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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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s- Georgis Power Comeaay ;
Post Office Box 883 . q Waynesboro Geor&a 30830 '
- "' l0 E d ATTACHMENT.8 Soutnern Company Services. Inc.
4 Post Ottice Box 2625 1 Birmingham. Alabama 35202 wooeone 2:s m.On .Vogtle Project -
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- November 23. 1988 ,1
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i' U.S. Nuclear Regulatory Commission File:- 'X7N00.0-39 Log:- GM-1502 Attn.: Docutent Control Desk -1 Washington, D.C. 20555.
NRC DOCKET NUMBERS 50-424 AND 50-425 OPERATING LICENSE NPF-68 '
CONSTRUCTION PERMIT NUMBER CPPR-109 V0GTLE ELECTRIC GENERATING PLANT -UNITS l'AND 2 FSAR AMENDMENT NUMBER 39 l Gentlemen: ;
Georgia Power Company, acting on its own behalf and as agent- for'0g'lethorpe Power Corporation, Municipal Electric Authority'of Georgia,Eand the City of Dalton, Georgia, hereby submits Amendment-39 to the Vogtle Electric Generating' l Plant (VEGP) Final Safety-Analysis Report (FSAR).
3 The changes resulting from this amendment are identified in.the ' Attachment.
These changes are applicable >to both Units l'and 2.- All substantive changen,
~e for Unit 1, were evaluated as required by Title 10 CFR 50.59. This amendment i l contains all the known processed changes for Unit 2 as of.0ctober 31, 1983.-
( Due to the time lag associated with the as-built: notification process, not all ,
of the FSAR figures have been updated in this amendment. '.Our submittals to !
the stati, as noted in the Attachment, do contain the information on drawing .
modification sheets and provide the appropriate cross references to the; affected FSAR figures. Your staff 'till be notified should the final drawings .;
materially differ from what was previously provided. 3 l
In accordance with the requirements of Title 10 CFR 50.30(f) and .
Title 10 CFR 50.4(b), one (1) signed original and thirty-seven (37)' copies of Amendment 39 are submitted for your use. Also in accordance with the- ;
requirements of Title 10 CFR 50.4(b), copies of Amendment 39 are being sent to j the NRC Regional Office and the NRC Resident Inspector. ;
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9010170122 900928 PDR ADOCK 05000424 ,
P PDC ]
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E Files::X7N00.0-39 I U.S. Nuclear Regulatory Commission-November 23,-1988 Log: GN-1502 ,
Page 2 Should you have any questions on the enclosed. submittal,Ldo not hesitate to-contact me. .
Yours truly,. .
f, h. Y--1 ;
I P. D. Rice November , - 19 8 8 . ---
SWORN AND SUBSCRIBED-BEFORE ME, THIS M DAY 0Fl l
Aw
'Noga(/Public Alabama State at Large My commission expires %CommissientrairesNovember24.1991 PDR/sm j ' Attachment xc: NRC Regional Administrator-NRC Resident Inspector FSAR Distribution List l
1548V
. ~ - - -- . _ . . _.._._ . . _ .
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VEGP-FSAR-13 t
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13.1.1.2.2 Nuclear Operations Organization ;
The nuclear operations organization,.under the supervision of the executive vice president-nuclear. operations, has direct j responsibility for the operation and maintenanceLof:GPC's nuclear plants. .The n'ac. ear operations : organization consists 1of the
l plant operatin; staffs, the. safety. audit and engineering-reviewL organization, tnd the nuclear support (Vogtle) organization which? ,
provides support in the areas of. engineering, licensing, '!
i maintenance, and administration.
Engineering support during plant operation'will-be provided '!
primarily by the SCS Nuclear Plant Support, Department. ThetSCS [
Technical Services-Nuclear Department will provide-nuclear 3 fuel' contract administrative services, reload licensing,,and operating ,
licensing support. The structure of the General Office- 1' organization is shown in figures 113.1.1-2 and 13.1'l-3 and is I
described in the following paragraphs. .
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13.1.1.2.2.1 Executive-Vice President-Nuclear Operations. The executive vice president-nuclear operations, an officer: of both; i Georgia Power Company 1(GPC) and Alabama' Power-Company (APC),.is . .;
responsible to the chairman and-CEOs of each company for all l
aspects of operation of the nuclear genezeting plants in the~GPC and APC systems, as well as technical and . adnd nistrative - support ~
activities provided by SCS. The executive vice president-nuclear operations directs the senior vice .
president-nuclear operations in. fulfillment of his responsibility.
Amend. 16 4/85 Amend. 24 6/86
' Amend. 25 9/86 Amend. 26 10/86 Amend. 29 11/86 Amend. 35: 3/88 13.1.1-7 Amend. 39 11/88; .l
. N VEGP-FSAR-13 ;
13.1.1.2.2.2 Senior Vice President-Nuclear Operations. The.
senior vice president-nuclear operations, an officer of both Georgia Power Company (GPC) and Alabama Power, Company (APC),
reports to the executive vice president-nuclear. operations. This -
individual is responsible for the safe, reli~able, and efficient- ,
operation of Plants Vogtle, Hatch, and Farley. The-senior vice i president-nuclear operations directs the' efforts of the-vice president-nuclear (Vogtle), the vice president-nuclear-(Hatch), .
and the vice president-nuclear-(Farley). !
13.1.1.2.2.3 Vice President-Nucl' ear-(Vogtle). The vice ,
president-nuclear (Vogtle) reports to the senior vice '
president-nuclear operations and is responsible for operation.and }'
maintenance of Plant Vogtle as well as licensing,-engineering,-
maintenance, and administrative support activities. The vice ,
president-nuclear (Vogtle) directs the general manager-nuclear plant (Vogtle), the general manager-nuclear support (Vogtle), and the manager-safety audit-and engineering-review-(Vogtle).
q 13.1.1.2.2.4 General Manager - Nuclear Support-(Vogtle). The general manager-nuclear support (Vogtle) reports to the vice; j president-nuclear (Vogtle) and11s responsible for corporate ~ l support in the areas of engineering,. licensing, maintenance,=and administration. The general manager-nuclear support (Vogtle)E ;
directs the manager-nuclear engineering and-licensing-(Vogtle), '
the manager-nuclear maintenance and' support (Vogtle), and the manager-nuclear administration (Vogtle).
13.1.1.2.2.5 Manager-Safety Audit and Engineering Review (Vogtle). The responsibilities of the manager-safety audit and engineering review (Vogtle) are described'in.section 17.2.
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Amend. 16 4/85. .
Amend. 24 6/86 Amend. 25 9/86 4 Amend. 26 10/86 Amend. 29 11/86-i Amend. 35 3/88' l 13.1.1-8 Amend. 39 11/88 ;
ATTACHMENT 9 Interoffice Correspondence GeogiaPowerk DATE: August 21, 1990; * .;
RE: Operational, Assessment Inspection FROM: G. Bockhold Jr. 1 T0: Plant Employees :
As many' of you know. the. NRC recently concluded -an Operatienal '
Assessment Inspection. The inspection. among .other things, includedi investigation of a number of allegations - of -"wron doing " such as-intentional -violations of NRC requirements. . Somes VE P employees were interviewed femally in "on the recotti" interviews.
The NRC appropriately : investigates allegations: of wrongdoing which 'l bear on matters of safety or public health in a thorough and deliberate.
manner. While a fomal interview. may be disconcerting :or stressful, these reviews are sometimes necessary. Georgia! -Power. encourages couperation in these investigations .and . views it as essential that the -
NRC obtain the relevant and material' facts. :
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We have been inforined that all allegations of wrongdoing by -VESP l
employees were found to be unsubstantiated. At the same time. .the-Operational' Assessment team identified several technical: items where potential violations of NRC requirements may have occurred. For example. i the NRC observed at least one instance in. Which a : Deficiency Card -was not issued for equipment mpair, contrary' to .our practices. We must remember to use our Deficiency Card systemi only by identifying potential-deficiencies can we achieve our high standards of . excellence inca 11 of the areas which support this plant. All of us need; to be reminded to pay strict attention to detail -- to dot all the 1's;and cross all the t s -- in each of our daily tasks.
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I want - to thenk all of you who- worked diligently to support the Operational Assessment team. Your cooperation during,this , difficult, time is greatly appreciated. I. personally, am very proud of the.
professionalism shown by each of you and. encourage you to maintain those high standards as we move forward to fulfill our goal of efficient and, foremost, safe operation of the Vogtle Electric Generating Plant.
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L . ATTACHMENT 10 D!tstL STARTE AND FA!WRt REPORTING: 8/12/90
. Time: 13:00~ # .
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MRC_ Concern
- 1. The NeC is concerned about the incorrect number._ of diesel- starts reported in LER 1-90-06 and the number of starts: presented to: the NRC.on April 9,.
1990 and in the confirmation response letter' of April 9,1990. The. major- 'l issue remaining is to try and determine ~ through personal interviews, how- '
the number of 19 for diesel 18 was arrived at in the April 9 letter to the l
- NRC. The NRC believes the intent of- the April 9 letter .and the- '
presentation discussed- consecutive . successful starts.. The: revised-response to LER 90-06 did not clarify the number of starts reported J.
NRC April 9, and did not clarify that the Ig starts were not consecutive. ,
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- 2. The inspector noted that documentation provided by Operations to support.
diesel trending -(14940-C and 13145-C data; sheets)- does not contain- an adequate description of what happens during the start attemptc The plant ,
is not interpreting Reg Guide.1.108. properly with regard to ' reporting '
valid and non-valid failures. There may be valid and non-valid failures that were not reported. The NRC does not consider the current ~ status of:
reporting diesel failures.to be in compliance with cosaiteents made to the NRC in V olation 50-424/87-57. ,
l NRC_Doegmentation The NRC has reviewed the' diesel start log and supporting documentation (149eo-C and 13145-C data sheets). The NRC currently believes some probless-i identified on 14980's and 13145's should be classified as non-valid fattures '
and reported to the NRC. The NRC has requested' and received written analysis to explain the disposition of the following -Il_ diesel' starts: O s ' 123, 124, ,
132. 133, 134, 136. 160, 161, 161, .164, - 168, . and 190. LER 1-90-06, reviston 1; QA Audit Report opt 6-90/33; QA Audit Report OP09-90/311 and Special Report-1-90-05, dated August 7,1990; GPC confirmatory action letter dated April 9, >
1990.
VMP Petitlen
- 1. The error made in the number of diesel starts reported to the NRC on April-9,1990, and in LER 190-06 is attributed to two factors:-
- a. The testing as described in LER 90-06, revision: 0, . was- in the- '
" context of' and "in reference to" the- diese)- eentral evetene. The first-two sentences of the 5th paragraph' explain actions taken with regard to sensor calibrations and control system. testing. In this.
context, the test arenra'a correlates to testin9 discussed with the NRC on April 9,1990, and reported in the April 9,1990, confirm l 1etter. The LER 90-06 comment of " subsequent to the test program was not intended to exclude successful diesel starts before declaring the diesel :,perable. As a.nsult, diesel starts after testing of the contro) systems, but before a declaration of operability were !
counte(. The transmittal letter for LER 90-06, revision 1, describes .
the confusion and attempts to. clarify the concern by redefining the types af starts and the point of counting. ,
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O!ESELSTARTSANDFAILUREREPORTINGL L ,
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i .b. LER 90-06, revision 1 was ' intended to clarify any inadvertent-l
! *sisleadint" of the NRC,on successful operation of the diesel control- '
L systems. een Vo9tle Management- was : aware of the probles in ;Ltt ;
l 96-06, revision 0. management notified the NRC Residents. - Also at i
the corporate office on 6/11/90, .4.s Shipman contacted Ken Brockman
- l. and on about 8/11/90. H. G. Wairston !!! contacted Mr. 5. Ibneter ' 1
- of NRC Region !!. The revised LER was submitted on 4/19/90. i The 19 starts discussed on April 9 were based on operator assessments.
of the starts as- successful using VEGP edures. - Additional review of these starts by both the NRC and Vo tio personnel indicates start. ,
L #134. performed on March 23. 1990, cou d be counted: ss unnueceanful.
If 'startc #134 isc not counted. .on1 14. successful- starts occurred before April 9.1990. This start 11? be reviewed in- detail- and an appropriate report to clarify ,the: number of starts reported Apri1 ~ 9.
-1990 will be made. ;
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- 2. After a thorou9h review of Reg ' Guide 1.108. Engineering- Support (Mike Horton) agreed that all distel start erehtaan have not been reported as failures. GpC's response to .NRC Violation 424/87-57 committed. to report such equ ent problems as failures;: ;however, due to internal administre ve problems, the commitment was not implemented. Engineering ,
Support intends to review diesel start records for any unreported failures. '
l-VEP Documentation l o LER 1-90-06, revision 1; QA Audit Report opt 6-90/33; LQA Audit- Report l
OP09-90/31; and Special Report 1-90-05, dated -August 7. 1990; GpC :
confirmatory action letter dated. April 9.;1990.
j o 13 diesel start analysis available 8/15/90 'and' Re9 Guide .1.108. position l
from Engineering Support.
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1/W90 Response to RC Question Concerningc Time: 11:00 >
Dittel $t&Ptl Reported 6R April 9 1990-
&nd in LER 90 06, Revisions 0 and 1 L ouantian at 1 Who pre Answer: pared the slide for the ~4/9/90 presentation?
G. Bockhold. Jr., J. P. Cash, and K.- Burr working as a group..
- 2. Who approved use of the slidet Answer: G. 80ckhold, Jr.
Quantien at
- 1. Who prepared the confirmatory letter of April 9,:19901 Answer: C. K. McCoy, J. A. Bailey,-W. G. Nairston. !!!'as a group.
- 2. Who approved the letter?
Answer: W. G. Hairston. III ouantien as (with rosard to LER 90 06, revision 0,' dated 4/19/90)-
- 1. Who prepared the LER? _
Answer: Several draft revisions of the LER were prepared by Tom Webb and others of the NSAC group of the Vogtle Site Technical: Support.
These drafts were reviewed and commented on by the Plant Review Board. . The final < revision of LER 90-04. revision 0 was prepared by a phonacon between site management and corporate mana Those participating are believed to be G. Bockhold, Jr.,gement. A. L.
Mosbaugh, J. G. Aufdenkampe, W. Shipman.
- 2. Who reviewed the LERt Answer: All revisions of the LER Were reviewed by the PRB and the General Manager-Plant Vogtle.
- 3. Who approved the LER?
Answer: The LER was approved by W. G. _Hairston.. !!!
Quantien se
. 1. Who prepared the cover letter for LER 90-06, revision 17 Answer: The cover-letter was prepared by H. W. Majors of the corporate staff. This letter was prepared > under the guidance of W. G.
Hairston.
- 2. What was the purpose (intent) in the wording of- the cover 1stter with '
regard to the number of diesel starts?
Answer: The cover letter was intended to document discussions with NRC Region !! to clarify the ' starts documented in LER 90-06, revision 0. By picking- a well defined wint to specify
" subsequent to the test program" it was poss9ble to identify a substantial number of successful diesel starts. This was-intended to remove any additional ambiguity.
Quantion #5 *
- 1. Who in' corporate added the words " subsequent to the test program" in LER -
90-06, revision of Answer: Corporate Licensing personnel in conjunction with the phone conversation described above made editorial changes as directed. Those present durini.the on are thought to be W. Shipsan. G. lockhold, phone Jr. , A.conversatd L. Mosbaugh, J. G. Aufdenkampe, and J. Stringfellow.
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