-14 6 3/4 12-5 1 i 3/4 7-16 6 3/4 12-9 1 3/4 7-17 f
7 3/4 12-10 1 3/4 7-19 1 33/4 0-4 1 I
l
ENCLOSUILE 1 l Pane 3 l
l 83/4 0-5 1 5-6 1 33/4 0-1 1 6-1 2, 1 33/4 1-3 3, 1 6-2 2 53/4 2-2 1 6-3 2 53/4 2-3 20 4-4 2 33/4 3-3 3 6-5 1 33/4 3-4 1, 14 6-4 2, 10 B3/4 4-7 5, 1 6-7 2 53/4 4-8 5, 1 6-S 1, 2 33/4 4-9 5 6-9 2 83/4 4-9a 5 6-12 2, 1 B3/4 4-10 5 6-13 2 33/4 4-11 5 6-14 2 33/4 4-12 5 6-20 1 33/4 4-15 5, 1 6-24 2 53/4 5-1 3 6-25 2 33/4 5-2 3, 1, 12 Title Page for 1 Bases 3/4.6 33/4 6-2 1 33/4 6-3 3 33/4 7-1 1 B3/4 7-7 1 -
83/4 8-1 1 83/4 8-2 1 ,
33/4 8-3 1 53/4 9-1 3 5-2 20 5-3 20 5-5 9 9
i e
t 3
ENCLOSURE 1 l
Pase 4 t
JUSTIFICATIONS FOR CHANGES TO PROOF AND REVIEW DRAFT
- 1. Description of the channe L l D VI Change "Loose-Parts" to "Loose Parts".
XI "Change "MOTOR OPERATED" to "MOTOR-OPERATED". !
2-3 Align the margin for Equation 2.2-1 over the word '
"where".
- 2-5 Cha nge " y, " to " > " .
- 3/4 0-4 Remove the page number and plant identification from the.
title page for Section 3.0 and 4.0 and move the title i page to the front of Section 3.0 and 4.0. i i
3/4 0-2 The period after "common." in 3.0.5 should be outside ;
the quotation mark. ;
j 3/4 1-6 To eliminate confusion for items that have two footnotes [
one indicated by
- and the other by **, replace the **
l with d. (The **" and "**" look like * ***" in some v cases.) i
> c 3/4 1-7 Insert "and" af ter "72*F" in Specification 4.1.2.1.a. [
This is consistent with 4.1.2.2.a. '
i 3/4 1-16 Adjust the left margin of line six such that the word "Pressure" begins beneath the word "Break" j
3/4 1-18 Replace ** with f. See justification for change to
- ,page 3/4 1-6. t 3/4 1-20 Replace ** with f. See justification for change to l page 3/4 1-6.
3/4 1-21 Replace ** with d. See justifiestion for chanse to I page 3/4 1-6. !
I 3/4 2-1 Replace ** with d. See justification for change to L page 3/4 1-6. !
3/4 3-3 Align table entries for Table 3.3-1.
(
l l
[
t i
L ENCLOSURE 1 1 pane 5 i
- 1. Description of the Change (Continued)
M
. 3/4 3-6 "Under voltage /under frequency" should be "undervoltage/underfrequency". !
j
- 3/4 3-10 Remove the extra space from the column headings and correct the l alignment for the table entries for functional Unit 12. p
, 3/4 3-11 Change the dotted line to a solid line to separate the footnote from the remainder of the page.
3/4 3-14 Eliminate the space between table notations (16) and (17).
- 3/4 3-15 Move the word "where" to align it under the word Equation and
- reduce the space between "Equation 2.2-1" and the first ters of I the Equation.
i
- 3/4 3-20 The hand-marked *'s on functional units 4.c and 4.e should be !
j typed, align "loop 2" in functional ueit 4.c. j 3/4 3-21 The hand-marked "*" on functional unit 5.c should be typed. I i 3/4 3-30 This page was inadvertently omitted from the Troof and Review l copy. A copy of this page is included for convenience, i I I
- 3/4 3-31 Change the location of the i to appear after 18.5% for items l l 6.b.1 and 2.
1 3/4 3-35 Align sargin for the table notations.
I 1
3/4 3-40 change the location of the ** to appear af ter "High-High" for
- ites 5.c.
) 3/4 3-51 Align "(basemat)" beneath the word "Unit" in itee 5.a.
3/4 3-52 Align "(basemat)" beneath the voed "Unit" in ites 5.a.
l 3/4 3-54 Delete the spurious mark E. j
! l 3/4 3-56 Delete the "LP" from ites 3 of Table 3.3-7. [
! 3/4 3-57 Realian entries in the table, f
1 3/4 3-59 Realign lustrument numbers. [
3/4 3-60 Realign entrant in the table.
k
_~r
ENCIASURE 1 Pase 6
- 1. Description of the Chante (Continued)
Page 3/4 3-61 Delete the "s" from "requirements" and capitalize letters as indicated.
3/4 3-62 Delete the "s" from "requirements" and capitaltre letters as indicated.
3/4 3-66 Realign entries on Table 3.3-9.
3/4 3-69 Realign entrant in the table.
3/4 3-72 Realign entries on Table 3.3-10, 3/4 3-74 Insert "the" between "if" and "inlet" in ACTION statement 4.9.b. Add a period st the end of table notation f.
3/4 3-76 Realign entries to Table 4.3-6.
3/4 3-80 Realign entries to Table 3.3-11.
3/4 4-3 Change "50 'F" to "50'F".
3/4 4-5 Change "50 *F" to "50*F".
I 3/4 4-6 Correct indentation of Specification 4.4.1.4.2.2.
3/4 4-10 Align margin in Specification 4.4.4.1, 3/4 6-16 Capitalize "specification".
3/4 4-22 Align "V0GTLE UNITS - 1 & 2" with the left margin.
3/4 4-30 Delete the spurious statement "FIGURE 3.4-2".
3/4 4-34 Insert "Specification" before 3.4.9.3.e in two places and change
3/4 5-1 Move "gallons" to before the parenthetical statement and relocate periods in 3.5.1.b r.nd 4.5.1.1.a.2).
3/4 6-3 Add "ani" af ter ites d.1) and change the coms: to a period after ites d.2).
3/4 6-7 Move the word "location" such that it is directly above items a, b and c. ,
l
ENCLOSURE 1 Page 7
- 1. Description pf the Change (Continued)
U 3/4 6-11 Insert "Specification" before 3.6.1.7b in ACTION statement b.
There is no apparent need to hyphenate the word "isolation" in 3.6.1.7a.
3/4 6-12 "La" and "Pa" should be "L," and "Pa " in Specification 4.6.1.7.2.
3/4 7-l' Move "Specification" to the next line to avoid confusion of 4.0.5 with 4.7.1.1.
3/4 7-3 center "Valve Number" over the appropriate section of Table 3.7-2 and add a period af ter the abbreviation of inches.
3/4 7-8 center the title above the lef t-hand column in Table 4.7-1. ,
t 3/4 7-19 Replace "** by "d" to avoid confusion due to two footnotes on the same item in Specification 4.7.8.b.
3/4 7-21 Relocate the "+" in the equation in Specification 4.7.8.e.3).
3/4 7-23 Change "B305" to "B003" and adjust the spacing of the column in Table 3.7-3.
3/4 7-31 Capitalize "specification" in ACTION b.
3/4 7-32 Change "3/4.7.13 (Continued)" to "PLANT SYSTEMS (Continued)".
3/4 8-1 Move "of fuel" from af ter the parenthetical statement to before the parenthetical statement.
3/4 8-2 i should be a superscript.
3/4 8-5 i should be a superscript in ites f. the word Specification should be inserted before 4.8.1.1.2 in footnote e, and .007%
should be written as 0.0071 in footnote d.
3/4 8-6 Correct the spelling of arachronized.
3/4 8-7 8 and di should be superscripts in ites 7).
3/4 9 9 Delete the underline from the word "and" in the footnotes.
3/4 8-22 Add " " between Motor and Operated in the title of Table 3.8-1 and indent the phrase "ACCVS outlet Header" in the table.
l 3/4 8-23 Add "(continued)" after Table 3.8-1. Add "
e ENCLOSURE 1 Pete 8 _
- 1. D,ese_ription of the change (continued) 7.81*
3/4 8-24 Add "(continued)" after Table 3.6-1. Add " " to Motor-operated.
3/4 11-1 Adjust the margin of the ACTION statements. l 3/4 11-2 capitalize "Waste Vater Retention Basin" in Table 4.11-1.
3/4 11-3 Indent the second itne of the definitions of equation terms in Table 4.11-1, table notations.
3/4 11-8 Add an "s" to Specification in ACTION b.
3/4 11-9 Add V0GTLE WITS - 1 & 2 and the pafe number to the bottom of the page.
4 3/4 11-10 Correct spelling of "omitted" and indent the second lines of the definitions of equation terms in Table 4.11-2.
3/4 12-3 Add V0GTLE WITS - 1 & 2 and the page number to the bottom of the page.
3/4 12-4 Add V0GTLE WITS - 1 & 2 and the page number to the bottom of the page and adjust the entries of Table 3.12-1 to align ur3er
- the headings of the columns as marked.
3/4 12-5 Add V0GTLE UNITS - 1 & 2 and the page nusbar to the bottom of l the page and adjust entry of ites 3.c as marked. '
3/4 12-6 Add V0GTLE UNITS - 1 & 2 and the page number to the botton of i the page and adjust entry 4.c as marked.
3/4 12-9 Add V0 m .E "NITS - 1 & 2 and the page number to the bottom of the page.
3/4 12-10 Add V0GTLE UNITS - 1 & 2 and the page number to the bottom of the page.
33/4 0-4 Delete page number as this is the title page for the Basos for !
3.0 and 4.0 an.1 delete the unit designator at the bottua of '
the page. '
B3/4 0-5 Delete tha page number and delete the unit designator at the bottos of the page.
EHOIASURE 1 Page 9
- 1. Description of the Change __(Continued)
S*K*.
33/4 0-1 Adjust the margin for this page. t 53/4 1-3 Change FtH to F2H under 3/4.1.3 ites 2.
n3/4 2-2 Change toF{H in the title line for 3/4.2.2 and 3/4.2.3 33/4 3-4 Insert the word "ani" between "instrumentation" and "corresponding" in Bases 53/A,.1.3.3.
33/4 4-7 Adjust the subscript of "1gg" such that it doesn't overlap the line below it.
B3/4 4-8 Capitalize Ef fective Fut' Power "ears.
B3/4 4-15 Change "10CTR50" to "10 CFR ! 0".
B3/4 5-2 "rT2 should be changesd to "2t 2 ,
Title pate for Bases 3/4.6 - Delete unnunhered page entitled "Basea for ft tion 3/4.6".
B3/4 6-2 Change "each" to "the" and change "el.3" to "c.1.3" in Bases section 53/4 6.1.6.
B3/4 7 1 Adjust the astgin of the definition of"SP" and "V and add a period at the end of the definition of Y.
33/4 7-7 Adjust margin of the title for Bases Section 3/4.7.13.
B3/4 6-1 Chaute "V0GT1.E-UNIT 1" to *V0GTI.E UNITS - 1 4 2" at the bottom of the page.
B3/4 8-2 Change "VOGTLE-UNIT 1" to "V0GTLE tNITS - 1 & 2" at the Wttom of tt page.
83/4 6-3 Change "V0GTLE-UNIT 1" to 'VMTLE 1 NITS - 1 & 2" at the bottom of the page.
3-6 Add V0GTLE UNITS - 1 & 2 and the page nuriber to the bottoa et the page.
6-1 capitaliae "Senior operator" and place the "d" synki as a Jupe rsc ript.
6-5 Change "not* to "no" in footnote **.
I
l ENCLO.M 2 't Page it. _
- 1. Description of the Change (Continued) fagg 6-8 Add "Yinal" between "Vogtle" and "Safety Analysis Report" in item e.
6-12 Add a period at the end of 6.4.2.8, item 1.
6-20 Change 3.3.3.10 and 3.3.3.11 to 3.3.3.9 and 3.3.3.10, respectively, in Specification 6.8.1.4 Justiff. cation for the Changes These changes represent editorial, format, spelling or is ntar changes that de not alter any requirements.
Pages Idfected See the Description of the Changes for affected page numbers.
. a om
ENCLOSURE 1 Page 11
- 2. Description of the Change This change incorporates Amendment 6 to the Unit 1 Technical Specifications into the Proof and Review copy of the Cosbined Unit 1 and 2 Technical Specifications. This amendment replaces organizational charts with more general organizational requirements.
Justification for the Change This change has been approved for Unit 1 and is also applicable to Unit 2. The change is consistent with NRC Generic Le'tter 88-06, "Removal of Organizational Charts from Technical Specification Administrative Control Requirements," issued on March 22, 1988. Additional information concerning the justification of tre change is found in Georgia Power letter SL-4752 of June 1, 1968 to the NRC, that requested the change, and in the :(RC letter of July 11, 1988, that issued the change.
Pages Affected XXII 6-8 6-1 6-9 6-2 6-12 6-3 6-13 6-4 6-14 6-6 6-24 6-7 6-25 0
4
- _ . = _
ENCLOSURE 1 Page 12
- 3. Description of the Change The Proof and Review copy of the combined Technical Specifications is revised to show changes to the Unit 1 Specifications that are applicable to the se and operating cycle of Unit 1 but are not applicable to the initial operating cycle of Unit 2. These changes incorporate different Moderator Temperature Coef ficient requirements, RWST Boron Concentration requirements, SHUTDOWN MARGIN requirements and high flux at shutdown alarm requirements.
Justification for the Change The Unit 2 requirements have not chan;ed, they remain the same as those approved for the initial operating cycle of Unit 1, which are described in the FSAR, addressed in the NRC's Safety Evaluation Report, and currently reflected in the Unit i Technical Specifications. This change to the Proof and Review Copy of the combined Technical Specifications incorporates changes only for Unit 1, second operating cycle. These changes were requested by Georgia Power Company letter SL-4682 of May 19, 1988, and are currently under review by the NRC. These changes are proposed to the Proof and Review copy of the combined Technical Specifications in anticipation of their approval for Unit 1.
pages Affected IV 3/4 5-1 3/4 1-3a 3/4 5-10 3/4 1-3b B3/4 1-3 .
3/4 1-3e B3/4 3-3 3/4 1-3d B3/4 5-1 3/4 1-4 B3/4 5-2 3/4 1-11 B3/4 6-3 3/4 1-12 B3/4 9-1 3/4 3-13
ENCLOSURE 1 Page 13
- 4. Description of the Change Add a footnote to page 3/4 3-21 that states:
"* See Specification 3.3.3.6" Justification for the Change The "*" is already placed on the table on page 3/4 3-21 but the footnote to which it refers was omitted. This footnote does not include or alter any requirements of the Technics 1 Specifications. It alerts the reader to the fact that the instrument to which it refers appears elsewhere within the Technical Specifications. This cross reference is made in a '
similar manner for other pages of this same table.
Page Affected 3/4 3-21 e
ENCLOSURE 1 Page 14 _,
- 5. Description of the Change Add specific references to Specification 3.4.9.1 to address separate heatup and cooldown curves for each unit. Revise Figures 3.4-2 and 3.4-3 to apply to Unit 1 only and add new figures for Unit 2. Add a new Figure 3.4-4b to address separate PORV setpoints for Unit 2 and revise Specification 3.4.9.3 accordingly. Revise the Bases for 3/4.4.9 to explain the reasons for separate Unit 1 and 2 heatup and cooldown curves.
Justification for the Change ,
None of the Unit i requirements have changed. The heat ap and cooldown curves for Unit 2 b3ve been developed using the same critercia and methodology as was used for Uait 1. The Unit 1 curves are not applicable to Unit 2 because the Unit 2 material has an initial RTNDT which is greater than that for Unit 1.
Pages Affected VIII 3/4 4-35a XVI B3/4 4-7 3/4 4-30 B3/4 4-8 3/4 4-31 B3/4 4-9 3/4 4-31a BS/4 4-9a 3/4 4-32 B3/4 4-10 3/4 4-32a B3/4 4-11 3/4 4e34 B3/4 4-12 3/4 4-35 B3/4 4-15 I
ENCLOSURE 1 Page 15
- b. Description of the Change Change 80*F to 85"F in Specification 4.7.6.a, and 850 CFM to 1500 CFM in 4.7.6.e.3.
Justification for the Change These changes were requested for Unit 1 by Georgia Power letter SL-4685 of May 19, 1988 and issued as Amendment 9 to the Unit 1 Technical Specifications by NRC letter of August 17, 1988 It raises the allowable control roes temperature by 5'F and increases the required pressurization flow rate in conjunction with the removal of portions of the partition betwcan the Unit 1 and Unit 2 areas of the control room. Since these portions of the partition will be removed prior to Unit 2 licensing, the change had to be made initially for the Unit 1 Technical Specifications.
The Unit 1 Technical 3poeification change also included additional requirements (in the form of footnotes) that apply only to Unit 1 and only during the period of time from the removal of the control room partition until licensing of Unit 2. Those footnotes do not need to be included in the combined Technical Specifications, because they will no longer be applicable af ter Unit 2 is licensed.
Pages Affected 3/4 7-14 3/4 7-16
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ENCLOSURE 1 Pase 16
- 7. Description of the Change Provide a space for insertion of Unit 2 Piping Penetration Area Filtration ard Exhaust System flowrate in Specification 4.7.'/.b.l.
Justification for the Change This value is to be provided for Unit 2 following completion of system preoperational testing.
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3/4 7-17
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ENCLOSURZ 1 Page 17 I
- 8. Description of the Change Delete "during shutdown" from Specification 4.8.4.2.c. ,
l 1 l Justification for the Change Some of the overload protection bypass devices can be tested at times other than during shutdown. This change was requested for Unit 1 by Georgia Power Company letter SL-4737 of June 7, 1988 and issued as Amendment 10 to the Unit 1 Technical Specifications by NRC letter of August 24, 1988 and is also applicable to Unit 2.
Page Affected 3/4 8-21
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ENCLOSURE 1 Page 18
- 9. Description of the Change Insert "Unit 1" af ter t'ae fi st word of Specification 5.6.1.1. Delete Specification 5.6.1.2 and ren taber 5.6.1.3 and 5.6.1.4 accordingly.
Replace "west" with "'Jnit 2" in Specification 5.6.1.2 and change 2.4% to 1.13% in 5.6.1.2.a. Delete "west" from Specification 5.6.1.3.
Justification for the Change The current project nomenclature for the spent fuel pools is to refer to them as the Unit 1 or Unit 2 spent fuel pool instead of the east or west spent fuel pool. The criticality analysis for the Unit 2 spent fuel storage racks has been resubmitted to the NRC in Georgia Power letter GN-1479 of August 12, 1988. The revised uncertainty allowance changap from 2.4% to 1.13% for the spent fuel racks in the Unit 2 spent fuel pool. Specification 5.6.1.2 was deleted because it was a duplicate of the information provided in Specification 5.6.1.3.
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ENCLOSURE 1 Page 19
- 10. Description of the Change Change "Appendix A of 10 CFR 55" to "10 CFR 55.59" in Specification 6.3.1 and add the following sentence at the end of the specification:
"Personnel who complete an accredited program which has been endorsed by the NRC shall meet the requirements of the accredited program in lieu of the above."
Justification of the Change NRC Ceneric Letter 87-07 stated that 10 CFR 5:5.59 content requirements (formerly Appendix A to 10 CFR 5.1) can be met with a performance based program for a facility as approve. by 4 the NRC. Such a change has been requested by Georgia Power Company in its letter SL-A744 of Jena 14, 1988 This change incorporates the wording of the proposed change to the Unit 1 Technical Specifications contained in that letter since it is anticipated that it will be approved by NRC prior to the issuance of the Unit 2 license.
Page Affected 6-6 i
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ENCLOSURE 1 Page 20
- 11. Description of the Change Replace "as well" with "as appropriate" in Specificatica 3.0.5.
Justification of the Change The terms "as well" could cause confusion to the reader of the Technical Specifications where parameters are identified for each unit specifically in either parentheses or in footnotes but not addressed specifically in the APPLICABILITY section. The combined' Technical Specifications were written with the intent that the APPLICABILITY section would be applied to each unit separately unless otherwise noted in either parentheses, footnotes, or the APPLICABILITY section as appropriate. It should be noted that the Specifications contained withis sections 3/4.11 and 3/4.12 are considered to apply to the Vogtle sitt and are not to be construed to apply to either unit specifically.
Page Affected 3/4 0-2 e
4 ENCLOSUnE 1 Pm 21
- 12. Description of the Chant.g Add a footnote applicabla to valves HV-8809A and B stating that either valve may be closed in F9DE 3 to allow testing pursuant to Specification 4.4.6.2.2.
- Justification for the Change This change has been requested for Duit 1 in Georgia Power Company letter VL-36, dated August 12, 1938, and is eldally applicable to Unit 2. The !
change clarifies that either valve HV-88d9A or B may be closed in MODE 3 l to allow leakage testing of RCS pressure isolation check valves. This test method has been reviewed and approved by the NRC as documented in Supplement 7 to the SER. The NRC requested that GPC apply for this Technical Specification change by letter dated April 15, 1988.
Pages Affected 3/45-4 B3/4 5-2 4
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ENCLOSUll',1 Pase 22
- 13. Description of the Change Replace "the" with "either" when referring to the spent fuel pool.
Justification For the Change As described in Georgia Power letter SL-4780 of June 22, 1988, the spent fuel storage area is a common area containing 2 spent fuel pools that are joined through the spent fuel cask pit. Fuel is expected to be moved from one pool to the other and in that sense the pools are common. The common Fuel Handling Building Post Accident Ventilation system serves the area. There may be times when one of the pools contains spent fuel and the other one is empty. In order to avoid any confusion, due to Specification 3.0.5, it is necessary to state that the operability requirements apply whenever spent fuel is in either pool.
Pages Affected 3/4 3-25 3/4 3-44 3/4 9-14
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ENCLOSURE 1 Pase 23
- 14. Description of the Change Change "neets the requirements of Regulatory Guide 1.12" to "meets thc.
recommendations of Regulatory Guide 1.12".
Justification for the Change The current Unit 1 Technical Specifiestions uses "recomendations" rather than "requirements" in referring to this Regulatory Guide in this bases section.
Pase Affected B3/4 3-4 I
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Q ENCLOSURE 1 Page 24
- 15. Description of the Change Insert the following statement into Specification 4.4.6.2.1, "The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4".
Justification for the Change It is not reasonable to perform a Reactor Coolant System (RCS) water inventory balance during transitions from COLD SHUTDOWN to HOT STANDBY.
The RCS water inventory balance should be performed when the RCS pressure is at 2235 + 20 psig since more accurate information about RCS leakage is obtained at full pressure (check valves seat bitter at full pressure).
Since RCS pressure isolation valve leakage has a direct affect on the RCS water inventory balance, the provisions of Specification 4.0.4 should not be applicable for entry into MODE 3 or 4 for Specification 4.4.6.2.1.d as well as for Specification 4.4.6.2.2. This chanSe Will provide consistency between the requirements of Specifications 4.4.6.2.1.d and 4.4.6.2.2.
Page Affected 2/4 4-21 1
DiCIhSURE 1 Page 25
- 16. Description of the Change Revise the label of the temperature scale in Figure 3/4-2a, 3/4-2b, 3/4-3a, and 3/4-3b to state "Lowest Indicated RCS Teoid Temperature
(*F)".
Justification for the Change This change is intended to emphasize that the lowest indication of RCS temperature should be used in conjunction with this figure. The change does not represent a new or different requirement. It is intended to avoid any question that might be raised concerning the use of the figure.
Pages Affected 3/4 4-31 3/4 4-31a 3/4 4-32 1 3/4 4-32a l
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- 17. Description of the Change Replace "be" with either "place Unit 1", "Place Unit 2" or "place the applicable Unit" as appropriate in ACTION statements a, b, and c. An additional change to ACTION c is proposed to change "other than ACTION a and b" to "other than that defined in ACTIONS a and b above".
Justification for the Change Tne use of "place Unit 1". "place Unit 2" or "place the applicable Unit" clearly indicates the aa.ic to which the ACTION should be applied. The proposed change to ACTION c better defines the situations when ACTION c should be applied. This change is requested to enhance the readers' understanding that ACTIGN e applies to the situation where there is abnormal degradation of the structural integrity which is not addressed in either ACTION a or b.
Page Affected 3/4 6-8
ENCLOSURE 1 Pase 27
- 18. Description of the Ch g Delete footnote ##.
Justification of the Change This footnote provided a temporary exemption to the requirement to verify mercaptan prior to fuel addition to the diesel fuel oil storage tank.
This exemption was needed for Unit i but is not required for Unit 2 -
because the mercaptan verification program is now in place.
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DICLOSURE 1 Page 28 i 19. Description of the Change Add the word "Common" or "Common System" as appropriate, to Specification requirements which are common to Unit 1 and Unit 2 per Technical Specification 3.0.5 and change unit designators f rom "1" to "1/2" for components that are identical on both units, as described below.
3/4 3-50 Add "(Common System)" to title 3/4 3-66 Add "(Common)" to item 3c Flow to Blowdown Sump 3/4 3472 Add "(Common)" to item la and Ib.
3/4 8-14 Change tage from 1 to 1/2 in LCO ,
Justification of the Channe Making the Technical Specifications a conson document that accurately describes the systems on both units requires all Specifications that ;
apply to both units to be designated as "Common" (see 3.0.5). Equipment ,
tags that are called out in the specification should be designated as "1/2" if identical equipment exists on each unit. Common instrumentation is indicated by an instrument number beginning with the letter "A" in the ,
current Unit 1 Technical Specifications. For these cases the word '
"Common" has been added per Specification 3.0.5.
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Pages Affected Affected pages are lir,ted in the Description of the Change.
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ENCLOSURE 1 Pase 29
- 20. Description of the chanae The Proof and Review copy of the Combined Technical Specifications did not include figures. The proposed figures are added.
Justification for the Change These figures are the same as the current Unit 1 figures and are also applicable to Unit 2. The unit designator on the bottom of the page has been changed to indicate that it is part of the Combined Technical Specifications, and some corrections to the use of capitalization and title locations have been made.
Pages Affected 2-2 3/4 1-22 3/4 2-3 3/4 2-5 3/4 4-26 3/4 7-24 B3/4 2-3 5-2 5-3 i
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3 ENCLOSURE 2 TO LrrIER GN-1483 l Open Itess To Be Provided to the NRC l
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- 1. Camera Ready Figures.
- 2. Eductor test flow rates for 4.6.2.2.d.
3'. Test flow rate for Piping Penetration Area Filtration and Exhaust System for 4.7.7.
4 Provide revised action statements in the instrueentation and HVAC Specifications to reflect the combined control room design.
- 5. Addition of Unit 2 rooms to Table 3.7-3, Area Temperature Monitoring. l e
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