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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20217G1071999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Vogtle & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Plans to Conduct Core Insps at Facility Over Next Six Months ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20217B0141999-10-0101 October 1999 Forwards Insp Repts 50-424/99-06 & 50-425/99-06 on 990725- 0904 at Vogtle Units 1 & 2 Reactor Facilities.Determined That One Violation Occurred & Being Treated as non-cited Violation ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210V0881999-08-16016 August 1999 Forwards Insp Repts 50-424/99-05 & 50-425/99-05 on 990620- 0724.No Violations Noted.Vogtle Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices ML20210Q4611999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 for Vogtle.Requests Info Re Individuals Who Will Take Exam. Sample Registration Ltr Encl ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210N1191999-08-0202 August 1999 Discusses 990727 Telcon Between Rs Baldwin & R Brown Re Administration of Licensing Exam at Facility During Wk of 991213 ML20210G3351999-07-27027 July 1999 Forwards Second Request for Addl Info Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20210E0121999-07-23023 July 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20210D9341999-07-22022 July 1999 Discusses Closure of TACs MA0581 & MA0582,response to Requests for Info in GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20210E0431999-07-15015 July 1999 Forwards Insp Repts 50-424/99-04 & 50-425/99-04 on 990502- 0619.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196H8081999-06-28028 June 1999 Discusses 990528 Meeting Re Results of Periodic PPR for Period of Feb 1997 to Jan 1999.List of Attendees Encl ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage ML20207E7421999-06-0303 June 1999 Refers to from NRC Which Issued Personnel Assignment Ltr to Inform of Lm Padovan Assignment as Project Manager for Farley Npp.Reissues Ltr with Effective Date Corrected to 990525 ML20207F6201999-06-0202 June 1999 Sixth Partial Response to FOIA Request for Documents.Records in App J Encl & Will Be Available in Pdr.App K Records Withheld in Part (Ref FOIA Exemptions 7) & App L Records Completely Withheld (Ref FOIA Exemption 7) ML20207D9861999-05-28028 May 1999 Informs That,Effective 990325,LM Padovan Was Assigned as Project Manager for Plant,Units 1 & 2 ML20207D2701999-05-19019 May 1999 Forwards Insp Repts 50-424/99-03 & 50-425/99-03 on 990321- 0501.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206M5141999-05-11011 May 1999 Informs That NRC Ofc of Nuclear Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Rl Emch Section Chief for Vogtle. Reorganization Chart Encl ML20206U4061999-05-11011 May 1999 Confirms Telcon with J Bailey Re Mgt Meeting Scheduled for 990528 to Discuss Results of Periodic Plant Performance Review for Plan Nuclear Facility Fo Period of Feb 1997 - Jan 1999 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20206A6371999-04-21021 April 1999 Forwards SE Authorizing Licensee Re Rev 9 to First 10-yr ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205Q3351999-04-15015 April 1999 Forwards Insp Repts 50-424/99-02 & 50-425/99-02 on 990214-0320.Three Violations Identified & Being Treated as Non-Cited Violations ML20205T2351999-04-0909 April 1999 Informs That on 990317,B Brown & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Date Scheduled for Wk of 991213 for Approx 10 Candidates ML20205K7501999-04-0505 April 1999 Informs That Effective 990329,NRC Project Mgt Responsibility for Plant Has Been Transferred from Dh Jaffe to R Assa ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl 1999-09-20
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl ML20205H4051999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3891999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included ML20205A9441999-03-25025 March 1999 Forwards VEGP Unit 1 Cycle 9 Colr,Per TS 5.6.5.d ML20205H3811999-03-24024 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3621999-03-22022 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81, as Requested IAW 10CFR50.75(f)(1) ML20204G4361999-03-18018 March 1999 Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Vegp,Iaw Requirements of 10CFR50.54(w)(3) ML20204C0591999-03-17017 March 1999 Forwards Rev 0 to WCAP-15160, Evaluation of Pressurized Thermal Shock for Vegp,Unit 2 & Rev 0 to WCAP-15159, Analysis of Capsule X from Vegp,Unit 2 Reactor Vessel Radiation Surveillance Program ML20207K9551999-03-11011 March 1999 Forwards Response to Rai,Pertaining to Positive Alcohol Test of Licensed Operator.Encl Info Provided for NRC Use in Evaluation of Fitness for Duty Occurrence.Encl Withheld,Per 10CFR2.790(a)(6) ML20207L9721999-03-10010 March 1999 Forwards Rev 15 to EPIP 91104-C of Manual Set 6 of Vogtle Epips.Without Encl ML20207B0191999-02-25025 February 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 980701-1231,IAW 10CFR26.71(d) 05000424/LER-1998-009, Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 9812291999-01-27027 January 1999 Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 981229 ML20199F7701999-01-13013 January 1999 Submits Revised Response to RAI Re Licensee 980713 Proposed Amend to Ts,Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Protection Channels. Corrected Copy of Table,Encl ML20199F7981999-01-13013 January 1999 Forwards Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage. Change Bar in Margin of Affected Pages Denotes Changes to Rept ML20199G1381999-01-13013 January 1999 Forwards Copy of Permit Renewal Application Package for NPDES Permit Number GA0026786,per Section 3.2 of VP Environ Protection Plan 05000424/LER-1998-007, Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.731999-01-13013 January 1999 Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.73 ML20198F6131998-12-18018 December 1998 Forwards Revised Certification of Medical Exam Form for License SOP-21147.Licensee Being Treated for Hypertension. Util Requests That Individual License Be Amended to Reflect Change in Status ML20198L6631998-12-18018 December 1998 Forwards Amend 37 to Physical Security & Contingency Plan. Encl 1 Provides Description & Justification for Changes & Encl 2 Contains Actual Amend 37 Pages.Amend Withheld,Per 10CFR73.21 ML20198D9291998-12-16016 December 1998 Forwards Requested Info Re Request to Revise TSs Elimination of Periodic Pressure Sensor Response Time Tests & Elimination of Periodic Protection Channel Response Time Tests ML20198D9991998-12-16016 December 1998 Forwards Responses to 980916 RAI Re Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations ML20198D8171998-12-14014 December 1998 Forwards NRC Form 396 & Form 398 for Renewal of License OP-20993.Without Encls ML20206N3051998-12-0808 December 1998 Submits RAI Re Replacement of Nuclear Instrument Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys 1999-09-20
[Table view] Category:LEGAL/LAW FIRM TO NRC
MONTHYEARML20044A7461990-06-25025 June 1990 Forwards Endorsement 35 to Nelia Policy NF-302 & Endorsement 29 to Maelu Policy MF-129 ML20064B4911990-05-31031 May 1990 Forwards 900507 Court Order Instructing Parties to Provide Info to Wage & Hour Administrator Re M Hobby Claims Against Util Under ERA ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML20244D9001989-04-0606 April 1989 Forwards Endorsements 94 & 18 to Maelu Policies MF-78 & MF-129,respectively & Endorsements 112 & 24 to Nelia Policies NF-215 & NF-302,respectively ML20244D9131989-04-0505 April 1989 Forwards Endorsements 1 to Nelia Certificate N-117 & Maelu Certificate M-117 ML20247A3021989-03-21021 March 1989 Discusses 890302 Notice of Finding of No Significant Antitrust Changes Re OL for Unit.Oglethorpe Power Corp 890317 Comments Do Not Affect NRC Ability to Recommend & Commission Ability to Issue Full Power License on 890330 ML20247H3981989-03-21021 March 1989 Forwards 890228,0308 & 15 Ltrs on No Significant Change Finding Re Antitrust OL Review ML20245H7831989-02-28028 February 1989 Discusses Transaction Between Oglethorpe Power Corp & Seminole Power Cooperative,Per Antitrust Review.Antitrust Review Reflects Assertions That Are Factually Incorrect & Should Reflect Addl Facts Available ML20151Z5491988-08-23023 August 1988 Forwards Supplemental Reg Guide 9.3 Info in Response to Mathews to Wg Hairston ML20150E4781988-07-0505 July 1988 Forwards Endorsement 14 to Maelu Policy MF-129 & Endorsement 20 to Nelia Policy NF-302 ML20148H0821988-01-12012 January 1988 Forwards Endorsements 105 & 16 to Nelia Policies NF-215 & NF-302 & Endorsements 87 & 10 to Maelu Policies MF-78 & MF-129 ML20206R9481987-04-10010 April 1987 Forwards Endorsements 15 & 9 to Nelia Policy NF-302 & Maelu Policy MF-129,respectively ML20204F4841987-02-26026 February 1987 Forwards Endorsement 8 to Maelu Policy MF-129 & Endorsements 10,11,12,13 to Nelia Policy NF-302 ML20207T6041987-02-26026 February 1987 Forwards Dept of Labor 870218 Final Decision Dismissing Case 86-ERA-9 Re JW Durham Vs Util & Butler Svc Group,Per Cw Whitney Request.W/Certificate of Svc ML20210S5371987-02-0202 February 1987 Forwards Endorsement 1 to Nelia Policy N-111 & Maelu Policy M-111 ML20211J8201986-10-14014 October 1986 Forwards Endorsement 8 to Nelia Policy NF-302 ML20214Q1441986-09-18018 September 1986 Discusses ASLB 860827 Partial Initial Decision Re Several Contentions,Incuding Contention 10.1 Addressing dose-rate Effects & Applicant Submittal of Addl Info on Subj.Addl Info Should Not Change ASLB Conclusions.Svc List Encl ML20206S2701986-09-17017 September 1986 Notifies of Address Change Effective on 860927.Requests Address on Encl List of Dockets Be Changed ML20214L6021986-09-0505 September 1986 Forwards Kp Twine Supplemental Affidavit on Contention EP-5 Re Rev to Savannah River Plant Plan,Incorporating Info on Reception Ctrs.Inclusion of Reception Ctr Info in Emergency Plans Resolve ASLB Concern ML20212Q8141986-09-0303 September 1986 Forwards Applicant 860821 & 0902 Ltrs to NRC Re Board Notification 86-018,for Info.W/Svc List.Related Correspondence ML20212N0631986-08-26026 August 1986 Discusses Plant Conformance to NUREG-0654,App 3 Re Emergency Broadcast Sys,Per Board 860812 Order.Related Correspondence ML20212H4171986-08-11011 August 1986 Forwards 860430 Scheduling Svcs Agreement Between Georgia Power Co & Oglethorpe Power Corp.Partially Deleted Interconnection Agreement Between Alabama Electric Cooperative,Inc & Ogelthorpe Power Corp Also Encl ML20204K0691986-08-0404 August 1986 Informs That Listed Info on Burke County Reception Ctr Capacity Will Be Added to Emergency Plan,Per Board 860717 Memorandum & Order.Info Should Enable NRC & FEMA to Complete Verification of Plan.W/Svc List ML20202G1691986-07-10010 July 1986 Forwards Correspondence Re Application for 10CFR70 License for Possession & Storage of Unirradiated Reactor Fuel & Associated Snm.W/Svc List.Related Correspondence ML20206P7131986-06-30030 June 1986 Forwards Revised Pages to Offsite Plans Re Emergency Public Info Program for Transients (EP-2/EP-2 (H)),Per Board 860505 Memorandum & Order.W/Svc List.Related Correspondence ML20206J7821986-06-23023 June 1986 Forwards Updated Page Changes for Burke County & State of Ga Emergency Plans for Facility Plume Pathway Emergency Planning Zone.Encl Plan Changes Composite of Feb & Apr 1986 Changes.Svc List Encl.Related Correspondence ML20206D8211986-06-16016 June 1986 Responds to Re 860310 Motion for Summary Disposition of Contention EP-5.Applicants Did Not Address Savannah River Plant Plan Because Reception Ctrs Not Related to Issue Raised.Kp Twine Affidavit Encl.W/Svc List ML20206D7041986-06-16016 June 1986 Forwards Revised Burke County Plan Pages Re EP-4 & EP-1/EP-1(a)/EP-2(b).In Accordance w/860513 Ltr to Board, Revised Plan Pages Re EP-2/EP-2(h) on Public Info for Transients Will Be Provided on or Before 860701.W/svc List ML20209E7401986-06-12012 June 1986 Forwards Certified Declarations Page for Endorsements 1 Through 6 to Nelia Policy NF-302,dtd 860605 ML20155K0021986-05-20020 May 1986 Requests That Specific Revised Sections of Burke County Emergency Plan Which Accurately Identify Backup Means of Notification & Line of Succession of Emp Be Provided to NRC & FEMA by 860701.Svc List Encl ML20197G7181986-05-13013 May 1986 Discusses Steps Taken to Comply W/Aslb 860429 & 0505 Orders Re Offsite Emergency Planning.Changes Will Be Reflected in Full Plan Revs Scheduled for Fall 1986 ML20203D6621986-04-17017 April 1986 Informs of Review of Staff Response to Applicant Motion for Summary Disposition of Joint Intervenors Contention EP-2/EP-2(h) & Affidavit of Cl Stovall.State & Local Emergency Plans Will Be Revised.Related Correspondence ML20203A0071986-04-14014 April 1986 Forwards Proposed Findings of Fact & Conclusions of Law on Technical & Environ Contentions.Certificate of Svc & Svc List Encl ML20138C1491986-03-28028 March 1986 Forwards Revised Emergency Public Info/Education Matls for State of Ga Portion of Plume Exposure Pathway Emergency Planning Zone.Info Revised to Include Use of Fixed Sirens. Svc List Encl.Related Correspondence ML20137Z5791986-03-11011 March 1986 Requests That Gf Trowbridge Be Replaced as Addressee for NRC Correspondence in Accordance W/Listed Client Facility & Designated Addressee ML20203C2321986-03-0505 March 1986 Appeals Lack of Response to FOIA Request for Documents Re NRC Investigation Into Complaints of Register,L Price & JB Register Concerning Illegal & Improper Procedures & Practices at Facility ML20154B8611986-02-28028 February 1986 Forwards Draft Bechtel Rept, Groundwater Numerical Modeling, Dtd Feb 1986.Svc List Encl.Related Correspondence ML20154C4641986-02-27027 February 1986 Forwards Page 13 of Asco Catalog NP-1,omitted from Exhibit F to Applicants 860224 Testimony of Gt Baenteli,G Bockhold, Sj Cereghino,Wv Cesarski & Hj Quasny on Contention 10.5 Re Solenoid Valves.Related Correspondence ML20205J7171986-02-24024 February 1986 Forwards Applicant Testimony on Contentions 7 & 10.1 Re Groundwater,Per ASLB 860114 & 23 Scheduling Order & Suppl,Respectively.Testimony of Contention 10.5 Filed Under Separate Cover.W/Certificate of Svc.Related Correspondence ML20205K3911986-02-24024 February 1986 Forwards Updated Reg Guide 9.3 Info for Antitrust Review of Facility,Per Jl Funches 861218 Request ML20153E0761986-02-18018 February 1986 Identifies Witnesses Scheduled to Testify on Applicant Behalf Re Contentions 7,10.1 & 10.5 Per ASLB 860114 & 23 Scheduling Order & Supplemental Scheduling Order, Respectively.Svc List Encl.Related Correspondence ML20147C4651986-02-14014 February 1986 FOIA Request for All Documents Re Mcnally,B Weatherford, J Register,St Register & L Price ML20151W8721986-02-10010 February 1986 Forwards Vogtle Energy Generating Plant Groundwater Monitoring Program Jul-Dec 1985 & Results of Hydrogeologic Testing Power Block Area Vogtle Electric Generating Plant.... W/Svc List.Related Correspondence ML20151U7241986-02-0505 February 1986 Forwards site-specific Emergency Response Plans,In Response to 850812 & 1001 Memorandum & Orders Re Ruling on Proposed Contentions on Emergency Planning & Ruling on 850905 Reconsideration Motion.Svc List Encl.Related Correspondence ML20199E3961986-01-15015 January 1986 FOIA Request for Documents Re Allegations,Findings & Orders That Pullman Power Products Employees Intimidated & Harassed QC Inspectors at Nuclear Facilities ML20138P6151985-12-17017 December 1985 Advises That Applicants in Accord w/851212 Ltr Stating Proceeding Expected to Commence in Mar 1986.Emergency Planning Issues Remaining After Summary Disposition Will Be Ready for Mar Hearing.Related Correspondence ML20133K9991985-10-18018 October 1985 Forwards Emergency Planning Zone Map.W/O Map.Svc List Encl. Related Correspondence ML20133F1131985-10-0404 October 1985 Forwards Emergency Public Info/Educ Matls for Plume Exposure Pathway Emergency Planning Zone.Challenges to Adequacy of Matls Should Be Submitted by Joint Intervenors within 30 Days.Svc List Encl.Related Correspondence ML20210K5041985-10-0303 October 1985 Forwards for Review,Petition & Supporting Brief Re Dept of Labor Case 85-ERA-27 (Mcnally,Et Al Vs Georgia Power Co), Per C Whitney Request.W/O Encl ML20210K5111985-10-0303 October 1985 Forwards for Review,Petition & Supporting Brief Re Dept of Labor Case 85-ERA-27 (Mcnally,Et Al Vs Georgia Power Co), Per C Whitney Request.W/O Encl 1990-06-25
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a e a e.g'n = =c 0+ o Es eose C 880# Y One ATTORNEYS AT LAW CANOitR sulLDING, Suitt I*00
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, AnANTA.GEORGLA 3004J ,res o,.te,o.u nymete 4o4 e ese-sooo esa-sona JCSSC P. SC64AUDIES.JR* castt: was sino October 3, 1985 Mr. Bradley Jones USNRC Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303 Re:
McNally, DepartmenFoT Labor Case ~io.et al. v.85-ERA-27 Georgia Power Company
Dear Mr. Jones:
I have been working with Chuck Whitney in the above-captioned case and we have prepared the enclosed Petition and supporting brief that we want to file in this case by next Monday. Chuck has asked that I submit a copy of it to you so that you can review it and comment if you have any questions or if we have inadvertently mischaracterized p anything. If there is any consnent you would like to make, please call Chuck at his Augusta office at (404) 724-4267.
If for some reason Chuck is unavailable, please feel free to call me.
Ve r y yours, c/e w g Je se P. Schaudies, Jr.
JPS/jdm Enclosur cc: . Bruno Urhlich Charles W. Whitney, Esq.
e 8604280346 860328 PDR FDIA FOWLERS 6-43 PDR
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NUCLEA3 CEGULATCGY COMMISSION REGION ll 2 g 101 MARIETTA STREET.NW.
- ATLANTA.GEORGB A 30323 Georg1a Power Company DEC2 4 ISE ATTN: Mr. R. J. Kelly Executive Vice President P. O. Box 4545 Atlanta, GA 30302 Gentlemen:
SUfuECT: REPORT NOS. 50-424/85-53 AND 50-425/85-38 On November 18-22, 1985, NRC inspected activities authorized by NRC Construction Permit Nos. CPPR-108 and CPPR-109 for your Vogtle facility. At the conclusion of the inspection, the findings were discussed with those members of yotur staff identified in the enclosed inspection report.
Areas examined during the inspection are identified in the report. Within these areas, the inspection consisted of selective examinations of proc:edures and representative records, interviews with personnel, and observation of anctivities in progress.
Within the scope of the inspection, no violations or deviations were icientified. c Should you have any questions concerning this letter, please contact us, Sincerely, N. p.v u .
e, Virgil L. Brownlee, Chief Reactor Projects Branch 2 Division of Reactor Project s
Enclosure:
Inspection Report Nos. 50-424/85-53 and 50-425/85-28 t J J. U l $ 2 l 9 f a n /
Cc w/ encl:
R. E. Conway, Senior Vice President Nuclear Power
- 0. O. Foster, Vice President and General Manager Vogtle Project H. H. Gregory, III, General Manager, Vogtle Nuclear Construction G. Bockhold, Jr. , Vogtle .
Pirr.t Manager ,.
8 L. T. Gucwa, Chief Nuclear Engineer cc w/ encl: (Continued See page 2)
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' 2 Georgia Power Company DEC2 41985 cc w/ encl: (Continued) .
Ruble A. Thomas, Vice President-Licensing Vogtle Project Ed Groover, Quality Assurance Site Manager C. W. Hayes, QA Manager J. T. Beckham, Vice President
& General Manager - Operations J. A. Bailey, Project Licensing Manager George F. Trowbridge, Esq.
Shaw, Pittman, Potts and Trowbridge Bruce W. Churchill, Esq.
Shaw, Pittman, Potts and Trowbridge Ernest L. Blake, Jr. , Esq.
Shaw, Pittman, Potts and Trowbridge
- James E. Joiner, Troutman, Sanders, Lockerman and Ashmore James G. Ledbetter, Commissioner Department of Human Resources Charles H. Badger, Office of Planning and Budget, Management Review Division Deppish Kirkland, III, Counsel Office of the Consumer's Utility Council Douglas C. Teper, Georgians Against Nuclear Energy Laurie Fowler, Esq., Legal Environmental Assistance Foundation Tim Johnson, Executive Director Campaign for a Prosperous Georgia Morton B. Margulies Esq., Chairman Administrative Judge, Atomic Safety and Licensing Board Panel Dr. Oscar H. Paris. Administrative Judge Atomic Safety and Licensing Board Panel Gustave A. Linenberger, Jr. . Administrative Judge, Atomic Safety and Licensing Board Panel Billie Pirner Garde, Citizens Clinic Director, Government Accountability Project an.
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t UNITED STATES
[me ath *g .4UCLEA3 CEGULATORY COMMIS$1*:N y- -
RE:fo Il y j 101 MARIETTA STREET. N.W.
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R: port Mos.: 50-424/85-53 and 50-425/85-38 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos.: 50-424 and 50-425 License Nos.: CPPR-108 and CPPR-109 Facility Name: Vogtle 1 and 2 Inspection Conducted: November 18-22, 1985 Inspector: kdkE J. F. Harris
/2/3 3/P f Date Signed Approved b & Ar-] t MW
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T. E. Conlon, Section Chief Date S'igned Engineering Branch
- Division of Reactor Safety
SUMMARY
Scope: This routine, unannounced inspection entailed 37 inspector-hours on site in the areas of structural concrete, post tensioning activities, and employee ccncerns in civil construction.
Resultr.: No violations or deviations were identified.
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". REPORT DETAILS
- 1. Persens Contacted Licensee Employees
- R. E. Conway, Senior Vice President
- D. O. Foster, General Manager Vogtle Project
- M. H. Googe, Project Construction Mana;er
- E. D. Groover,,QA Site Manager
- R. C. Harbin, Manager Quality Control
- P. Ciccanes, Regulatory Compliance Specialist
- G. A. McCarley, Project Compliance Coordinator Other licensee employees contacted included
- construction craftsmen, engineers, and technicians.
NRC Resident Inspector
- 2. Exit Interview The inspection scope and findings were summarized on November 22, 1985, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the licensee.
The licensee did not identify es proprietary any of the materials provided to or reviewed by the nnspector during this inspection.
- 3. Licensee Action on Previous Enforcewent Matters ,
This subject was not addressed in the inspection.
- 4. Unresolved Items Unresolved items were not identified during the inspection.
5.. Independent Inspection Effort Construction Progress The inspector conducted a general inspection of the soils and concrete testing laboratory, concrete structures, ongoing concrete curing operations and backfill operations to observe construction progress and construction activities. _
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2 Within the areas examined, no violations or deviations were identified.
- 6. Containment, Structural Concrete (47054) - Unit 2 The inspector observed preparation for the final concrete placement of the Unit 2 containment dome. The placement was scheduled for November 22, 1985, but had to be rescheduled for November 26, 1985, due to adverse weather resulting from Hurricane Kate. Acceptance criteria examined by the
. inspector appeared in the following documents:
Specification X2AP01, Placing, Finishing and Curing Concrete
- Procedure CD-T-02, Concrete Quality Control
- FSAR Secticns 3, 12, and 17.
Observations showed that the area was being properly cleaned, that re-inforcing steel was properly installed, and that equipment was being in-stalled to allow proper placement of the concrete. Examination of the concrete testing laboratory and batch plant showed that the calibration of the batch plant and testing equipment were current and that they were in ,
good working order. Discussions with QC inspectors and craft personnel <
concerning preparation for the dome placement indicated that they were aware of the specification and procedure requirements for the preparation and placement of the concrete pour for the dome.
Within the areas examined, no violations or deviations were identified.
- 7. Containment (Post-Tensioning) Observation of Work (47063) Unit 1 The inspector observed the stressing of horizontal tendon numbers 127, 129',
and 139. Acceptance criteria examined by the inspector appear in the following documents:
Specification X2AF04 - Rev. 3, Containment Post Tensioning System
- VSL Field Instruction Manual for Installation of Post-Tensioning System, Rev. 10 Drawing PT-11.2-1, Horizontal Tendons, Unit 1 Drawing P1372.23, Horizontal Tendon Stressing Data Observations included checking calibration of the stressing rams, witnessing measurement of elongation of the tendon strands, seating measurements, lift off pressure, and cutt;ng of wire strands following completion of stressing activities. Observations and review of stressing data showed that the stressing operations were being conducted in accordance with require-ments and that the operations were being monitored by quality control l
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3 inspectors. Discussions with craft and quality control personnel and responsible engineers indicated they understood the requirements for the stressing operations.
Within the areas examined, no violations or deviations were identified.
- 8. Containment (Post-Tensions) Review of Quality Records (47065) - Unit 1 The inspector examined quality records relating to post-tensioning activi-ties for horizontal tendons in the Unit I containment. Acceptance criteria examined by the inspector appear in the documents listed in paragraph 7.
Records examined were for horizontal tendon numbers 2, 3, 4, 9, 13, 14, 15, 19 and 20. Records examined included; tendon installation reports, quality control checklists, stressing reports, and tendon greasing reports.
Review of these records showed that the tendons were installed in accordance with specification requirements and that problems encountered during stressing operations were being identified and properly addressed.
Within the areas examined, no violations or deviations were identified.
- 9. Employee Concerns, Discussions, and Findings ]
The following employee concerns were reviewed:
- a. Backfilling Against North Wall of Control Building (1) Concern The north wall of the control building (an exterior wall at level D) was backfilled before it cured. As a result, there was'a lot of honeycombing on the wall.
(2) Discussion The inspector examined drawings of the control building, walked down the exterior and interior of the control building, discussed placement of concrete and backfill activities in the control building with quali ty control inspectors and engineers and examined records relating to backfill and concrete placement for the control building.
Review of drawings showed that the exterior wall on the north side of the control building begins at level.B at elevation 180 and not at the D level as stated in the concern. Discussions with QC inspectors and engineers and examination of records disclosed the backfill was placed against the north wall of the control building before the specified time. This was identified by a quality control inspector in Deviation Report CD-1762 dated February 17, l 1982. This deviation report stated that backfill was placed
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i against the north wall of the control building to elevation 196 which was contrary to requirements that no backfill be placed I above elevation 186 before placement of the level A concrete slab which ties into the north wall at elevation 200. This problem was submitted for engineering review and as a result the backfill was removed. Analysis by design engineers showed that no structural damage was done to the north control building wall. A walkdown of the control building by the inspector showed no evidence of any adverse cracking or structural damage.
Placement of the backfill against the wall would not cause honeycomb in the concrete because by the time the forms were removed, the concrete would have hardened to the point where the backfill could not have had any affect on the concrete surface.
Research of the literature and experience has shown that honeycomb is caused by inadequate vibration near the outer face of the walls where the reinforcing steel interferes with the flow of the !
plastic concrete. !
(3) Findings Investigations showed that backfill was placed against the north wall of the control building before the specified time. This was identified and investigated by the licensee. The backfill was removed and the structure was evaluated to determine if the backfill had caused any structural damage. The analysis showed no structural damage due to the placement of the backfill. A walkdown of the structure by the inspector disclosed no evidence of structural damage. Backfill against the walls would not cause honeycomb or defects in the concrete because the concrete would-have been in a hardened state by the time the forms were removed'.
No problems with the quality of the concrete were substantiated.
- b. Falsification of Soil Density Tests (1) Concern Soil density test results had been falsified. Proctor tests were run on the soil compaction which was done at the site. Proctor tests are tests to determine soil density and moisture and these test were done on the compacted soil for the power block.
Individuals involved in this matter manipulated the test results to indicate that they were acceptable. Results are too good to be true in that results are too perfect. -
(2) Discussion The inspector examined Bechtel Specification X2AP01, " Earthwork and Related Site Activities", and Georgia Power Company procedure CD-T-01, " Earthwork Quality Control", and reviewed proctor and
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field density test data on compaction of soil material in the power block from 1978 through 1980. The inspector also inter-viewed seven quality control inspectors that were involved in inspection of compaction of backfill in the power block.
Review of specification X2AP01 and procedure CD-T-01 showed that the required field compaction of the backfill is specified in terms of percent of maximum dry density as determined from the laboratory modified proctor test (ASTM D-1557). In perfomance of the laboratory proctor test (ASTM D-1557), soil samples are compacted at varying moisture contents in a steel mold of known
' volume using a specified compacting effort. The purpose of the test is to determine the maximum soil density and the corre-sponding optimum moisture content at which this maximum density can be obtained. The test results are presented as.a plot of the dry density versus moisture content. Connection of the plotted points results in a curve shaped line. A line to the curve peak from the vertical axis containing density values in pounds per cubic foot represents the maximum dry density for that material i - and a vertical line from the peak of the curve to the horizontal axis containing water content values in percent of dry weight -
represents the optimum moisture content at which the maxisnum dry j density is obtained. Specification X2AP01 requires that soil in the power block to be compacted to an average of 97 percent of the maximum dry density determined by the laboratory proctor test.
The specification also requires that the moisture content of the soil at the time of compaction be within minus three percent or plus two percent of the optimum moisture cor. tent detemined by the laboratory proctor test.
Procedure CD-T-01 details the method for quality control testin'g' of Category I backfill to . assure the backfill is compacted to the density and moisture limits determined by the laboratory proctor test. The testing is performed by quality control (QC) soil inspectors using field density (sand cone) tests (ASTM D-1556).
The results of the field density tests and the soil samples collected in performance of the field density tests are sent to the soils laboratory by the QC field inspectors. In the soils lab, laboratory technicians test the soil samples and calculate the results of the field density tests. The field density test ,
results are determined by comparing the density of the in-place soil (determined by sand cone method) with the laboratory proctor
' results and computing the percent compaction (field density divided by proctor density) of the in-place backfill material.
Review of the field density test data from 1978 through 1980 showed that, for the most part, the power block backfill was compacted to a density of 97 to 107 percent of the maximum density determined by the laboratory proctor. Some of the field density i.
tests showed that backfill was compacted to 93 to 96 percent of the maximum proctor density. These low test results were identified and addressed by the licensee. Review of the data
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! indicated 'that the results were reasonable and normal for the compacted effort being used to compact the backfill (compacted with a ten' ton vibratory roller).
Interviews with the seven quality control inspectors disclosed no evidence of manipulation or falsification of soil test data. Two inspectors indicated that they heard one individual would same-times round a decimal up (e.g., 96.5 to 97.0) to make a test i
- appear better, but that they had never witnessed or actually seen the individual do this. Review of test data by this inspector showed no evidence where decimals had been rounded up. All seven inspectors stated that they had no knowledge of any falsification of test data and indicated that they were satisfied with the quality of the compaction of the backfill.
In addition to the investigation of compaction of soil material in the power block during this inspection to satisfy the stated concern, this NRC inspector and two other NRC inspectors from the Region II office have examined controls on backfill activities during routine inspections conducted from 1978 through 1985.
- During these inspections, controlling specifications and proce- ;
l dures were reviewed, work activities were observed and records
! were examined to verify that backfill activities were being conducted in accordance with NRC requirements. During these visits, the inspectors also discussed quality control of backfill activities with civil quality control inspectors to verify that quality control inspectors understood the specification require-ments and that these requirements were being implemented. During these inspections, several minor violations regarding control cf moisture content were identified. The licensee was responsive ,in addressing and correcting these items. During one of these inspections conducted on November 16-18, 1979, this NRC inspector was informed by the Georgia Power Company QA supervisor that a severe storm on November 2, 1979, had aggravated ongoing moisture problems and eroded part of the backfill. Because the applicant failed to report the deficient condition to the backfill as required by 10 CFR 50.55(e), a Notice of Violation was issued.
- Subsequently a Confirmation of Action letter dated November 15, j 1979, from NRC Region II to Georgia Power was issued in which it i
was understood that Georgia Power would not continue with backfill placement in or around the power block area or concrete placement on affected structures without concurrence of NRC. Meetings were held with the applicant at the site and at the Office of Nuclear l Reactor Regulation (NRR) in Bethesda , Maryland regarding measures
! to be taken to correct the backfill. Corrective measures included
! testing to detennine the extent of defective backfill, removal of defective backfill and foundation slabs, installation of drainage facilities and a dewatering system and application of gunite (sand cement mixture) on slopes to prevent additional erosion problems.
{
7 The NRC inspectors observed the corrective measures tah correct the backfill and examined records documenting corrective measures during several onsite inspections. Re these inspections showed that the backfill was properly r-and that measures were taken to prevent future erosion pro:
Reviews of backfill activities were also performed by Geot.
Engineers from the NRC office of Nuclear Reactor Regulatiot These reviews resulted in some concerns being raised by i Geotechnical Engineer regarding the density of the comp backfill in the power block. To satisfy these concerns, representative of the Category I backfill were taken by licensee and tested by both an independent testing labora-the licensee's testing laboratory. The sampling and test these samples were witnessed and reviewed by NRC inspec from the two laboratories i Comparison of the test that the methodology results, being use d by the licensee to contr compaction of the backfill was reasonable and correct.
addition to the labaratory tests, the licensee hired a d-company to perform in-place standard penetration tests c existing backfill to verify that the density of the backfi '
design requirements. These standard penetration tests we by driving a two-foot eight-inch long cylindrical tube (c sampling spoon) having a two-inch outside diameter and a three-eight inch inside diameter into the existing backfi this method, the sampling spoon, which is attached to dri is driven into the soil by blows of a 140-pound hamer i from a height of 30 inches and impacting on a driving c attached to the drill rods. Each blow count is accompli.
raising the cylindrical shaped hamer, which has a cente that allows it to be raised along the shaft attached to t collar, with a rope to a height of 30 inches and then allc hammer to free fall and strike the drive collar. After sampling spoon has penetrated six inches into the soil .
i penetration test is started and the number of blows requ j produce the next one foot of penetration is recorded. A over 50 blows per foot is considered very dense. Review penetration data showed the following range of blow countt l backfill: 0-10 feet, 32- 131 blows with a conservative a.
50 blows; 10 to 30 feet,62-200 blows with a conservative of 100 blows; 30 to 80 feet, 100 to 200 blows with a cons average value of 150 blows. Results of the confirmatory by the independent laboratory and the standard penetratic
- indicated that the recorded density values accurately ref in-place density and compaction of the backfill.
Review of NRC inspection reports also showed that a si concern was identified in 1981. This conce n indicatec' results from backfill proctor analyses were altered to is that failing tests complied with spe:ification requiremen-
8 concern was' investigated by an NRC Region II inspector and an Ni investigator during the period of May 18 to August 7,1981.
Results of this investigation, documented in NRC report number 50-424/81-09 and 50-425/81-09 dated October 22, 1981, indicate:
there was no evidence that test data was being altered to indica failing tests meet requirements.
(3) Findings Review of records and discussions with civil quality control inspectors failed to show any evidence that backfill records we-falsified. Additional independent confirmatory testing of th(
backfill by independent organizations confirmed that the methodology being used and that the in-place density of the backfill met specification requirements. The concern was not substantiated.
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