|
---|
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
[Table view] |
Text
%ED conumy r
SHAw, PITTMAN, POTTs & TROWBRIDGE A *AmtNtatmp eNCLuCING pmOFE SS'ONAL Compomat ONS 1800 M STREET. N. W.
WASHINGTON. D. c. 20036 r AMSAY o potvt, p C. ( '
MAND "ENNt?M J MAUTMAN DamVL ANNE L ANOtm 1 tE uer L. pervu Ame, p C. e SCo Abe st L L,aPse C Sit g C. - Davio LawmE Ncg weLLg m ***it s p D #0mftm
[*e O mott S E eR 5 8 N'S C. TELECO*'Em S V N *TL L "Em*
G,t mALO CH Ammorr.
- CL $a'y*[",**, M *l& ,k e C (202) 822 #O99 & 822 H99 a 4
LaN"af am 'o*g[NO yQ , 'SI O ? 07 Y HAN P C. y"*,[y),hT ","g#d *n gDg4 .pC- _ Mam;Ey g t,ANO* gM,*g N ,Y,$ 7ggung Q$ L Yv SOMN e.mwiNELANDER pC.
- k,"I " ,$INbC
- map'r AN *OO h ,Na*g*g" nCwt u DCEN O l sg ryt ev L. vastpM. P C- (20 #0 12 MAL *H A TA vtom sm A *A t m+Cm L a iG ** TON HI LE NC O SbN. s . F C. Y.'aNg,"$. GI A Skaa r G g t ^
p wYN'[AdE"e og s g mu a ns Su"f S*mAGut MantiN O meatg C. twomaat w McC o m u iC m suortw A SAhot g n E me4 m mO S SOftt. D C No[a" *C n g a
U
^[c[a'nN "g'aN A AN O
- '**'(********) ;pr:3 <,,cfmqvata sm P'P.r.et, L*n!"h'o, e. se 'P C. Et*N '.'.'."
he *[S'".
A L L "O**
!A* ?A.$ " CABLE ~SMA*L AW y!Jr"~'t** I* *a" hav am.tt p
-a ma a vG, N.s,ma C n.
s mNg Se L etant se , p C.
p C. s0-4 L. 24mm sm
twA
,, a,n.Nn, SOONg owN w wong mum m,, A N.* k"u"o#"^"e tS C
'a u*'fa n" "N t=Of f*tETONSsONES.pC. Q f'gg*ggy a vimoihiA OrriCg *Aut 5 mit a c a,
- k"<"u'A[s 'C'*"OhANl f OTA SACHEM la s at C. tNb ' T *w","sumGM L t 190s Famme cetDet OmNE . vg
- ** 7 p C- y,",#E2g**g 3 'et *,'*a'#O ""'N **c k N. wmOIN4 2iO2 rYI'E t $ Dw" "wJ SINE .
=r wCs.r a M. Ntr: ,,. --- S w s:e: er:Ac. :rH r .A =1.* .e
""w'a
~
Att
- O m o [c daSEC2um Ib $ b "oSNONees es s a u .ce'Cmram.N DC -, Aetw. . b., >/ PO318b 239 7 d"mwCu eae.N ::r. =S:'us S'....
S T E p.e t N e u vett g n, a C w wmop w= *eOOG g Swt s A usC wamviv / a ah Ot eta w SvLv A ** L'O NOfN ANE S S ** A p* mo Y me c a m STEENA G Nattm.
sa'N'g na S e e.NA n.e v mO.,*p=s C. .
- C CE LeSSA A p'DGwar - sg 7 F'aty nL SNvog n. Su' SAN C. LONo stet t ?.
p\ Fmt 0 DNASNER
< ; sow.e ,_O AL,. *. '.so' .*.='"s
. . w .. . in.ae C-J c "_ ,0 R.C- A RO S ..Arn
, pOes et a. cohae C '
coumSEL z , r. . -
- "mo > Pe ruary 28, 1986
.m...NS o,R.e,o,AL,eo ...
sf 822-1474 A
n ., m L Morton B. Margulies, Chairman Mr. Gustave A. Linenberger, Jr.
Atomic Safety and Licensing Atomic Safety and Licensing Board Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Dr. Oscar H. Paris Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of Georgia Power Company, et al.
(Vogtle Electric Generating Plant, Units 1 and 2 Docket Nos. 5 0-4 2 4 and 5 0-4 2 5 04-Gentlemen:
Attached for the information of the Licensing Board and of the parties is a draft report, " Ground-water Numerical Modeling" (February 1986).
Sincerely, G603040453 060220 { ()
PDR ADOCK 05000424 w. 8"4 O PDH David R. Lewis Counsel for Applicants cc w/onc1:
Service List g
~
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )
)
GEORGIA POWER COMPANY, et al. ) Docket No. 50-424
) 50-425 (Vogtle Electric Generating Plant, )
Units 1 and 2) )
SERVICE LIST Morton D. Margulies, Chairman Atomic Safety and Licensing Atomic Safety and Licensing Board Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Washington, D.C. 20555 Commission Washington, D.C. 20555 Mr. Gustave A. Linenberger Atomic Safety and Licensing Board Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Appeal Board Panel Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Dr. Oscar H. Paris Washington, D.C. 20555 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Douglas C. Teper Washington, D.C. 20555 1253 Lenox Circle Atlanta, Georgia 30306 ,
Bernard M. Bordenick, Esq.
Office of Executive Legal Director Tim Johnson U.S. Nuclear Regulatory Commission Campaign for a Prosperous ,
Washington, D.C. 20555 Georgia l 1083 Austin Avenue, N.E. !
Bradley Jones, Esquire Atlanta, GA 30307 l Regional Counsel U.S. Nuclear Regulatory Docketing and Service Section Commission Office of the Secretary I Suite 3100 U.S. Nuclear Regulatory l 101 Marietta Street Commission I Atlanta, GA 30303 Washington, D.C. 20555 i
)
4 1
j l
1 o
4 .
=.
p coggESW NDENUs DRArt a q t
< 9
'f 9- :. ^ -
-n 2 pl\q 3 - 1986 * :.
DOCKETING &
p EEJtVICE ER ANC:I r GCCY Air,J g V0GTLE ELECTRICAL GENERATING PLANT gT\'
l t
l l
GROUND-WATER MUNERICAL NODEL l \
i i
l I
l 1
1 i
' Bechtel Inc.
February 1986 I k.
1 1
l
- . I
GROUND-WATER NUMERICAL N0 DEL FOR V0GTLE A numerical model was used to simulate the ground-water conditions at the Vogtle plant site and its vicinity. It was intended to complement the analytical calculations of ground-water flow and travel times. The specific objectives of the ground-water flow simulation for the Vogtle site were to:
- 1. Investigate if the assumption of persistently high permeabilities of Utley limestone throughout the area is consistent with water levels in the vicinity of the site;
- 2. Determine the location of the ground-water divide with respect to the power-block area; and i
- 3. Investigate the influence of backfill on water levels in the power block area.
The methodology and results of the numerical enalysis and the conclusions derived therefrom are described in the following sections. The numerical model used is GS2, described in " Documentation and User's Guides G82 &
GS3 - Variably Saturated Flow and Mass Transport Models" (NURgG/CR-3901, April 1985).
I. Ground-Water Flow Simulation The finite-element mesh used for the ground-water flow simulation is shown in Figure 1. This mesh contains 455 nodes and 413 elements. To improve accuracy, the mesh is refined in the power block area where the (14773) 1 t - - _ _ _ _ - - - - - - . . - - - - - - _ __-- - . - - - - - - _ _ _ ------ _ - - _ - - - - - - - _ _ _ _ _ - - - _
nodal spacing is approximately equal to 150 ft. The elements become b progressively larger toward the boundaries.
The boundary conditions imposed on the model are shown in Figure 1. The model extends to the stroene bordering the interfluvisi, ridge on which the plant is located. The boundary conditions of the model at these streams are constant head conditions. That is, water levels remain at the elevation of the streams at these boundaries, or, as in the case of the boundary along the Savannah River, at the top of the mari exposed along the bluff. The levels of the streams were determined from the U.S.
Geological Survey 7.5-minute quadrangle topographic sheets covering the area. The top of the earl was taken from Figure 2.5.1-30 of the Vogtle .
FSAR. Beneath the narrow area at the northwest boundary between the Mathes pond drainage and the tributary to Daniels Branch, no-flow conditions.are specified.
An average annual recharge rate equal to 15 inches was specified throughout the model. This is a maximum of reported values for the region and corresponds to about one third of the average annual 1
precipitation in the area.
The transmissivity in the study area, based on field and laboratory -
j tests, is postulated to range from 2,000 to 25,000 syd/ft (as11ons per f day per foot) in the north where the Utley limestone is present, and between 500 and 4,000 spd/ft in the south where only the sands of the
\
(14773) 2 l
< J
_.a _- 4 Esenwell Group are present. Transmissivity values within theau ranges were successively assumed in the model until a satisfactory agreement i between calculated and observed water levels prior to construction was obtained. The water-level data prior to construction were used for calibration of the model because they most closely approximate a steady-state condition. The results of this calibration procedure are presented below.
The water levels used as a reference for the model calibration were i
weighted averages of measurements made between January 1, 1971, and May 30, 1974, kt each of thirteen wells located at the site of the Vogtle plant prior to construction. It is assumed that the reported water .
j levels taken during that period are all valid measurements representing
, the water table. Because there are few observation wells in I
the southern part of the study area, the local topography was used to I provide upper bounds to the model results. Specifically, criteria for acceptable results in the southern part of the study area are that water levels cannot be higher than a level 20 feet below ground surface.
II. Model Test Cases f The T (transmissivity) distribution that was found to provide the most satisfactory agreement between measured and calculated water levels is i
! shown in Figure 2. This simulation assumes three areas of aquifer materials with similar T values equal to, from north to south, 16,000 8pd/ft (area 1), 8,000 spd/ft (area 4), and 2,000 spd/ft (area 2). The Utley limestone is present in areas 1 and 4. The results of the (14773) 3
. e 3
sinalation are shown in Figures 3A and 3B, and in Table 1. Area 3, not i included in this sinalation, is the area excavated to the mari and backfilled for tha power block structures. It is the rectangular area within the dashed line of Figure 35. Figure 3A presents five- foot contours of the calculated water levels for this combination of ,
transmissivity and a recharge rate of 15 in/yr. Figure 33 is a close-up i
i~
view of the power block area, with one-foot contour intervals. The weighted-average water level measurements are shown in parentheses next
[ to the well locations in the figures.
i.
4 Figures 4 through 8 present results assuming different distributions of 4
- transmissivity in the study area. Figures 4A and AB and Table 2 show the .
results obtained with T = 16,000 gyd/ft in areas 1 and 4 and T = 2,000 l
- syd/ft in area 2; the same combination of transmissivities as in Figures fi ! 3A and ~35 except that the transmissivity in area 4 is increased to 16,000 f spd/ft (equal to that of area 1). The results of this case is similar to
'l that of Figures 3A and 35. However, the fit to the south of the power f
block (i.e.; well 124) is not as satisfactory as when the intermediate transmissivity zone is included in the model (compare Tables 1 and 2).
) .
l l In Figures 5A and 55. T is increased to 20,000 spd/ft in areas 1 and 4, i and T in area 2 is decreased to 400 spd/ft. This combination of transmissivities is seen to yield water levels that are too low in the i
)
! north and excessively high in the south (Table 3), and is considered i
l unsatisfactory.
1 I
a (14773) 4 l
1
I Figures 6A and 63, and Table 4 correspond to the case when T = 16,000 b spd/ft in area 1, 8,000 spd/ft in area 4, and 4,000 syd/ft in area 2; that is, same conditions as in Figures 3A and 35 and Table 1, except that I the transmissivity in the southern part of the model has been increased. {
Figures 7A and 75 (Table 5), and Figures SA and SE (Table 6) are two additional cases applying T = 8,000 syd/ft in area 4 and 4,000 gyd/ft in I area 2, but reducing the transmissivity in the northern part of the model, (area 1); first to 12,000 syd/ft and then to 8,000 spd/ft, respectively. Neither of these cases are found to improve the model l calibration achieved in Figure 3, which is therefore considered the best case among the simulations performed in this study to fit the apparent .
weighted average water-level conditions prior to construction.
l III. Influence of Backfill on Water Levels 1.
G !
Figures 9A and 95 and Table 7 show the results when backfill material is included in the model at the power block excavation. The backfill material was assigned a transmissivity of 8(0 spd/ft (area 3) based on a ,
permeability of 1200 ft/yr and a thickness of 35 feet. The zone of [
backf111 material is that area inside the dashed rectangle on Figures 9A and 98. Recharge in the model is assumed to be siellar to preconstruction conditions except in the power block excavation area. In t
that area it is restricted to the portion that will not be covered by surface paving or buildings. The largest open area available to recharge l
, is in the southern portion of the backfill. The calculated water levels in the power-block area with backfill in-place are slightly higher than ;
without backfill (i.e., Figures 3A and 33). ,
5 !
(1477s) t A__
1'
~ .
( IV. Conclusions Based on the results of the numerical modeling presented in sections II and *.II it is concluded that:
- 1. Of the model test cases used in this study, the closest approximation of transmissivities in the study area is as shown in figure 2, wherein the study area is divided into three transmissivity zones: 16,000 spd/ft in the northern part (area 1),
2.000 syd/f t in the southent part (area 2), and 3000 spd/f t in a transition zone (area 4) between the high- and low-transmissivity .
regions.
( 2. High permeabilities (i.e. , transmissivities greater than 16,000 sp4/ft) are not persistent in the area underlain by the Utley timestone.
- 3. Over the range of transmissivity values modeled, the ground-water divide remains ecuth of the ple:st.
- 4. A slight rise in water levels is apparent beneath the power block area when tu backfill material is considered. The direction of ground-water flow rossins frou south to north beneath the power block.
N (14773) 6
~
?
i ('
- Table 1 - Match of Water Levels at Wells by "Best-Fit" Case l
================33==== magn =====================
Observation Wells Mcdel Simulation Water Level Elev. Water Elev. Di++erenco No. (Weighted Average. Ft) (Ft) (Ft) 42D 159 161 2 124 166 16e 0 129 1$6 160 2 140 164 160 -4 142 15s 157 1 143 158 159 1 176 164 165 1 177 164 160 -4 l '7d 161 160 -1 243 149 156 f3 244 160 158 -2 .
I 245 160 161 1 249 160 160 -3 Statistics of water level difforonces:
(- Artthmetic mean 0.2 Standard deviation 3.1 Sum of squarnH d1VidQd by N (N213) 9.4 an=======_ =wan======manern..........a. 2 n........... .. .
l I
s O
I.. .
l 3
[
Table 2 - Match of Water Levois at Wells by Test Caso 1
===============================================
Observation Wolls Model Simulation Difference Water Level Elev. Water Elev.
i No. (Weighted Average, Ft) (Ft) (Ft) l
! 42D 159 162 0 124 166 165 -1 129 158 161 3 l 140 164 161 -3 l 142 156 157 1 143 158 160 2 176 164 165 1 177 164 162 -2 178 161 160 -1 243 148 156 0 044 160 159 -1 . !
045 160 162 2 249 163 161 -2 Statistics of water lovel difforencost
( Arithmotic mean 0.0 Standard deviation 2.0 Sum of squares divtdod by N (N=13) 8.S i
============nn===============n===wn====n===w =======n
e l
I L
l 1
\
l Table 3 - Match of Water Lovels at Wells by Test Case 2 l
l ms======================u==========s=======================
l l
l Observation Wolls Model Simulation l
Water Level Elev. Water Elev. Difference t
i No. (Weighted Average, Ft) (Ft) (Ft) l ______________________________ _________________________
l 42D 159 165 6 124 3 166 le9 129 158 lo3 5 140 164 164 0 142 l'J 6 loo 4 143 158 lo2 4 176 164 174 10 177 164 16e 2 170 161 160 -1 243 148 158 10 t 244 160 161 1 -
l 245 160 165 5 l 249 163 164 1 l
l Statistics of water level difforences:
( Arithmet1c innan 3.9 Standard deviation 3.3 Gum of squaros divided by N (Nm10) 25.7
==============n============mn===mamanamussw_mmans
i l
_ _ _ _ _ _ - _ _ _ - - _ _ __ > _ _ _ _ O
(-
, Table 4 - Match of Water Levels at Wells by Test Caso 3
======================== ======================
I Observation Wells Model Simulation Water Level Elev. Water Elev. Difference No. (Weighted Average, Ft) (Ft) (Ft) 42D 159 158 -1 124 166 161 -5 1.'9 159 159 0 140 164 159 -S 142 156 153 -1 143 158 157 -1 176 164 157 -5 177 164 157 -7 176 161 160 -1 243 148 154 6 244 160 156 -4 .
i 245 160 158 -2 249 163 159 -5 Statistics of water level differences:
f( Arithmetic mean ,
-2.5 Standard deviation 3.3 Sum of squares divide?d by N (N=13) 16.9
===============================================
I 4
l l
\
f
\ Table 5 - Match of Water Levels at Wells by Test Case 4
===============================================
Observation Wells Model Simulation Water Lovel Elev. Water Elev. Difference No. (Weighted Average. Ft) (Ft) (Ft) 42D 159 160 1 124 166 162 -4 129 158 157 1 140 164 159 -5 142 156 156 0 143 158 159 1 176 164 160 -4 177 164 158 -6 178 161 160 -1 243 148 156 8 244 160 159 -2 .
245 160 160 0 249 163 159 -4 Statistics of Water lovel differences:
( Artthmetic mean -1.2 Standard deviation 3.5 Sum of squares divided by N (N=13) 13.C
======================e==,2====-==============
i 9
O
(.
Table 6 - Match of Water Levels at Wells by Test Case 5
======================================================-==== _
Observation Wells Model Simulation
__ _____== ---- _ _ _ _ _ _ _ _
Water Level Elev. Water Elev. Difference No. (Weighted Average. Ft) (Ft) (Ft) 42D 159 165 6 124 166 167 1 129 158 164 6 140 164 164 0 142 156 161 3 143 158 16s .a 17e 164 164 0 177 164 163 -1 178 161 161 0 243 148 160 12 244 160 162 2 ..
! 245 160 164 4 l 249 163 163 O l ________. -___________________ _________________________
9tatistics of water level differences:
( Arithmetic mean 3.1 Standard d'evi a t i on 3.6 Sum of squares divided by N (N=13) 22.2 l ===========u===============================================
l l
l l
l I
~
i Tabl'e 7 - Match of Water Levels at Wells by Test Case 6
== ============================================
Observation Wells Model Simulation Water Level Elev. Water Elev. Difference No. (Weighted Average, Ft) (Ft) (Ft) 42D 159 159 0 124 166 166 0 129 1'58 159 1 140 164 160 -4 142 156 157 1 143 158 158 0 176 164 166 2 177 164 160 -4 178 161 160 -1 243 148 155 7 244 160 157 -3 .
245 160 160 0 249 163 159 -4 Statistics of water level differences:
(- Arithmetic mean -0.4 Standard deviation 2.9 Sum of squares divided by N (N=13) 8.7
=== ===========================================
s I. I I .I E ! ! I. I. l l I l l l I l I l l l l l l I I. I. I . I .I I.
g,.a...i....i,,,,...,,,,i...,,...a...a,...i....i...a....ia,,,....i...a1..a....i....i.,,a,.....a....i...a.,..iz,_.i..,,i...a,,..i....i., _g
'i . 8 P
i l.5
- i
- i[E.
1 E-I.5 2
' LI i ; .I i;
'I '
- T l! O I i
i[
1 .
E
[.2
-i I !
Ll E-
-i &
- E-
- 1. .:
2
- i s
E 35 1i : -s E 31 j-i 5-ogi Eg 6-1 5 E-22 % ;
6i = -e z E E E!i d I/NE I!
4- : I/
- 3. :! ,
L 1.3.4 . I s5 U -! E/ b
!I-!
rj n/ il
=
a' a
e/
j; 1g'i
.i a -
tj
/ ~
,- ig Ta 8i
~
.I.2 3
a a/ -
/
/
P
/
/ i.
,,,, if Fi
> 1 e 5 * -YP g[ '
,- ' i ig -
~
_. s_N--s.-<-
- d r
g
'~~
E/ - ' '
5l1 - .hfE5 s .,,
N N%.%
- - s s
'.', -1 i ,. / , / '
, N ..
1 # '
g- 2 /
/ /
- z' r r
/ i i i
.s x N N
% I E_
,' / x x NN N :g
.: ,./ e f
e i I t x x N t
s :.
i , / a S E/
"fg
/ / \ \ \ N ! E
\
i f / \ 's 4 pg li ,
. / / / \ \ \ N a =
/
gi / / \ x 'N i
.i i
/ / / \ \ \ g,-
"8 !g l' -
~
3
- I P
i s .
jir le -
-i -
b
,,,..,..,,,,,,,,,,,,,.........,,,,,,........,,,,.,,,,.,,,,,,,...,....,,.........~,.,,,,......,....,....,,...,........,................
!!!!!!!!!si!Ist!i!I!iliti!!i.i!!
,.......,..........,_........1.............................,_,..............,_,.....,. .....................i....r.. .g 3
/ 3.
gi ts.
- =
i h i.i L. i.
t-i >> -
1 a a t >a s i, 11 l!ja- -
a s
4 _
g.: .... .
tg
.: ae* :.
i 1111 -
0 F li: Illi . -
il:
1
- r E-l.
s 1. i
+ - E o4 5 . 3
,: 4 -
- s -
3g i 4 -
+ :
2 -
1.. : . #
- f all ,,
- bi
- 4 - -
i.
- le-11: -
- /.d -
5 A
g; f -
,fil +
l -
/<j -
l-l
,j . . - . .
/ -
L-ij d' - - -
t '. - '
in 2g- ,$ .
,3 < .
j,
- E-m: - . p = ,,,,** 7
$!j (l-.
b.
o h
/- .
/
/
((,
-;p. .. n i -
h rs' . - -
i
.ig
{---
- g1/ .
- ;
.,p ga-;a f :-
3 -i r__ r ror 4 L
'g -
T-
- n)_s.
1 4 ~.
s s
- . :g s '
, c,/. /.
.i .f
/ -
. y.; .N - .
. j.
g /
/ d.' / - / -
1- 1-1-
s~m - s 1-i . -x
'N N :R I_;, .
N *
- S.
g g- \ - A '-.=,,,
~~
.-/-i- -s x - x . . N. - , :.
,,,#' .e - / - / - - \ \ -
L . N g E g,l 6-f.3 / - / - - \ -\ j \ . N
- - + El 3 - /./ - / - I- - -
\1- N . N s' t
/ - / - / - -
A -
'N -
. - ig g]s / - /- / - -
Lf \ -
A d l.
g.j .
/g [g 4 \ .
[g' E i j \t i l iD I 4
\ 2-I l]gi EpIqg513r 14e yll 5154 I1If 5ITI I3II 1EIi ff.3 lI1I .JlE IFll .IjE IIIE 13IT 53Iig5Ie.gs.E{giIII igI5f1gIfIf fTfIg15B1giIIEgIlgIgIqglgl3[]
- i. 5 :
- i. a i. a: a : i. g i g g g g i n l 6LTI g a g a g g g a sI 5gya
- - -- a.an 7 T I
m
!!!!!!!!!i111111 . . . . . , . . . . . . . . . . . , , . . . . . . .1!!n i.................,_...................................................111!i11: gI!
1 N i' li N F1 4 s s
., nn %
,s il I 1, il
h A[,E, y
')
3-:
o .: f s
/
p
. n %_ =
I- *# # e E!
~
I <
a' o n:
li 1 O, #
t
. ri S-I 3
- I
- ,I si 5 a I
~
i s . II 4 / F
~.....p,,.,m......p...,,,c...p...r..c...........c...c......r.......c...c....m.im..e,.c...c...r...c...r...c.r.c.
- g. ~ -
I, . I. . . I. . . . I. .
I, . . . . !,
-/,// / J ) -\
)<<e (~%--! ,
!- -, i
}
ms .
a [j[ -
. an. .
- =
- . -a lla / .-
a .
?: (
c' i
r---- ------ -----
(
- 2. j l l
!!- [! I -l '
1 i- i _n ' \
8~ l '
I $
a i ! _
\
i- .
E T. E i '
_t E l
si- l (
-l 3
o i
i \ ,
3- , -
d.
l______ ________ ____a l- g.
3 .
~
i - ,
I w x. . W, x.. \. . . ixN,:
i I I I !
e
- ,- ,_, y _ ,y v---,- ,y 3 .-mr. , .--r _., -,s
i d
!!!!!!!!!ill 11!i!i!i! ...................................r-g......_,..................................................................................,........1!i!!i.i!! ,
"i E-
\ [
li N F!
a % >
Eh 38
% I I
i / [, s \ i
,l i! _/ il
=
li s
.j FI i - S l F
I4 il f// LI h j j
/
[ s, b E-l #
-l Yi '
I p L~
5]j]
/
[* b N
l o
g- , j # [i-E gi
!!i . If
'n
~c o
Fl F!rf i le*
~
s!i 3 *f: s
!i a ;;
! d!5
/ \
P
$ . E!
*~~~
j
\
A.Ci.$]; g, ij j -
i h .,, s s . El
> ,, /
'i
-f a t, I
li E= , PI I ! I
- / !-
\
i i It i .
I I i i e Iii e I
f i i I
1 ,
Il l R 's, N .
~
l e i _
I; 8 E I
~
__ res ~l; 8& -
{.
Q* l
. _a -
o E$
I-
~
~
' 'E * ! -l
&E a a i i- ! 2 r-
)
8 E
I I
*s .
$l- I
-l i- si
-g l -
i 3-u
_ i ; ! . c
$ l N I _
2- e a l ! -'
E I i.. !
r i i
=
\.
'!- l
- s. l i
l -1 <
\
l
\ _ _ _ _ _ _ _. _ A Q g
'jh. . . ..y 'A. . . . x'x. ..,j' . .
I I I I I i
s 1
1 l
l l
!!!!!!!!!!!!ill!ini!sti!!!!i.i!!
i.................,_.,....,...,....,...........,..........,...,_,....,...,_,_,..,.,....,....,....,.......,.2...t, ,
~;$ - -
\\
! I,5 i!
i
!i '
5!
"i
'i
==
>> '. i-11 g :r1 Il;
.A ii at -
)' !!
T fl 'il ,
,] r # , l ',[
~- ' -
il 4' T
/.' -
b!
14 '
'l :~
$li ./ s o il fif ; Y v
[ f!:
w
$~i *%
t,1 i=b a
~
T s!j )
a pg j hl n:
I
' )e '
[i j
A .
**' i d]i _ = i .
r}i 6;
{( air- w l1 I
~b \"
5 ( l n ll[l$ 5 \
hs g g 4 - - ,
3j d % s ,,,
[3 ij -4,
~
[Il
,l I, 4 =
3 '
-i E r
.i l 4 / I' T
l
" 1 e e i , ,
! e
'- k(( ,
g "
( i e S
'e l' j E ii y I- !
5< lj l \ -I p
. E
, (.
,r ---- ----- ------
g i I :
y a , ,
k 4 31-
[- h.
3-li \
s
,rm, y .
l -
, N(i ,;
4 . , i I -
- 7. E g ' * -
5, l- [ ' -1 s
- g. 1 y
l \
3 '- .
l E. !
j -
4 -
i Q -i ..
- 3~ -
I j
e,
+ ' ,,,
_ %<'g I ! l i'j j
, . - .- m. , _ , - . . ,--. . .,- , - - - - -
i g
!!l!!!!!!!!!IEI!!!l!!!I88Ia a..,....,_,_,_,_,_,..................,...,m..,........,....,... n.a!!
,,...,_,._,...,....,........,.............a..t-
= =
m 7 li ~,.. Y
! /
, s, s, , s, , c.
i
=
g-x=
$ *' \ II
- a i e i g]
,o e N M W :s Th 7
Eb bbbb %
5l
~J t I Il[
f -
7
}} ' '
ss {\
*3
} ?
Elk '#
'e
) bi Yi ge -
ll/),I s V u
i-l # o N er E5 bl I 't # ,*
i a!] i i S s e r, -
i :
~WWjl y #s ,! !
u Il4
[=!
J'r, I e f1
* ?- ~ ~ , 8 5
) I n +E!
i
', # / '// 5' ij ,,,, , J ji's , ,
1!
11
~
*< \ :!
?
gl i ')
g .
k
//
/ [g 5
7 / r li=
s , il 3 ,,. ,e E.
b l 0 5
Ii 3 & '
',o // ?I e
i
// , r si i ..,...,...,,...,,.,,r...,_.,r..,,.......,.c...,...,,.,...,,,.,,_,_,,,..,...,..,,,.,,..z..,_..,,
/
5 iii!!!!!l!l!Iii!Iii!l!l!!!!3 5 !!
I
4 _ __ ... _ .2 _ .. ... -
e e I
4 I a i I
I a Ii I f I
f e a t 1 M \
~f l -
l-
=
* ? ee e E y k' 4 =
-,e -
s -
!!f!
. .~,,
)
l- llll
' t aa3- -l
~
a 1!11 .-
- -r -
O.
E 3 -
r----
.1 5 ? - e l
.i
}l-e l l _g i-u l
e P l J j { { l' _
~
3 s 8 -
9 t $ 3 8
, z_ r a i
*l- l
-l s.
2 l
I i
g
)-
> l a 8 .
0 l~ 's, .
m - -------.___. . ..J 3-. .
i _
-I I .
e -1, . .
E *
~
h' l'
,x f';
.e, x , a, ,s, , ..
s ,
i i i I i i i 4
(
i !!!!!!!!!Illisiittisiinti!!i I. ~' ' ' ' ' ' '~' '~~'~~'~'~~' ' ' ' ' '.~' '- ~' '~' '~+~+'~.. i~i .i~! !' I -
% b" li .:
-~,. il n.i -
is ni RR R s in i 1111 / ., F
!i , !!$$ / $ \ II g;:
-an*
s 5 ,
\ ((
1111 S1 :
14
- aat a till *r ,
il.
i j .#
, sj '
y
- g
- g]
# i-
< R: 1 i 314 s / I~ LI 23 ,
e- i !
' # L ijg.
e N 3];'
.- o
!!) J s s (' 7 ,
[!:
ii Fs l< F1
/s I r
f J ,~
i
(
s!i F!2
)T s
11
>,.g .
/ i.
#'t, \ ?
P!
1 ':
ar g ___
r h+_
I i ~ )) i i i !! s, ?
[
Ij \ EI M'
ll [Dj.-
I:
s ll
'i
=.,g-1 ;,,1
//
giir.;,i,,y,.,
/
1 gi..i....,.. rig,,,,3.,.,,,,,g.,,,l 6'l - l 4 l l' l'l l l l' 4 l lir I. I. i. !. !. !. !. I. I. I i ! I I'I i i !'!'!'i'i i'i'i !'!'8 8 ! I 1
4
.]
i t
4 i .
O i
i i
I, . I. . . I. . . . I. . . . . I. .
I,
- i- a tu +--!
E p ~R t
a
} '
%, s
./
~
? _
,,, s .
~ "
, / ~, ..
l113 l e i l- tta5 -l j
1111 .-
* * ~
a . .
a a 3 e 3 .
S l I__________l
'g j g~ ! l
_ / t
~
![- ! n !i f l -j j- .-
1 i
8
,1i A i g
O . I e .~
3-a h
e I
l
! - }r '
!, i.
s
$ i i
E I .I 8 r I
=
2 i 1-E. i
' '\_i 1f "S I i \ V l . '
s i
}. t
' l .
i t l
.i . .
g -
4 3 g. _____ _ _ _ _ _ _ _ _ _ _ _ . . _ _
o -
5e I "g
*U ~ & .
f t
~
. <e, .
's,
'~
8-
*r, -l '
j . .
1 % 'to kr % y y
#'s , . . . ,... . . . . .'N .
I !! I I i i 4
! l 1
3_
g f 12 'I.. ..Aa 1..s .nea igei ,,,, ,,1, , , ,
?
~,.. Fl
~J
! /
b!
(( 3 lj li /: s
'N [i t
i a I!
~i 11 ./ ,t
$) r
' I4 ja gl /$ $
4
, - ( i ti r!i se -
i ! ,
) \
i r!
e n; -
# o fb r
{pk s ] i e I
- /, f .
i s i
/ ig
@l'
" g zI c14 , , , :
aa -, a g$ ! ! 3 E b"3 "gj ( s uaj *
, / 1 3
i
~
' fu .
'j 4, l
/ M, !',:
, ,l .
,4 v ,, / ,
ir i
-., ,,,,,i. ,, ,,,. , , , , ,,,
/. , , , , , , , , , , , , , , , , , , , , , , , , ,
- - - - , , - --.ger~ --,
l l
e o e
'I e
. . . i . . . . I. . I. . . I. . .
I, . . . I, h, .
n, ,
i.
o s t
g-....
m %s 3-5
- 1_, a i l _l g- t* i i I O -
i v
i l
i .=
ie 3 8 i 3 i l I -
8 3
- t. f 5 $ 8
)
, }
~l- r
-1 i s.
2 i
i w l e
~t l ' -
' s, ,
L........ .. _ .....a -\,
=. .
~ ~
- k, ,,,
. g
. a .
E . .
r,
's, K
'*t
.\ "to %, B ,o, %, .
\, \ ,\ . N
,\ . .
I i i i i i t
i i
y - ...
i ,......!,...!
. _ ,I
. . . .l. . .i.....s tilli
...................,..,.... stil!i!!i.,!!
i.....n.....i
................z..,,...,..................,....,_,.
1 .,
li N :-
T N F!
i lill #
,i en I
--e.
3 j
v:t y s ri j
c ,.
- llj o .
7 M y
l~
r
!l'
!!! J# re ,?
il:
g,
,4 ,/
m)ifM
! ,1 ll 'djs<
i
/
i l;l
..............,.............................,,....,..,,,._........,,,...,,7.... .,
d 9
a w
.se
- g. .. . . . - . - - - ,.
9 O
e e
I i
g I .c 1 .! t N. g fI\,\,,,1 t
li' [
i if/ /
x E is f
s-
- \
i
,h s
I i i ne b
1 A
j 1f 3 3 ~
/, j I ilti y l
~ [
;] . t 1
i s 3
a r ___ t
/ i \ '
e 1 \. e 1 \
1 '-
a i ,
5 1* 1 S- I i 2 '
- I S i Y i
y 4 1 I E - '$
.3 3 i
-t 'i 1 i i i i i l 4'
#{ i s i s
s - ~~~ ~ ,
I, , ___.
; . t h I. i N.
1 i.
. . '*r 1 %
S
*< a,,
q
]
. j g 1 7
e '"o}}