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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, Geor0ia 30308 Tdephone 404 526-3195 Mailing Address 40 invemess Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Telephone 205 868 5086 J. D. Woodard tv s %n, sync symm l Senior Vice President June 17, 1996 l
LCV-0603-L l i
Docket Nos. 50-424 ;
50-425 TAC Nos. M92131 M92132 U. S. Nuclear Regulatory Commission i ATTN: Document Control Desk l Washington, D. C. 20555 Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT PROPOSED CONVERSION OF THE UNIT 1 AND UNIT 2 TECHNICAL SPECIFICATIONS BASED ON NUREG-1431 By letter dated May 1,1995, (LCV-0603) Georgia Power Company (GPC) proposed to amend the Vogtle Electric Generating Plant (VEGP) Unit 1 and Unit 2 Technical Specifications (TS). The proposed changes would modify and convert the existing VEGP TS to the improved TS for Westinghouse plants based on NUREG-143L By letters dated September 22,1995, (LCV-0655), November 20,1995, (LCV-0670). December 21,1995, (LCV-0603-D), January 30,1996 (LCV-0603-E), March 5,1996, (LCV-0603-I), and May 6, !
1996, (LCV-0603-P), GPC revised our May 1,1995, submittal in response to requests for additional information from the NRC staff as well as other issues that were identified subsequent to our May 1,1995, submittal. Enclosed are the proposed TS and Bases that reflect the above submittals.
The enclosed TS reflect four administrative changes. The first applies to specification 5.6.5,
" Core Operating Limits Report (COLR)" This specification contains an incorrect reference to WCAP-9220-P-A, Revision 1," Westinghouse ECCS Evaluation Model- 1981 Version,"
February 1982. The correct reference is WCAP-10266-P-A, Revision 2. "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code," March 1987. This is an administrative change because the use of WCAP-10266 was approved for VEGP by the NRC as part oflicense amendments 43 and 44 for Unit 1, and 23 and 24 for Unit 2 that provided for the use of VANTAGE-5 fuel and increased operational flexibility. See NRC letter dated September 19,1991, D. S. Ilood, NRC, to W. G. Hairston. III, GPC.
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U. S. Nuclear Regulatory Commission l
LCV-0603-L Page 2 Second, specification 5.5.! 3 should include the following statement:
"The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program surveillance frequencies."
This is current licensing basis. These provisions are applicable to the corresponding requirements in the current TS.
Third, specification 4.2.1 needs to be revised to reflect the correct spelling of the word "zircaloy" and to reflect that ZlRLO* is a registered trademark. Furthermore, specification 4.2.1 of the enclosed TS reflects a change from current licensing basis in that fuel assemblies using ZIRLO* cladding are no longer restricted to the lead test assemblies. The following discussion is provided to supplement the basis for this change. The use of this cladding has previously been reviewcd and accepted by the NRC on a generic basis through the review and approval of WCAP 12610-P-A and the appropriate revisions to 10 CFR 50.46 and 50.44, which was the basis of the NRC stafrs previous approval for the use of 7lRLO* clad fuel rods at other nuclear plants. This WCAP serves as a reference core design report for a fuel assembly design using ZlRLO* clad fuel rods. It presents the information necessary to support the licensing basis fbr the use of fuel assemblies containing ZIRLO* clad fuel rods for fuel reload regions. It includes mechanical, nuclear, thermal-hydraulic, accident and radiological evaluations. It also includes appendices to document ZIRLO* material properties, support fuel rod performance, and provide LOCA models and evaluations.
WCAP-12610-P-A was approved in NRC Safety Evaluations issued on July 1,1991 and October 9,1991. These Safety Evaluations approved the use of VANTAGE + fuel design, i.e.,7.lRLO" clad fuel and found it acceptable for up to a rod-average burnup level of 60,000 MWD /MTU. Therefore, the proposed change to the VEGP Technical Specifications is an administrative change indicating the expected use of fuel cladding at VEGP which has already been generically accepted by the NRC.
The fourth administrative change involves the frequency for SR 3.3.1.14. This SR requires that a trip actuating device operational test (TADOT) be performed on the turbine stop valve closure channels. Turbine stop valve closure and/or low fluid oil pressure indicates a turbine trip, and this in turn will initiate a reactor trip above the P-9 interlock. The present frequency for SR 3.3.1.14 is prior to reactor startup, but the function is not required to be operable until reactor power is above the P-9 interlock. The low fluid oil pressure channels are subject to a channel operational test (COT)(SR 3.3.1.16) at a frequency of after each Mode 3 entry for unit shutdown and prior to exceeding the P-9 interlock trip setpoint. This frequency is consistent with the applicability requirements for the reactor trip on turbine trip function (above the P-9 interlock trip setpoint). GPC overlooked the need to make the frequency of SR 3.3.1.14 consistent with SR 3.3.1.16. Since the NRC has found the frequency of SR 3.3.1.16 to be acceptable, GPC proposes to make the frequency of SR 3.3.1.14 identical to that of SR 3.3.1.16. !
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. I U. S. Nuclear Regulatory Commission :
LCV-0603-L Page 3 The last change to the TS since our last submittal involves the lube oil inventory for the emergency diesel generators (DGs)(LCO 3.8.3). It was necessary to revise the required lube oil volumes specified in LCO 3.8.3 due to revised information from the DG vendor.
Our December 21,1995, submittal shows that Note
- to SR 4.5.3.2 (precedural detail for using a safety injection (SI) pump to fill the accumulators) of the existing TS would be moved to the Bases for LCO 3.4.12. The Bases for LCO 3.4.12 do not discuss actual use of an SI pump to fill the accumulators, but the requirement in the Bases that the SI pump be rendered incapable ofinjecting into the RCS by at least two independent means provides fbr use of an Si pump for filling accumulators. Therefore Note
- to existing SR 4.5.3.2 was not incorporated verbatim into the improved TS Bases, but rather the intent was incorporated.
Please note that our December 21,1995, submittal revision included pages for Enclosures 2, 3, and 5 to Chapter 3.9 that were not current with respect to our September 22,1995, submittal. The current pages for Enclosures 2,3, and 5 for Chapter 3.9, as it relates to the unborated water source isolation valves, are those that were provided with our September 22, 1995 submittal.
In response to our May 6,1996, submittal regarding the proposed extended diesel generator allowed outage time (AOT), the NRC staff has identified two issues. The first issue concerns the lack of reliability data for the Plant Wilson combustion turbines (cts), and the second involves demonstrating the operability of tha Wilson line via testing. With respect to the first issue, the NRC staff has stated that an acceptable alternative would be to start and run a CT while a DG is inoperable during an extended AOT.
In response to the first issue, GPC offers the fbilowing. GPC will demonstrate and maintain the " Plant Wilson enhanced black-start generation reliability" at 2 95%. Plant Wilson has 6 cts, any one of which can support the full capacity of the SAT. Two of the cts (CT A and CT B) have enhanced black-start capability. (Under controlled conditions, GPC has demonstrated that Plant Wilson enhanced black-start generation can be started within one hour.) The " Plant Wilson enhanced black-start generation reliability"is defined as the capability of either, or both, CT A or CT B to successfully supply generation for possible alignment to VEGP. The enhanced black-start generation reliability will initially be demonstrated by requiring, either cumulatively or individually,20 consecutive tests of either CT A or CT B with no more than I failure out of the 20 tests. Successful tests will be defined via our procedures based on the overall criteria of having a CT available to supply power. Therefore, the enhanced black-start generation reliability will be demonstrated and maintained at 2 95%.
Separate from the 20 consecutive tests of the enhanced black-start generation reliability, the black-start diesel will be required to successfully start (and load) with no more than 1 failure out of a total of 20 consecutive tests. This will demonstrate the reliability of the black-start
U. S. Nuclear Regulatory Commission LCV-0603-L Page 4 diesel generator. Detailed computer models have been used to simulate the black-start l system design, and these models were validated with field tert results. Therefore, there is no need to perform 20 consecutive black-start demonstrations. The generation capability of the enhanced black-start cts is not materially affected by the source of motive power for the !
staning motors. Once the diesel is started, all that is necessary to start the CT is manipulation of the necessary disconnect switches and breakers. In addition,in accordance with Plant Wilson procedures, performing 20 black-starts would involve disconnecting Plant Wilson l from the grid (thereby deenergizing the standby auxiliary transformer (SAT) and removing a l preferred offsite source from service) 20 times. GPC considers this to be an unnecessary i reduction in the number of offsite power sources available to VEGP and would reduce VEGP's loss of offsite power recovery options. GPC will maintain our commitment to demonstrate the complete enhanced black-start generation capability at least once per 18 months.
l Once a reliability of 2 95% has been demonstrated, that reliability will be maintained by l ensuring that an enhanced black-start CT and the black-start diesel are started at least once per quarter. Ilowever, performing a series of 20 consecutive tests requires time. In the interim GPC will commit to running a CT during an extended DG AOT until the necessary enhanced black-start generation reliability can be demonstrated. (An extended DG AOT begins at 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> but must not exceed 14 days from initial failure to meet the LCO.) During this interim period, while in an extended DG AOT, a CT will be able to power the safety loads within one hour, and if this CT fails during an extended AOT, GPC will start another CT within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. In addition, if during this period GPC chooses to remove a DG from service for preventive maintenance that will involve an extended AOT, GPC will start a CT prior to removing the DG from service. The commitment to run a CT would also apply in the event that enhanced black-start generation reliability were to decrease below 95% after the i
initial demonstration.
l l The second issue, operability of the Wilson line, will be addressed by, at least once per 18 months, demonstrating that power can be made available to a safety bus via the underground I line within one hour. GPC means this requirement to encompass the electrical alignment necessary to provide power to the safety buses, and does not consist of a requirement to black-start a CT within one hour, in addition, GPC means that this testing can be performed in one test or in a series of sequential tests provided that the entire alignment is tested.
Finally, the enclosed Bases reflect certain minor revisions that were identified as a result of our review of the draft Safety Evaluation Report or as part of our implementation effort.
These Bases changes were incorporated to correct errors or to make the Bases consistent with our submittals and the enclosed TS.
r I
U, S. Nuclear Regulatory Commission '
LCV-0603-L i Page 5 i
i The changes to the TS proposed herein do not alter the conclusions of the evaluations !
performed pursuant to 10 CFR 50.92 that were provided with the above referenced l' submittals.
i The conversion involves relocating certain requirements and details to licensee controlled documents as reflected in the submittals referenced above. GPC will ensure that these I requirements and details are appropriately reflected in these documents or that they will be j included in the next required update of these documents. In some cases, information is being l moved from the TS to plant procedures, and this information is not reflected in the FSAR, the -
procedures are not described in the FSAR, and no other regulatory requirement applies (i. e.,
10 CFR 50.55(a),50.54(a), etc.). In these cases GPC will control future changes to this information via 10 CFR 50.59.- That is to say, changes to this information will only be made without prior Commission approval provided those changes do not involve a change to the TS or an unreviewed safety question.
In addition, GPC will maintain an auditable record of, and an implementation schedule for, the procedure changes associated with the conversion to the ITS. Furthermore, GPC will maintain the documentation of these changes in accordance with the record retention requirements in the Quality Assurance plan.
Finally, GPC requests that the license amendment be issued by July 7,1996, with implementation within 150 days ofissuance.
Mr. J. D. Woodard states that he is a senior vice president of Georgia Power Company and is !
authorized to execute this oath on behalf of Georgia Power Company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
GEORGIA POWER COMPANY IlY: k MA 6 Woodard Sworn to and subscribed before this /7Mday of June _,1996.
My commission expires: f-/9-P)
Notary Publ' -
J (pfd JDW/NJS
i l l ... l
, U. S. Nuclear Regulatory Commission l LCV-0603-L I Page 6 1
1 Enclosures xc: Georgia Power Comnany l Mr. C. K. McCoy Mr. J. B. Beasley, Jr.
Mr. M. Sheibani NORMS ;
U. S. Nuclear Regulatory Commission Mr. S. D. Ebneter, Regiona.' Administrator Mr. L. L. Wheeler, Licensing Project Manager, NRR Mr. C. R. Ogle, Senior Resident Inspector, Vogtle l
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