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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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- c. n. ucc., Georgia Power N${$ ~~ wrwoennum Docket Nos. 50 424 ELV 02853 50 425 April 3, 1992 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555 V0GTLE ELECTRIC GENLRATING PLANI BIENNIAL REVILWS Of NUCLEAR PLANT PROCEDJ)RES Gentlemen:
Georgia Power Com)any hereby reque m a change to the Quality Assurance ProgramasdescriaedintheVopti: Electric Generating Plant Units 1 and 2 Final Safety Analysis Report (.iAR , sections 1.9.33, 13.5.1.1 and 17.2.1.3.3. Currently, the GAR requires that plant procedures be reviewed at least every 2 years. This procedure review process is controlled by internal plant procedures. The fSAR also currently references the conformance to Regulatory Guide 1.33, which endorses ANSI N18.7-1976. This ANSI standard requires the biennial review of plant procedures.
Based on the justifications in Attachment 1, Georgia Power Company proposes to change the FSAR to provide for biennial Quality Assurance audits of the plant procedural development and maintenance program utilizing a representative sampling process. This biennial audit would replace the current commitment of performing a biennial review of all procedures except the commitment to review the Emergency Plan Implementation Procedures on a biennial basis or commitments associated with the review of security procedures. Existing plant programs, independent of the biennial review program, provide for adequate ri: view and revision, if necessary, of plant procedures to ensure they remain technically correct and adequate. Also, Georgia Power Company proposes to include a statement in the fSAR for the Safety Audit and Engineering Review staff to perform a biennial quality assurance audit of the plant procedural development and maintenance programs utilizing a representative sampling process. Although this would be 2 new FSAR provision, Georgia Power Company already performs the scope of this audit as part of the current quality assurance program. Attachment 2 provides the proposed FSAR wording revisions.
Pursuant to the requirements of 10 CfR 50.54 (a), Georgia Power Company has concluded that there would be no significant reduction in commitments in the Quality Assurance Program as a result of this change. Ilowever, as 9204060339 920403 A PDR ADOCK 05000424 PDR god /
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. U.S. Nuclear Regulatory Commission Page 2 a conservative measure, Georgia Power Company is requesting NRC approval before implementing this change. Following NRC approval, Georgia Power Company will update its internal procedures and the FSAR and transmit those changes to the NRC on schedules consistent with the regulations.
The Plant Review 30ard has reviewed and recommended approval of this proposed change and the Safety Review Board will review this proposed change at a future meeting. Georgia Power Company requests that this ~
proposed change be approved by.the NRC by July 1992.
In accordance with 10 CFR 50.91, the designated state official will be sent a copy of this letter and all enclosures.
Respectfully submitted, GEORGIA '0WER COMPANY 0 . PM C. K. McCoy CKM/JMG AtAachments Sworn to and subscribed before me this I day of M o4 h , 1992.
kay'Pu i 7 My Commission Expires:
cc: Georaia Poxqr Company Mr. W. B. Shipman, General Manager - Plant Vogtle NORMS U. S. Nuclear Peaulatory Commission. Washinatori. DC Mr. D. S. Hood, t.icensing Project Manager Vogtle U. S. Nuclear Reaulatory Commission. Reaion 11 Mr. S. D. Ebneter, Regional Administrator Mr. B. R. Bonser Senior Resident Inspector - Vogtle State of Georata Mr; J. D. Tanner, Commissioner, Department of Natural Resources
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. Attachment 1 Justification for Change to Biennial Audits of Procedures IDtroduction Currently, FSAR section 13.5.1.1 requires that plant procedures be reviewed at least every 2 years. These reviews were developed during plant licensing to address the procedure review philosophy of ANSI N18.7 1976 endorsed by Regulatory Guide 1.33.
Georgia Power Company has 4,200 proedures which fall under the 2 year review requirements. A cnnservative estimate for the biennial review time for these procedures is 20,000 manhours. Also, the documents supporting the review of each procedure are considered life of plant documents; therefore, more space must be allocated each year for storage.
By letter dated December 21, 1990, from Georgia Power Company to J. P. Stohr of the NRC, the commitment was made to provide for a biennial review of the Emergency Plan 2mplementation Procedures rather than an annual review. This commitment will remain. Commitments relative to security procedures also remain unchanged.
Discussion ANSI N18.7-1976 provides for a static biennial review process, but recognizes-that the procedure review process may change as a plant reaches operational maturity. _ Georgia Power Company believes that an ongoing dynamic process is inherently required in maintaining procedures in an ,
accurate and useful condition. This process requires that procedural controls be in place to provide for. procedure changes as the plant design, regulatory, or operational requirements change.
in addition, most of these procedures are used frequently by plant personnel. As plant personnel use these procedures, problems are identified and resolved through various internal programs, some of which are discussed below. Further, a significant portion of the emergency operating procedures are frequently used through various simulator training programs 4 Once identified, procedural issues are addressed in an expeditiotis manner.
Georgia Power Conpany continually evaluates its procedure maintenance +
processes and has effected controls to ensure that potential procedural impact is assessed and revisions are made based on input from a number of different programs. The following programs adequately provide input to procedure revisions _and changes:
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. Page 2 Attachment 1 (1) Plant Design Control Program lhe plant design control )rogram requires an interface review of all modifications by groups witch are potentially affected by the modification. This interface review requires that all procedures potentially affected by the modification be identified, and changet and revisions be ready to be implemented upon completion of the modification. All group managers must indicate that all revisions +.0 :
- elant procedures have been issued before the modification package crn se considered complete.
(2) Operating Experience Program The operatina experience program requires the review of HRC bulletins, nocices, and generic letters; Westinghouse Owner's Group information; INPO significant operating event reports (50ERs),
significant event reports (SERs), and operation and maintenance reminders (0MiRs); Nuclear Network operating plant experience reports; controlled vendor-technical information; unsolicited vendor technical information; and various internally generated reports such as the incident report. This review includes an evaluation of a)plicable procedures and the initiation of any required procedure c,1anges .
(3) Licensed Operator Requalification Program As potential deficiencies are identified in the energency operating procedures, formal processes are in place to identi?y and resolve them. This includes procedure revisions, if appropriate.
'(4) Deficiency Control Program The deficiency control program is in place so that any individual onsite who identifies a potential deficier.cy may report it directly to the Unit Shift Supervisor. As potential deficiencies are identified, formal processes are in place to resolve them. This includes procedure revisions, if appropriate.
(5) Technical Specifications and FSAR Revisions Revisions to Technical Specifications and the FSAR require evaluation ,
for impact on procedures and result in the initiation of procedure changes, if appropriate.
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'Page 3 Attachment 1 (6) Quality Assurance Program The Quality Assurance Program includes a review of procedures as part of the audit and surveillance process (which is based on a 2 year cycle). The Quality Assurance Program assigns the responsibility to the Safety Audit and Engineering Review (SAER) group to audit the entire procedural process on a periodic basis. The Plant Review Board (PRB) also performs overviews that include a review of many plant procedures. Input into the procedure revision process may be provided by either of these two avenues.
(7) Surveillance Test Program The surveillance test program provides direction to evaluate the need for a procedure change that is identified through the performance of a procedure. These changes may be required prior to continuation of the performance of the tests, or after completion of the tests, depending on the nature of the discrepancies.
(8) Vendor Documents Review Program The vendor documents review program requires the review of vendor manuals and revisions to vendor manuals. This review includes an evaluation of applicable procedures and the initiation of any required procedure changes.
(9) Plant Personnel feedback Plant personnel including operators are trained and directed by procedure to repo.t to management any procedural deficiencies or concerns which may prevent or impact their implementation, feedback into the procedure revision process may be initiated through such programs as the operating experience program.
(10) Simulator Training Program As potential deficiencies and enhancements are identified in the emergency operating procedures during simulator and classroom training, formal processes are in place to identify and resolve them.
This includes procedure revisions, if appropriate.
Conclusion As evidenced by the number of programmatic controls discussed above for procedure input and revision, Georgia Power Company considers the biennial
. 'Page 4 Attachment 1 1
review process to be an unnecessary regulatory requirement. The imptet on I plant resources for the biennial review process reduces the site !
personnel's ability to concentrate on issues of greater significance to '
plant safety. Therefore, Georgia Power Company proposes to change the FSAR to provide for biennial Quality Assurance audits of the plant procedural development and maintenance program utilizing a representative sampling process. This biennial audit would replace the current commitment of a biennial review of all plant procedures, except the commitment to review the Emergency Plan Implementation Procedures on a i biennial basis or commitments associated with the review of security procedures, and will provide verification that the existing plant programs
- and activities are effective in maintaining procedures current.
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- 3. Paragraph C.5 9 of Regulatory Guide 1.33 will be implemented with the addition of the modifier "normally" after each of.the verbs (should) which the Regulatory Guide converts to "shall." It is GPC intent h to fully comply with the requirements of this F paragraph, and any conditions which do not fully comply
- will be documented and approved by management personnel. In these cases, the reason for the exception shsil be retained for the same period of time as the,3ffected preoperational tests.
1.9.34 9- REGULATORY
@ ct C GUIDE 1.34, DECEMBER 1972, CONTROL OF ELECTROSLAG WELD PROPERTIES 1.9.34.1 Regulatory Guide 1. 34 Post *. ion This guide describes an acceptable method of implementing requirements with regard to the control of weld properties when fabricating electroslag welds for nuclear components made of ferritic or austenitic materials.
1.9.34.2 VEGP Position Conform. Refer to paragraph 5.2.3.4.6.
1.9.35 REGULATORY GUIDE 1.35, REVISION 2, JANUARY 1976, INSERVICE INSPECTION OF UNGROUTED TENDONS IN PRESTRESSED CONCRETE CONTAINMENT STRUCTURES 1.9.35.1 Regulatory Guide 1.35 Position This guide describes an acceptable basis for developing an appropriate incervice inspection and surveillance program for ungrouted tendons in prestressed concrete containment structures.
1.9.35.2 VEGP Position Conform as discussed in subsection 3.8.1.
h 1.9-32
'lNSERT 1 During original plant licensing, a 2 year review process for plant procedures was developed to meet the requirement of Regulatory Guide 1.33 and ANSI 18.7-1976. Since the procedural process has now matured and adequate programs to assure procedural revisions consistent with plant design, operational, ;
and regulatory requirements are in place, this original commitment has been modified to require biennial Quality Assurance audits of the procedural development and maintenance program utilizing a representative sampling process. Therefore. .
the 2 year review process is no longer required. r
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VEGP-TSAR-13 Operations department heads shall further ensure that procedures described in subsection 13.4.1 are forwarded to the Plant Review Board (PRB) for additional review.
For procedures not forwarded to the PRB, reviewers will meet requirements of section 4.4 of ANSI N18.1-1971 for applicable disciplines. For those disciplines not described in Jection 4.4 of ANSI 18.1-1971, the reviewer will have a minimum of ; years experience. A maximum of 4 years of this 5 yea.. may be fulfilled by related technical or academic training. Reviewets of quality control inspection procedures shall meet the requirements of Regulatory Guide 1.58. Also, those procedures not forwarded to the pRB and impacting another department's area of responsibility, shall be forwarded to the impacted departments for their review.
The general manager-nuclear plant (Vogtle) (GMNP) has ultimate responsibility for all plant procedures.
Provisions of these procedures establish the GMNP as the approving authority for procedures wnicn estaclish plant-wide administrative controls (which implement the quality assurance program and the Technical Specifications surveillance progra.../; unit operating procedures (UOps); emergency operating procedures (EOPs); abnormal operating procedures (AOPs);
procedures for implementing the security plan, the emergency plan, and the f t re protection progtm; and fuel handling procedures. Nuclear Operations department heads are established as the approving authority for other procedures covering activities within their area of responsibility.
i Additional provisions of these procedures exist to ensure that changes or revisions to procedures are reviewed and approved in accordance with the same administrative controls used for review and approval of l
l new p r oc edu r es . *,N-in+v 're4 cn i c ade to ensure that
! --p4+nt p r oeedwes- exoept--444ef49M-i+9-p+ep44n -e l l revicued Ot 1000t c>,w y 2 y e a r ; by a-kw+w4edw.h
-tedi-vtdue4 to detu mine-whether chen9c c : e a c c c u a++P 0: d c c i r+ble, Also, provisions exist to ensure that g procedures, or.ce approveo, are distributed appropriately so that only the most current procedures are used ty plant personnel.
~ As pet .J Se wall saalib awrana peyn . the SAER yup performs varwus salits (described in 112 ) 1e essure &t l OL prottdurel prMLSS 95 WorU9 & h[procedJrts b rt. beiny ytope.rh nainta\ned. 13.5.le2 REV 1 3/91 ,
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E. To assure Wi wiro/s .ve a p/hte to dfec/hely m.% fain
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pbat protebres, fAe .WR Jiaff vill perform a biennu/
<1alif of 4Ae protedaral <Aa/epment ad nain/tn.snee prytant hlllilij A. fiftYMn d.tllVd. bm VEGP-FSAR-17,0lin) {ft)le$$.
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17.2.1.3.3 SNC Safety Audit and Engineering Review (Onsite) l The SNC SAER staff will selectively audit those quality-related l
[ activities that are within the scope of the OQAP, as described )
in subsect'on 17.2.2, to verify compliance with the requirements of the OQAP. These consist of activities performed onsite and i those performed offsite in support of VEGP when directed. The i results of all such audits will be reported to the organization audited and the vice president-nuclear (Vogtle). !
I SAER personnel have written authority to stop work on a system, ;
structure, or component that affects nuclear safety if the work :
is not in accordance with provisions of the OQAP. Disputes arising from differences of opinion between SAER personnel and ,
other department personnel will be resolved by the lowest level of management possible. If necessary, the vice president-nuclear (Vogtle) will maxe the final disposition. The MSAER shall regularly assess the SAER workload to ensure a sufficient number of personnel are available for complete and efficient implementation of their quality assurance responsibilities.
Specific duties and responsibilities of the SAER onsite group (headed by the supervisor-safety audit and engineering review) are as follows:
A. Prepares annual schedule and performs planned audits of organizations and activities (GPC and contracto).
B. Provides the MSAER with information on site activities on a routine basis.
C. Maintains open-items list of SAER onsite group audit results; follows up until resolved and closed out.
D. SAER participates in the development process for plant procedures by evaluating procedure adequacy and-implementation in the SAER audit program and through its non-voting membership in the Plant Review Board.
SAER personnel have access to meetings where quality matters are discussed. The MSAER shall designate the types of meetings his staff or representative (s) from his staff will routine,1y attend, including day-to-day work planning meetings and staff meetings.
17.2.1.4 Engineering The SNC Nuclear Support (Vogtle) has overall responsibility for l assuring the availability of and providing or securing adegaste engineering and technical support for the VEGP. The SNC manager- l
(. nuclear engineering and licensing (Vogtle) serves as the 17.2.1-7 REV 1 3/91
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