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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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~ ' Georgia Power Company o Post Office Box 282 Wayntsboro, Georgia 30830 Telephone 404 554-9961 404 724 8114 Southern Company Services, Inc.
Post Offace Box 2625 Birmingham, Alabama 35202 Telephone 205 870 6011 VOgtie Project l
1 1
s l
July.7' 1987 l
U.S. Nuclear Regulatory Commission File: X4BJ01 Attn: Document Control Desk Log: GN-1380 Washington, D.C. 20555 NRC DOCKET NUMBER 50-425 CONSTRUCTION PERMIT NUMBER CPPR-109 V0GTLE: ELECTRIC GENERATING PLANT - UNIT 2 FIRE SUPPRESSION SYSTEM CHANGES Gentlemen:
Enclosed for your review are proposed changes to certain portions of the Vogtle Unit 2 Fire Suppression System design, briefly discussed with a member of your staff. These changes . will not compromise the-ability of the fire protection systems to perform their intended functions during a fire event. These changes include:
- 1. Revised sprinkler hanger design based on. the results of seismic testing for qualification purposes rather than analytical means as done previously.
- 2. Revision to the criteria for placement of in-tray sprinkler protection to include them only in the cable spreading! rooms.
- 3. Revision to the fire suppression flushing procedures, which provides an alternate to flushing of sprinkler system piping.
Attachments 1, 2 andi 3 provide detailed information regarding .each of these . changes. Attachment 4_ provides - a . draft of the 'FSAR changes, which will .be incorporated into a future amendment.
8707150162 870707 PDR l F ADOCK 05000425 0
. 0k '
PDR . ,; :
I
'Vogtle Electric Generating Plant ~ July 7,1987 :I '
J Fire Suppression System Changes- Page Two Fi1e:. ' X48J01 Log: GN-1380 d
Should you have any questions, please inquire. ,
Sincerely,.
.k. ,
'J. A. Bailey
- Project Licensing Manager JAB:Je-
= Attachments xc: .NRC Regional Administrator NRC Resident Inspector l J.lP. O'Reilly .l R. E. Conway 'I L.'T. Gucwa l R. A. Thomas J. E. Joiner, Esquire B. W. Churchill, Esquire M. A. Miller (2) r- G. Bockhold, Jr.
l R. Goddard, Esquire l
[ D. Feig i R. W. McManus '
Vogtle Project File ;
1 i
I a
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_ _ _ _ _ _ = _ _ _ _ _ _ _ _ __. _ _ _ _ _ _ _ - - _ ___
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ATTACHMENP 1 FIRE PRCTTECTION SPRIIELER HAtGER CHAFEES l l
FSAR subsection 9.5.1.3 currently identifies that the ccuponents of a fire protection system are analytically checked to assure they will not collapse when subjected to accelerations of the design basis earthquake.
The Unit 2 fire protection systens will be suspended with rod type hangers rather than rigid type supports which were used on Unit 1. The Unit 2 systems have been modeled and seismic testing has been performed instead of using analytical means to show they will not collapse when subjected to seismic acceleration of a design basis earthquake. This support arrangement naintains i seismic 2/1 considerations. l The Unit 2 fire protection hanger arrangement provides VEGP with the following i advantages:
o Sprinkler spray pattern blockages incurred frcm rigid type (tube steel) '
supports will be reduced. !
o Sprinkler heads will require less frequent relocation while providing better spray coverages.
The follcwing are excerpts frczn the seismic test report. This report is attached for your review. 4 i
SEISMIC TEST INTRODUCTION AND OVERVIEW l The Fire Suppression Systems (FPS) installed in Unit 1 were designed and constructed to meet strict support stiffness and piping deflection criteria. In safety related areas, the FPS are classified as seismic twtM:ver-one (2/1) l i systems. Their integrity chring and after a seismic event cannot jeopardize the f l
- integrity of adjacent equignent and structures which may be essential for safe j
! shutdown of the plant after a seismic event.
j l
A recent experimental effort performed by ANCO Engineer, Inc. (AICO) for Bechtel '
Western Power Corporation (BWPC) successfully derronstrated that the rod- {
suspended FPS at the South Texas Project (STP) were capable of withstanding j simulated seismic events in excess of predicted design criteria without I collapse. These ' flexible" supports were demonstrated to have a ductile capacity far in excess of their capacity predicted by linear elastic methods. j lbne of the test systems collapsed under extreme loading. 4 Based on the experience gained during the STP project, the expectation was excellent that FPS systems designed to IFPA-13 ctandards, which included sway i bracing as discussed in Section 10 of the standard, would be capable of :
withstanding postulated seismic events at the Vogtle Unit 2. It was further j
.mvisioned that incorporating a "pinrad" connection at the top of the supports i i (anchor elevation) would eliminate potential low-cycle fatigue failures. Other l concerns evaluated were the determination of required rattle space, the loads l transferred to anc111ary structures and the affects of inpact and collision on l piping integrity.
l 1-1 4
l
'Ib address these ccncerns, verify design ecocepts, establish design argins and determine design ecostraints, three segments of actual systems (as installed in VEGP t. hit 1) were asserrbled and tested an AN00's R-4 Shake Table. The three systeme were chosen to be representative of' actual installed systerre. Eachi system ccnsistad of a feed min asprmimately forty feet in length with several i branch lines and a simlated deluge valve ccnnecticn. Each system's supports l and sway bracing were located using WPA-13 reocrrmendaticos. All supports l iri.er rgeted standard off-the-shelf hardware, including swivel connecticos to l act as pins at the tcp of the supports.
Testing took place at A!OO Engineers, Inc. test facility in Culver City, California between 24 March and 2 April 1987. 'Ihe three test systems were fitted with sensing instrumentation to detezmine response acceleraticos, displacements and loads during simlated seismic events. 'Ihe.three test systems were fitted with the support hardware intended for use at the site and subjected .
to five Operating Basis Earthquakes (CBE) and a Safe Shutdown Earthquake (SSE) . I N3 piping separated and no supports failed during these events. Hydrostatic '
testing, as per WPA-13, Section 1.11, was performed prior to and after the first CBE test to demonstrate functionality. ' Next, the three test systems were subjected to a 1.2 x SSE event and lastly a 1.4 x.SSE event to derrmstrate survivability and to establish a design rrazvin. System fragility levels were l l determined to be in excess of shake table capacity and far in excess'of site j enveloping seismic design criteria.
1
'IEST CONCLUSIONS Based on the results of the VEGP specific test, the fire protection systerns l
2
~ designed to WPA 13 standard using red t.ype hangers and sway bracing have been derncostrated to be capable of withstanding postulated base input motions in excess of OBE and SSE requirements. The test has preven that seismic 2/1 capability is maintained.
1 1-2 M0587047/VT
ATIACHMENT 2 FIRE PROTECTION IN-TRAY SPRINCLER CHAKES FSAR Subsection 9.5.1.2.1.4 currently identifies that electric cable tray arrangements will utilize autcrnatic suppression systems located above the trays and FSAR Table 9.5.1-9 identifies that cable tray protection uses the guidance of NFPA 15 with closed head spray nozzles.
The Unit 2 sprinkler design will be based on the following: -
- 1) The area coverage boundaries for suppression systens will be in accordance with that identified on fire area drawings (FSAR figures 9A -
1 through 9A-46) .
- 2) In the cable spreading rooms, in-tray directional spray nozzles will be provided. Area protection at the ceiling will provide coverage for the first three safety-related trays in a vertical stack and in-tray protection will be provided for the remaining safety related trays starting with the 4th tray in the stack and ending with the last tray in the stack. (Typical Unit 1 design) .
- 3) For electrical cable chases and tunnels, sprinklers will be provided at the ceiling designed to discharge .3 gpn per square fcot over the nest renote 3000 square feet or area within the cutoff fire boundaries whichever is less.
- 4) For other areas containing three safety related cable trays or less in a vertical stack, sprinklers will be provided at the ceiling designed to discharge .21 gpm per square foot over the nest remote 1500 square feet or area within the cutoff fire boundary whichever is less. (Typical Unit 1 design).
- 5) For other areas containing more than three safety related cable trays in a vertical stack, sprinklers will be provided at the ceiling designed to discharge .3 gpn per square foot over the nest rmote 3000 square feet or area within the cutoff fire bourrlaries whichever is less.
Our insurance underwriter (Nuclear Mutual Limited) has agreed during a walkdcwn l of Unit 1 areas that because of the light to nederate cable tray fill densities, the in-tray nozzles could be eliminated if the ceiling density was increased in accordance with the criteria listed above.
The use of autanatic sprinklers at the ceiling, without in-tray nozzles, has been accepted at other nuclear plants.
The Unit 2 sprinkler design neets the guidelines of CMEB BTP 9.5.1 section C.5.e by providing an adequate level of suppression for cable tray arrangements.
I 2-1 l M0587047/VT
_-_ - Q
q j i ATTACIDENT 3 i
Fim Suppression Systm Flushing Changes FSAR table 9.5.1-9 identifies a deviation to NFPA-13 subsection 1-11.1'.1 regarding connection of sprinkler system piping prior to ccupletion of. flushing of underground mains and lead-in connections. - The underground main and lead-in piping was flushed while connected with the sprinkler systs. After the header piping was verified clean, the sprinkler systems wem flushed in accordance with j approved flush procedures. This deviation was identified as open item 7C of the {
Safety Evaluation Report and subsequently closed in supplement 4 of the SER.
For Unit 2, to assum that foreign material does not enter the suppression system the following steps will be performed when connection is made to lead-in.
piping:-
1
- 1) A test blank will be installed between the system isolation valve and l preaction sprinkler. valve prior to' system installation.. I
- 2) 'Ihe test blanks will be visible when installed and controlled through the use of drawings, procedures,~and inspections. j 1
- 3) Test blanks will be removed after header piping 'is verified clean. I This alternate to NFPA 13 requirements for Unit 2 provides reasonable assurance that foreign materials have been rmoved frun the underground piping system and that sprinkler systems are free of foreign material. q 1
i l
3-1 M0587047/VT l
-m DRAFT FSAR CHANGES ATTACHMENT 4 SH, 4 - l
. VEGP-FSAR-9 1
l With the exception of short runs.of flexible nonmetallic ;
conduit, wiring runs outside of cable trays are enclosed in 23 !
metallic conduit to reduce the exposure of the cable to ignition. I Several approaches are used to limit the, hazard presented by combustible cable insulation. Electrical cable. construction, as =l25 a minimum, meets the Institute of Electrical and Electronics Engineers (IEEE) 383-1974 flame test, except in a limited number l23 l of places, as outlined in appendix 98. Additional fire l protection for concentration of cables is provided as required. I Cable insulating materials which do not create hazardous concentrations of corrosive or toxic gas when overheated or when ,
exposed to flames are used to the extent practicable, as i detailed in appendix 9B.
Cable tray construction materials are noncombustible. Cable trays and conduit are used for cables only; miscellaneous storage is not permitted in cable trays, raceways, trenches, or-culverts. Piping for flammable or combustible liquids or gases is not permitted in areas of heavy cable concentrations. l23 Interior transformers are of the dry type.
- Cable and cable tray penetrations of fire barriers (vertical l and horizontal) are sealed (fire stops)' to give protection at j least equivalent to that required for the fire barriers. '
3 Fire protection for areas containing cable trays is achieved in i the design of the plant through a combination of the following i (detailed in appendix 9A): )
A. For early warning of fire conditions in the cables, smoke detectors are provided for all safe shutdown cable tray runs throughout the plant. Line-type detectors are provided in safety-related cable trays inside containment and those cable. trays containing 23 25 pressurizer heater cables inside containment.
B. For control and minimization of fire effects, either in case of significant cable fire loading within the same safety train or for congested runs of cable trays, automatic suppression systems located above the trays and manual backup capabilities are provided.
je"- 23 25 INSERT A ,
Amend. 23 4/86 9.5.1-11 Amend. 25 9/86
,e.
. i SH.
4- 2 l
VEGP-FSAR-9 system heads open upon a rise of ambient temperature to the melting point of fusible links on sealed sprinkler heads; thus, fire extinguishing flow through the spray heads is established.
Once initiated, system operation is terminated by manually ,
23 shutting a local valve at the preaction valve.
Inadvertent manual or automatic operation of the preaction valve, due to release failure, is detectedLby a system actuated alarm, The impact of inadvertent operation of suppression systems is minimized through the following design features: 23 e All suppression systems in safety related areas are l either Halon or pre-action sprinkler systems j
, .,, ___,_s,__ ............_4. ...__.., , ..+.m.;... 4.
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2EEi3iHi? dei--C WSERT B '
e Redundant safe shutdown equipi$ent is located in separate l23 fire areas to the extent practical I e Sprinkler heads are passive components, and only one l23 l head is expected to fail at any one time. I 15
- e Drip-proof motors are installed on safety-related l23 pumps.
I 3
e Safety-related electrical cable design allows water spray on cables in tray without electrical cable 25 faulting.
1 Where the safe shutdown analysis takes credit for distance j separation between redundant safe shutdown components in the i same fire area, the existence and orientation of intervening 23-structural components are reviewed in consideration of the possibility for damage during manual fire fighting activities (i.e., fire hose stream damage).
l Failure of one detector to sense fire results in no adverse l25 effect, since, in general, alternate detector (s) remain functional to sense the fire and release the system. In the event of a pipe break, no adverse effect results, since the system is dry within.
9.5.1.2.2.10 Water Sprav Deluce. Water spray system operation -
is initiated by an electric fire detection device. This sensor .
detects a fire and releases a tripping. device to open the deluge valve, thus supplying water under pressure to the open spray heads. Actuation of the fire detection device also initiates a local alarm and registers the alarm condition en an Amend. 15 3/85 Amend. 23 4/86 9.5.1-17 Amend. 25 9/86
SH,4-3 VEGP-FSAR-9 nw Insulation with UL ratings of 25 or less for flame spread, fuel contributed and smoke generated, is l28 provided for ductwork above the ceiling of the control '
room. "*
D. Fire suppression or extinguishing agents which result in corrosive products upon pyrolysis are not employed i to protect essential circuitry. '
Redundant engineered safety features (EST) components are physically remote and are separated by fire l barriers.
l In the unlikely event that the fire protection system does not function, fire barriers prevent the spread of fire to other areas. Safe shutdown is attained and maintained, during or after such an improbable fire in i an ESF area, by the use of the redundant components of !
the necessary safe shutdown-related systems. Thus, fire in an ESF area will not prevent a safe shutdown.
'E . The components (and supporting structures) of the fire protection system, the collapse of which could result
'_ in loss of a required function of plant structures, systems, or components important to safety are analytice.lly checked to determine that they will not l15 E
collapse when subjected to seismic accelerations of the .
l desicm b? s earthquake.
4'~ INSERT' l F. Wet pipe sprinkler systems are not installed in ESF j rooms so that inadvertent operation or failure would '
not impair safety systems. Preaction sprinkler systems are installed to mitigate these failures.
The fire 'ighting f water piping running from the source serving the preaction sprinkler systems is filled and pressurized with water up to a shut control valve, located outside the room to be protected. The pipe is dry between the shut control valve and the spray or sprinkler heads. Thus, flooding within the area to be protected due to piping failure inducted by seismic events, explosions, pressure, or missiles is precluded. Moreover, additional protection is realized in that the fire protection piping is analytically checked, as discussed above, and is protected from missile and explosion debris by the barriers that protect equipment within the area from missile damage. Inadvertent manual operation of a preaction sprinkler valve is detected by a system trouble alarm. No adverse effects result since there is no flow as the sprinkler heads remain sealed.
9.5.1-24 Amend. 15 3/85 Amend. 28 11/86 -
R
,SH,4.4 VEGP-FSAR-9 TABLE 9.5.1-9 (SHEET 2 OF 16)
- 2. Volume verification will be performed using^available < '
tank level measuring equipment instead of weighing:the tank. This method provides an accurate indication of tank volume and meets the intent of section 1-11.1.6 which requires a check of agent " quantity."
NFPA 13-1983, STANDARD FOR INSTALLATION OF-SPRINKLER SYSTEMS l23 General: Due to the complexity.of the plant, the determination of compliance with NFPA 13 is based.in part
~
28 upon the professional judgment of qualified fire protection engineers.
Subsections C-11.1: The underground main and lead-in piping will not be flushed before connection is made to the j
sprinkler piping. The underground main and lead-in piping will be flushed, in accordance with approved VEGP flush procedures, while connected with the sprinkler system.
Measures will be taken and controlled via the flush- 23 procedure to prohibit the introduction of foreign material i into the sprinkler piping during main and lead-in i flushing. The sprinkler systems will then be flushed in 1 accordance with the flush procedure after the header piping ,
is varif4ad cleaned.
FI NSERT DJ
' Subsection 1-11-2.5: Test blanks will not be painted or-numbered, however, they will be strictly controlled by procedure which requires removal verification.
Subsection 2-2.1.2.4 The water allowance for outside hose is not added to the sprinkler and inside hose requirements for all buildings, since some buildings are not accessible for outside hose usage, i.e., Auxiliary Control Fuel ,
Handling and Containment buildings. However, the design at !
Plant Vogtle is such that no given system plus hose stream will exceed the requirements of CMEB 9.5-1 section C.6.b.
Subsection 2-4: This' subsection is not applicable because 28 gravity tanks are not used at VEOP.
Amend. 20 12/85.
Amend. 23 4/86 Amend. 28 11/86-s
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I Insert A to FSAR subsecticn 9.5.1.2.1.4 Item B
'Ihe autanatic sprinkler systems consist of ceiling sprinklers supplemented by i cable tray protection utilizing the guidance of WPA-15. '
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For Unit 2, with the excepticn of the cable spreading rocms, the autct:stic .l sprinkler systens ccosist of ceiling sprinklers. 'Ihe automatic sprinklers in the cable spzsading zozns ccasist of ceiling sprinklers supplerrented by cable tray protection utilizing the guidance of WPA-15. i 1
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l 4-8 o-_______________________________-.-------------.. - - - - _ . _ _ _ _ _ _ _ . . _ _ . - _ _ _ _ _ _ _
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1 Insert B to FSAR subsection 9.5.1.2.2.9 )
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1 The header piping ard supports up to and including sprinkler system isolation i valves and all sprinkler system piping supports in proximity of safety related equignent are designed for SSE loads. .
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Insert C to FSAR subsection 9.5.1.3 (E)
Portions of the Unit 2 fire protection systems are mcdeled and subjected to seismic testing rather than checked analytically to shcw they will not collapse when subjected to seismic accelerations of the design basis earthquake. Where testing methods are saployed on the Unit 2 fire protection systems, . they will utilize NFPA-13 hanger and sway bracing designs. This hanger arrangement ccuplies with the seismic Category 2 over 1 requirements of FSAR subsection 3.7.B.
4 1
4-10
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l LM D to FSAR table 9.5.1-9 (sheet 2 of 16) l
}
For Unit 2 an alternate to flushing sprinkler systerns will be incremented to !
ensure foreign sterial does not enter the suppression system by installing a test blank at the system isolatica valve at tine of sprinkler piping installation. This will prohibit foreign naterial frun entering the sprinkler system piping should the isolation valve be accidentally opened. Af ter the flushing of lead-in ccrinacticms is ccupleted, the test blanks will be raroved in accordance with approved VEGP procedures.
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et 4-11 o____________---______________. _ _ _ _ _ _ _
Insert E to FSAR Appendix 9B section C.1.b The header piping and supports up to and ircluding sprinkler system isolation valves and all sprinkler system piping supports in proxhnity of safety related equirrnent are designed for SSE Icads.
4-12 l
M0587047/VT
~
Insert F to FSAR Appendix 9B section C.1.C.4 1
1b withstand a natural phencanena, the indoor fire protection header piping i systen up to and including sprinkler system isolation valves and the sprinkler l system piping in proximity to safety related equigamnt is designed for SSE 1 loads, and wind forces have been implemented into the outdoor design features.
The hanger criteria used meet or exceed the requirements of WPA in all seismic category 1 structures.
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4-13 M0587047/VT
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