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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
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Georgia Power Company
, , 333 Piedmont Avenue Atlanta. Georgra 30308
,p Te:ephone 404 52fc3195 Mail [ng Address 40 Inverness Center Parkway Post 0%ce Box 1295 ,
Birmingham, Alabama 35201 Telephone 205 B60-5086 J. D. Woodard l'e mo!NM 'xtoc num Senior Vece President August 23, 1996 l LCV-0603-R Docket Nos. 50-424 1 50-425 ;
TAC Nos. M92131 1 M92132 1
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk i Washington, D. C. 20555 Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT I PROPOSED CONVERSION OF Tile UNIT 1 AND 2 TECHNICAL SPECIFICATIONS BASED ON NUREG-1431 On July 25.1996, a telephone conversation was held between Mr. J. D. Woodard of Georgia i Power Company (GPC) and Mr. Steven A. Varga of the NRC concerning our request for an extended allowed outage time (AOT) for the emergency diesel generators (DGs) as documented in our May 6,1996 letter (LCV-0603-P) and as supplemented by our June 17, 1996, letter (LCV-0603-L). During that telephone conversation, the NRC presented specific I conditions which, ifimplemented at the Vogtle Electric Generating Plant (VEGP), would result in NRC approval of our requested extended DG AOT. The following is a statement of those conditions and our response.
The time of year that the extended DG AOT may be used must be limited so as to minimize the potential for weather-related events such as hurricanes occurring while a DG is i
inoperable. Enclosed are marked up pages from the VEGP Unit 1 and Unit 2 improved '
Technical Specifications (TS) and Bases that accompanied our June 17,1996 letter (Enclosure 1). Limiting Condition for Operation (LCO) 3.8.1 has been marked to show a new Required Action B.l. Upon entry into Condition B ("One DG inoperable"), Required Action B.1 requires verification that the calendar date does not fall on or within the period
! July 15 through November 15. If at any time while the DG is inoperable the date does fall I within this period, Condition C must be entered, and the DG must be restored to operable l status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from entry into Condition C. This will effectively prevent preplanned main'enance that might involve an extended I)G AOT that falls on or within this period of time.
9608270368 960823 PDR ADOCK 05000424 P PDR i
1 l
U. S. Nuclear Regulatory Commission
~ ' LCV'0603-R Page 2 l
l The TS will also be revised to require that one of the enhanced black-start combustion turbine generators (CTGs) be verified functional by starting it and verifying that it achieves I
l steady state voltage and frequency. This must be performed either within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to l removing a DG from sersice for an extended DG AOT, or within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after removing the l l DG from service for the extended AOT. See Required Action B.6.1 in the enclosed marked up pages. This Required Action is contingent on the combined reliability of the enhanced ,
l black-start CTGs having been demonstrated and maintained to be 2 95 %. Prior to
' l demonstrating the reliability of the enhanced black-start CTGs, or in the event that the combined reliability falls below 95 %, a CTG must be started and allowed to run !
continuously in the event that a DG is out of service for an extended AOT. In this case the l CTG must be started prior to removing the DG from service for preplanned maintenance that l would require the DG to be out of service for an extended AOT. For unplanned DG l i
inoperabilities requiring an extended AOT, the CTG most be started within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after removing the DG from service. See Required Action B.6.2 in the enclosed marked up pages. ,
As stated in the enclosed proposed Bases for Required Action B.6.2, any one of the six CTGs l may be started for the purposes of Required Action B.6.2. If a CTG is allowed to run while a >
DG is out if service, it is not necessary that the CTG be one of the two enhanced black-start CTGs. In addition, the proposed Bases for Required Action B.6.2 state that if the running CTG fails, one of the remaining CTGs must be started within I hour. In the unlikely event l that no CTG can be started, Condition C would apply and the inoperable DG would have to !
be restored within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entry into Condition C. !
l In order that a DG may be removed from service for an extended AOT, the standby auxiliary transformer (SAT) must be available. This requirement is expressed as Required Action B.2 !
of LCO 3.8.1. The NRC staff has expressed concern that for the SAT to be available it must be energized via the underground line from it's switchyard. The Bases for LCO 3.8.1 define SAT availability as, in part, that the SAT must be operable in accordance with plant j procedures. " Operable in accordance with plant procedures" means that, as a minimum, the SAT would be energized via the underground line from it's switchyard.
If a DG is to be removed from service for an extended AOT without requiring that a CTG be operated throughout the time that the DG is inoperable, then the enhanced black-start CTGs must have a demonstrated reliability of 2 95 %. The reliability of the enhanced black-start l CTGs will be demonstrated by performing a minimum of 20 starts and load-runs of at least I hour on cuch enhanced black-start CTG. The black-start diesel generator will be tested separately, and it will also be subjected to a minimum of 20 starts and load-runs of at least 1 l hour. The combined reliability of the two enhanced black-start CTGs and the black-start diesel generator must be 2 95 %. A successful start will be defmed as a CTG achieving ;
, steady state voltage and frequency within acceptable limits and time. For the purpose of ;
supporting a 14-day AOT, the acceptable time is dermed as I hour. A successful load-run
l U. S. Nuclear Regulatory Commission
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- Page 3 l 1 >
l l will be declared if the CTG runs with its output breaker closed for I hour. The combined reliability will be calculated as follows: I 4
Combined reliability = [(Reliability of CTA + Reliability of CTB)-(Reliability of
- CTA* Reliability of CTB)]* Reliability of black-start DG The reliability of CTA or CTB will be defined as
- Reliability of CT(A/B) = Start Reliability
- Load-run Reliability Where:
, Start Reliability = Number of successful starts / Number of start demands Load-run Reliability = Number of successful load-runs / Total number ofload-run l demands The reliability of the enhanced black-start CTGs (including the black-start diesel generator) will be maintained by quarterly testing. A commitment to quarterly testing appears in the proposed Bases for new Required Action B.6.1 in the enclosed marked up pages.
The next condition involves establishing procedures for use of the enhanced black-start CTGs and support systems. Additional guidance was provided by the NRC on the afternoon of July 25, and this guidance stated that "the licensee must develop procedures to black-start a CT and provide power to the 4.16 kV safety bus within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> In our May 6,1996, letter LCV-0603-P, we made the following commitment:
e If a CT black-start appears to be necessary during the extended EDG A0T, e.g.
Impending extremely severe weather or the Southern Electric System has been identified as being potentially unstable due to events in the system, thefollowing action l willbe taken.
An operator will report to The CT site and prepare for a CT black-start by placing at least one CT on turning gear. Under these conditions, a CT has been demonstrated to be capable of being black-started within I hour. The alignment of the CT switchyard / SAT line to VEGP for safe cool down purposes can be performed in ;'
parallel with a CT black-start and has also been accomplished within I hour.
GPC will have procedures in place to implement the above commitment prior to entering an extended DG AOT. In addition,in our June 17,1996, letter LCV-0603-L, we committed to demonstrate the complete enhanced black-start generation capability at least once per 18 months. Therefore, the appropriate Operations personnel will be trained in the use of these
U. S. Nuclear Regulatory Commission
,
- LCV-0603-R Page 4 procedures, and the procedures will be available to the appropaate Opentions personnel during a 14-day DG AOT.
Finally, the NRC stated that we must have a configuration isk management program in place prior to entering an extended DG AOT. NRC guidance provided later on the afternoon of July 25 requested that GPC include the SAT in the "lPE Tool" and consider "more than the top 500 sequences." (The existing "IPE Tool" does not include the SAT and/or the CTGs, and all of the calculated risk indicators in support of the proposed extended DG AOT to this point have considered only the top 500 sequences.)
It is cur intention to begin work on an updated IPE model this fall with completion projected for the middle of 1997. This updated model will include the SAT and the CTGs, and it will generate cut-sets as opposed to sequences. It can be used to evaluate plant configurations fbr risk significance, and it will be used to develop a plant-specific equipment out-of-service (EOOS) model based on EPRI methodology. The EOOS model is designed fbr evaluating plant configurations for risk significance, and we project that it will be in place by the end of 1997. Given the above plan for developing more useable risk evaluation tools, GPC is reluctant to divert resources for the purpose ofincluding the SAT and the CTGs in the "lPE Tool" and for evaluating more than the top 500 sequences. However, in the interim, GPC can use the "IPE Tool" to evaluate the risk significance of plant configurations given that a DG is ineperable fbr an extended period. Enclosure 2 documents the results of our evaluation of the impact on risk due to the proposed extended DG AOT using the existing IPE model.
GPC will develop a program to assess changes in core damage frequency associated with applicable at-power plant configurations when a DG is out of service for an extended period.
This program will use the "lPE Tool" in the interim for assessing the risk significance of plant configurations, and it will adopt the updated risk evaluation tools (as discussed above) as they are put into place. This program will be in place prior to removing a DG from service for an extended AOT, and it will include:
e training of appropriate personnel, e provisions 1br identifying plant configurations and the evaluation of risk against established thresholds; and
. provisions Ihr evaluating changes in overall plant core damage risk resulting from unplanned maintenance activities.
Please note that GPC considers the preceding discussion to be a complete set of commitments regarding the proposed extended DG AOT. Therefore, this letter supersedes all prior letters and verbal agreements as they relate to this subject.
l l
U. S. Nuclear Regulatory Commission
' LCV-0603-R Page 5 in our June 17,1996 letter, we transmitted a complete set of TS and Bases. Since that time, an error was identified in Table 3.3.1-1, page 5 of 8. Function 16.e. The Allowable Value and Trip Setpoint for Power Range Neutron Flux, P-10 are incorrectly shown as s 12.3 %
and s 10 % respectively. The correct values are 2 7.7 % for the Allowable Value and 210
% for the Trip Setpoint. These values are consistent with the current TS requirements. The incorrect values were simply the result of a typographical error. In addition, a limited number of editorial corrections of a non-technical nature are included. For your convenience, marked up pages showing these corrections are provided as Enclosure 3.
Enclosure 4 is a complete clean typed copy of the TS and Bases reflecting the changes discussed in this letter.
The changes to the TS proposed herein do not alter the conclusions of the evaluations I performed pursuant to 10 CFR 50.92 that have been previously docketed with respect to the
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conversion of the VEGP TS based on the improved standard TS. j Finally, GPC regrests that the preceding proposed responses to the conditions of the j aforementioned July 25,1996, telephone call receive a timely review so that the license i amendments can be issued by September 23,1996, with implementation within 150 days of issuance.
Sincerely, i k
D. Voodard JDW/NJS Enclosures xc: Georyia Power Comnany hir. C. K. McCoy (w/o Enclosure 4)
Mr. J. B. Beasley, Jr. (w/o Enclosure 4)
Mr. M. Sheibani (w/o Enclosure 4) j NORMS (w/o Enclosure 4) ;
U. S. Nuclear Reyulatory Commission Mr. S. D. Ebneter, Regional Administrator (w/o Enclosure 4)
Mr. L. L. Wheeler, Licensing Project Manager, NRR (all Enclosures)
Mr. C. R. Ogle, Senior Resident inspector, Vogtle (w/o Enclosure 4)