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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML20209E3711999-07-0202 July 1999 Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML20196G2581999-06-23023 June 1999 Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20196G2211999-06-21021 June 1999 Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML20195J1391999-06-11011 June 1999 Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20206U7441999-05-20020 May 1999 Informs That NRC Unable to Conclude That NAPS Has Met Intent of Supplement 4 to GL 88-20.RAI Re Fire Area of IPEEE Encl. Response Requested within 90 Days of Submittal Date ML20207A8541999-05-20020 May 1999 Forwards RAI Re Licensee Listed Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 90 Days of Submittal Date ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206L4661999-05-10010 May 1999 Forwards SE Accepting Request to Delay Submitting Plant, Unit 1 Class Piping ISI Program for Third Insp Interval Until 010430,to Permit Development of Risk Informed ISI Program for Class 1 Piping 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206H0221999-05-0303 May 1999 Informs That Licensee Changes Bases for TS 3/4.6.1.2, Containment Leakage. Changes Allow Use of Other NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing.Ts Bases Page,Encl ML20206G9481999-05-0303 May 1999 Informs NRC That Insp of 58 Accessible safety-related Pipe Supports Completed in Response to NOV from Insp Rept 50-338/98-05 & 50-339/98-05.Commitments Made Include Plans to Perform Assessment of Welding & Welding Insp ML20205T1181999-04-16016 April 1999 Requests NRC Approval Prior to Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit.Nrc Concurrence with Irradiation Program Requested by End of June 1999 ML20205P1891999-04-0808 April 1999 Forwards ISI Program for Third ten-yr ISI Interval for North Anna Unit 1 for Class 1,2 & 3 Components & Component Support.Third ten-yr Insp Interval for North Anna Unit 1 Begins on 990501.Page 2-26 of Encl Not Included ML20205K3631999-04-0505 April 1999 Requests That Relief Request IWE-3 Be Removed from 980804 Relief Requests Submitted to Nrc.Subject Relief Request Was Inadvertently Retained in Attachment 1 for Unit 1 ML20205K2191999-04-0101 April 1999 Forwards Response to NRC 990106 RAI Re Util Summary Rept on USI A-46 Program,Submitted 970527.Calculations & Corrected Table 11.1-1,encl ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML20205E2701999-02-25025 February 1999 Forwards Rept on Status of Decommissioning Funding for North Anna Power Station,Units 1 & 2.Trust Agreement Between Old Dominion & Bankers Trust Co,Effective 990301,attached ML20207A8741999-02-25025 February 1999 Draft Response to NRC Telcon Re Licensee Request for Approval of LBB Evaluation in Support of Elimination of Augmented Insp Program on RCS Loop Bypass Lines.Response Justifies Use of Less than One Gpm Detectable Leakage Rate ML18152B5401999-02-11011 February 1999 Requests Relief from Specific Requirements of Subsection Iwl of 1992 Edition with 1992 Addenda of ASME Section Xi,Per 10CFR50.55a(a)(3) ML20203C8181999-02-0505 February 1999 Forwards Response to NRC 981217 Telcon RAI Re risk-basis of Nitrogen Accumulator Action Statement to Complete NRC Review of 951025 Proposed TS Changes 1999-09-27
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20238B7731987-08-0707 August 1987 FOIA Request for Records Explaining Status of Listed LERs Omitted from List,Previously Received from Nrc,Of LERs Filed by Commercial Nuclear Power Plant Licensees for Operating Year 1986 ML20237J1741987-07-18018 July 1987 FOIA Request for Documents Re Ruptured Stainless Steel Tube That Shut Down Plant Pending Investigation,Decisions Made, Insp Findings & Info Re Rupture Before Insp ML20134L4791985-07-17017 July 1985 FOIA Request for Biographical Data on Region III Resident Inspector,H Livermore & SALPs for Listed Plants for Specified Time Frames ML20063C5061982-06-23023 June 1982 FOIA Request for Four Categories of Records Pertaining to Rulemaking for Fire Protection & Fires in Operating Nuclear Power Plants ML20049A6061981-06-0505 June 1981 Informs That North Anna Environ Coalition Address Has Changed ML19347D2061981-03-0505 March 1981 Requests Explanation of Sentence on Blade Failure in Aslab 810223 Memorandum & Order ML20003B9181981-02-11011 February 1981 Requests Info Re Spent Fuel Storage at Facility & Air & Water Radiation in Vicinity of Facility ML20008D9581980-07-24024 July 1980 Requests Info Re Operation of Facility,Comparison to Other Nuclear Power Plants & Radiation Reading Around Farm ML18139A4831980-07-15015 July 1980 Advises That Effective 800801,address for Coalition Will Be: 1105-C Olive St,Greensboro,Nc 27401.Related Correspondence ML19309H2231980-04-18018 April 1980 Requests Basis for Selecting Essex Corp as Consultant.Also Requests Info Re Crystal River Syndrome.Public Entitled to Better Performance Considering High Cost of NRC Bureaucrats ML18139A0801980-02-28028 February 1980 Discusses Westinghouse Steam Generator Corrosion Problems & Westinghouse Turbine Disc Cracks at Facilities.Forwards NRC 800121 Ltr Re Insp Port Installation at North Anna Units 1 & 2 & Environ Coalition 800107 News Release ML19309B2891980-02-28028 February 1980 Requests Immediate,Thorough & Intensive Investigation of Util Operation Re Rate Control.Documentation of Homeowner Kw Usage & Charges Encl ML18139A4051980-02-18018 February 1980 Requests Action Concerning Defective Demineralizer Design, Related Corrosion & Cracking in Steam Generators & Turbine Discs.Commends NRC Decision to Require EIS Re Experimental Replacement of Steam Generators ML19290E0561980-02-0606 February 1980 Urges NRC to Authorize Util to Operate Facilities.Safe Nuclear Facilities Are Sitting Idle While Expensive Oil Is Burned to Generate Electricity.Energy Costs Are Rising. Notice from Util Encl.W/O Encl ML19262C1321980-01-0808 January 1980 Urges NRC to Consider Early Licensing of Facility.Further Delay Will Impose Addl Costs on Ratepayers ML19290C2011979-12-11011 December 1979 Submits Suggestion in Response to Aslab 791108 Request to VEPCO Re Use of Outdated Amplified Response Spectrum Curves. Housner Response Spectra Was Questionable Per Encl S&W 690820 Conference Notes Entered Into Record on Mar 1974 ML19257B8661979-12-0303 December 1979 Forwards 791119 Resolution Requesting Reconsideration of Licensing Moratorium of Nuclear Power Plants.Licensing Would Be Major Step Towards Energy self-sufficiency ML19211A6791979-11-29029 November 1979 Requests Continued Moratorium on All Nuclear Plants Until Compliance Is Made W/All Existing Safety Stds ML19305D2101979-11-29029 November 1979 Expresses Concern Re VA Governor,Atty Gen & Corp Commission Actions for Licensing of Facility.Govt Officials Favoring Util Interests Over Welfare of Citizens.Ltr Dtd 791128 to Goochland Gazette Encl ML19290C5781979-11-28028 November 1979 Notifies NRC That Citizens for Environ Values Supports Moratorium on Licensing of Nuclear Power Plants & on North Anna 2 in Particular,Until New Rules Insuring Safety Can Be Written ML19211A6671979-11-13013 November 1979 Requests Reconsideration of Moratorium on Licensing of Plant Due to Economic Impact of Delay & Oil Shortage ML19209C2841979-08-14014 August 1979 FOIA Request for Documents Re Abnormal Settlements at Facilities & Info Concerning NRC Reasons for Not Levying Civil Penalty Against Util in 1972 ML19208D7901979-07-29029 July 1979 Requests Opportunity to Make Limited Appearance at Charlottesville,Va Hearing Re Spent Fuel Pool ML19249D4431979-07-22022 July 1979 Request Opportunity to Make Limited Appearance at NRC Committee Review of VEPCO Spent Fuel Compaction Request ML19246C1481979-06-15015 June 1979 Requests to Make Limited Appearance Statement at Licensing Prehearing ML19289G1831979-06-11011 June 1979 Requests to Make Limited Appearance Statement at Licensing Prehearing ML19246C1331979-06-11011 June 1979 Comments on Proposed Storage of Spent Fuel & Sinking of Pump House.Concerned About Safety ML19241C2621979-06-11011 June 1979 Requests to Make Limited Appearance Statement at Licensing Prehearing ML19225B3771979-06-11011 June 1979 Requests to Make Limited Appearance Statement at Licensing Prehearing ML19247A8281979-06-11011 June 1979 Requests to Make Limited Appearance Statement at Licensing Prehearing ML19246C1401979-06-0909 June 1979 Requests to Make Limited Appearance Statement at Licensing Prehearing ML19225C0081979-06-0909 June 1979 Requests to Make Limited Appearance Statement at Licensing Prehearing ML19248D0621979-06-0808 June 1979 Requests to Make Limited Appearance Statement ML19241C1461979-06-0707 June 1979 Requests to Make Limited Appearance Statement at Licensing Prehearing ML19276E7601979-02-19019 February 1979 Urges ASLB Not to Increase Allowable Settlement,Hold Public Hearing Re Settlement Conditions & Investigate Revocation of License for Withholding Info ML19276E7561979-02-16016 February 1979 Expresses Concern Re Plant Const on Fault Line & Soil Conditions Which Permit Uneven Settling of Plant Equipment. Urges Aslab Refuse to Increase Allowable Settlement.Requests a Public Hearing Be Held ML19276E7581979-02-12012 February 1979 Urges Consideration of License Revocation & Initiation of Public Hearings Re Risky Settlement Conditions at Plants. Asks for Exploration of Unresolved Safety Questions to Clarify NRC & Util Roles in Alleged cover-up of Info ML19276E7541979-02-11011 February 1979 Urges Aslab to Refuse to Increase Util'S Allowable Settlement.Believes Public Hearing Should Be Held.Feels License Should Be Revoked ML19282C3031979-02-0909 February 1979 Requests Public Hearings on Settlement Conditions at Plant. Urges Aslab Consider Revocation of Plant Operating License for Withholding Hazardous Info.Util Cannot Be Trusted to Think or Act in Public Interest ML19282C2921979-02-0808 February 1979 Requests Hearing Re Facility'S Allowable Settlement & Util'S Withholding of Hazardous Settlement Info from ASLB ML19282C2981979-02-0707 February 1979 Requests Aslab Refuse to Increase Facility'S Allowable Settlement,Hold Public Hearings on Dangerous Settlement Conditions & Consider Suspension or Revocation of Operating License for Withholding Info from Aslab ML19282C3061979-02-0707 February 1979 Requests Util'S Foundation Settlement Allowance Not Be Increased W/O Public Hearing of Evidence.States Util Has Withheld Essential Info & Revocation of License Should Be Considered ML19276E7511979-02-0707 February 1979 Urges Aslab Not to Increase Foundation Settlement Allowance W/O Public Hearing.Suggests Possible Revocation of License in Order to Gain Cooperation ML19282C2941979-02-0505 February 1979 Requests Allowable Settlement Not Be Increased.Requests Hearings Be Held Re Util'S Withholding Hazardous Settlement Info from Aslb.Aslb Should Consider License Revocation ML19284A4271979-02-0505 February 1979 Concerned About Continued Mishandling of Facility by Util. Urges Public Hearing Re Withholding of Pumphouse Settlement Info ML19284A4331979-02-0505 February 1979 Requests Board Not to Increase Allowable Settlement & to Investigate Revocation of License Because Util Withheld Hazardous Settlement Info from Board ML20064J4481979-02-0404 February 1979 Suggests Revocation of Operating License,Holding Public Hearings & Prohibition of Increased Pumphouse Settlement ML19284A4291979-02-0303 February 1979 Urges Board Not to Increase Allowable Settlement & Requests Hearing.Also Urges Investigation of Revocation of Operating License,Since Util Withheld Info Until After License Was Granted ML19284A4281979-02-0303 February 1979 Expresses Apprehension About Settlement of Cooling Water Pumphouse,Which Is Built on a Fault & Unstable Saprolite Soil.Urges Hearing to Prove That Human Lives Are the Most Important Consideration ML19282C2841979-02-0303 February 1979 Expresses Concern About Facility,Especially Seismic Bldg Settlement & Spent Fuel Risks.Questions Facility'S Financial Justification.Requests Public Hearing Be Held 1987-08-07
[Table view] |
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NORTH ANNA ENVIRONMENTAL COALITION C..el ttesville, Virginia Mailing Address: 412 Onons Drive Huntsville, Alabama 35801 January 14, 1979 (205) 536-0678 Re: Settlement Hearing Messrs. Rosenthal, Farrar, & Buck @ q 6
Atomic Safety & Licensing Appeal Board U. S. N2 clear Regulatory Cc= mission 8 4
Washington, D. C. 20555 NRC PUBLIC DOCUMENT ISI g
@oc 2 Il in the Matter of Virginia Electric and Power Company b g22 $7.37 ~
(North Anna Power Station, Units 1 and 2)
, g gN '
Docket Nos. 50-338 and 50-339 OL q Vf.sa 8 s .
4
Once again the Coalition would cc= mend the Appeal 3 card for re-taining jurisdiction over the vexed issue of settlement at North Anna.
In the brief period of just over one year, three sets of Techni-cal Specifications on North Anna's abnormal and differential settle-ment have been issued by the KRC Staff in conjunction with VEPCO.
Two sets of these Technical Specifications are now admitted to contain significant errors. The third set -- issued just 18 days af ter the second - contains several changes and additions of a highb ques-tionable naturo. ( Example: the unexplained abandonment of the measurement of average pumphcuse settlement, that measurema2 t whose limit was rapidly being reached. )
Both the format and the content of the December 22, 1978 and January 9,1979 settlement docu=ents reflect the internal ca nfusien of the KRC Staff, pessibly combined with intent to confuses
--They fail to juxtapose old and new Tech Spec figures.
-They fail to point out significant changes in " base dates."
--They fail to mark textual changes, both cmissions and t he inclusion of new material,, or to explain them.
-They fail to address causes of " unanticipated" settle::mt.
But most significantly,
~They fail to provide settlement measure =ents as of December 1978 and to relate those current measurs:e nts, total, average, and differential, to the new limits propcs ed.
We are arre that if the Appeal Board has done the line by line co= pari-son and analysis these disordered documents require, it is well aware of the foregoing deficiencies.
The Appeal Board must also be tware of, and addressing, the contin-uing question of integrity surrounding the settlement matter: is YEPCO guilty of additional " material false statements" for failure to report major settlement in Au6ust of 1977 under require =ents of 10 CFR 50.55(e}7 That are the results of the Inspection and Enforcement investigation into "Destrcyed and Reset Survey Points" which prevented proper t.,ettlement measure::ent of Class I stmetures? 79029oM\
h
' ~
~.
In its letter of January 3 to the Appeal Board, the Coalition requested the Appeal Board to take no action pending the receipt cf certain infor=ation.
In this letter of January 14, the Coalition asks the Appeal Board to hold a public hearing on the "unreviewed safety question" of abnormal and differential settle =ent at the North Anna si te, and to acquire its necessary information from the cross-examination of expert witnesses under oath. NAEC would hope the Appeal Board would call the following:
Dr. Paul Rizzo, ACRS consultant Dr. Antonio Segovia, University of Maryland Dr. Milan Pavich, USGS (saprolite studies)
Dr. J. Paul Mulilis, U.S. Army Engineers Te suggest the foregoing na=es as a mini =um, and also urge t hat :he Appeal Board call Dr. Lyman Heller and his staff to explain their choice of limits and changes in limits on the record. VEPCO's geo-technical people shculd also be questioned en their contradictory state =ents and predictions regarding the effect of horizontal drains upcn additional settle =ent.
The Coalition believes that the erratic settlement record, the approaching settle =ent limit (as of August 1978 per Mr. DeYoung),
and the recent unncrving performance by the NRC Staff are in the=~
selves adequate and eloquent arg=:ents for a hearing by the Appeal Board. Additionally, we would re=ird the Appeai 30ard that former NEC Project Manager, Robert Ferguson, earlier recc== ended a Shcw cause hearing on settle =ent, and later described staff concern as to whether "this settle =ent would preclude the issuance of an operat-ing license."
Such a hearing might help to dispel the public i=pression that no =atter the cost, EC's elastic regulations and VZFCO's flexible pipes will rescue a defective reactor foundation.
The nuclear industry frequently tells the public how tightly and meticulously regulated they are by the NRC, but the original North Anna Technical Specifications allowed =ain steam valve houses to settle .45 and .31 feet respectively when the safe and correct a=ount we are now told is .045 and .031, an error by a factor of 10, written by VEPCO and approved by the NRC Staff.
In the second edition of the Technical Specificaticna, issued on Dece=ber 22, 1978, the NRC Staff argued at the bottem of page 5 under "ltem to change 1" that average excesgg/I, rom .15 feet .33 pu=phouse toefeet jjg could result if M 0's request were granted.
Thus it " modified" VEPCO's request to .22 feet.
C,[t?g
~0~
?
It is only inspection of Table 3.7-5 (Revision 1) which re-veals this to be an EC modification without a_ difference because the " base date" has been changed frcm December 1975 to July 1977:
VEPCO has asked to be allowed total a etticnent of 8.52".
- EC'S modification grants them exactly that:
-using Dr. Rizzo'[ August 1977 total avera6, settlement of 5.88"
-adding EC's modification of 2.64" from July 1977 Allowable total 8.52" ,
Richard Foster, Attorney for Intervenor Arnold, called NRC Attorney Daniel Swanson to inquire if perhaps an error had been made in regard to the allowable total average settlement of the pumphouse...
The third edition of the Technical Specifications, issued on January 9,1979, had quite a dif ferent treatment of " Item 1" on pages 5 and 6. A major section of the first paragraph had been omitted. Mr. Foster's question had a remarkable affect.
The second paragraph omitted any mention of modifying VEPCO's request from .33' to .22' and total average settlement of the pu=p-house was dropped without ceremony or explanation (or mention of its proximity to the current limit of .15 feet). Instead, the EC Staff proceeds to take a new position on differential settlement.
EC's December 22 second edition of the Technical Specifications stated on page 6 that
" .. differential settlement. ..should not exceed the design basis of 0.25 feet for the expansion joints." (date not mentioned)
NRC's January 9 third edition of the Technical Specifications stated on page 6 that
" .. differential settlement...should not exceed the revised proposed Technical Specification limit of 0.22 feet after July,1977..."
No explanation is given for the change in the third edition, just as in the second edition no explanation is given for the change in base date to August 1978 on Table 3.7-5 (Revision 1), a fact which makes a material difference in measurement but is not alluded to in the text. To be allowed .25 feet from August 1978 provides a considerable =argin over
.25 feet from January 1976 and is inaccurately represented by the state-ment, "The technical specification of 0.25 feet for the expansion joints remains the same."
Is the NRC Staff itself confused, or is it attempting to deceive?
Either situation puts the public at discomfiting rit.k.
~
4 .
" Item 3," starting on page 7 in both the second and third edi-tions, is a very disturbing paragraph regarding " uncertainties and gaps La settlement measurement data for the buried pipes..."
It appears that pipe-stress limits cculd be reached if the dike settles another 2.4 to 3.6 inches from the last reported measure =ent of August 3,1978 (not given). Given the " uncertainties and gaps" in data, it is impossible to understand how NRC arrived at the same number it had originally chosen as allowable additional average settlement for the pumphouse from July of 1977: .22' or 2.64" as the current limit for the buried pipes. Here, however, the new reference date is August 1978, with any reference to July 1977 having been dropped from this entry on Table 3.7-5 (Revision 1). (Shouldn't that be Revision 27)
" Item 5," starting on page 9 in both the second and third edi-tions, deals with cracking of the pumchouse structure. In the 18 days between the two editions, the.NRC Staff appears to have become con-siderably more concerned about this cracking prospect, doubling the text of that paragraph, adding some lines about the "Dat-of-Plane Distortion" limit not previously mentioned despito its inclusion in Table 3.7-5 (Revision 1).
Both editions are full of optimism about untested auxiliary service water pumps. Given the questionable conditions at the site, it would seem a mini =um action on the part of the NRC Staff to rescind the re-lief from testing granted TEJC0 in 1977, and, in the light of the new situation, require the pumps to be tested regularly.
The NRC Staff concedes that certain maximum allowable limits are possibly within reach and "cannot be increased without modifications if any pumphouse settlement occurs beyond the limits herein specified."
3ecause of that admittedly narrower margin, the Coalition believes that the Appeal Board should require reporting when 50% of the current limit is reached as ~ opposed to 75% now in effect. 75% and a 60-day report make an erroneous assumption about the predictably gradual rate of set-tlement which actual experience of 1975-75 and 1977 does not support.
NAID has no time for necessary further analysis. We do, however, ask that the Appeal Board honor and explore those questions raised before it by the Coalition from May 1978 on plus those to the ACRS and Staff which were also submitted to the Appeal Board. We are sure that the Appeal Board has serious questions of its own arising from the troubling differences in the three editions of Technical Specifications, questions which may parallel and go beyond those raised by NAEC in this letter.
We close by asking once again that the Appeal Board hold a public hearing on North Anna's abnormal and differential settlement and the significant hazards considerations which it represents.
Sincerely, e Allen (Jrs. P. M.)
. resident, NAEC cc: Dr. Paul Rizzo Dr. Antonio Segovia, Messrs. Poster, Maupin, & Swanson, Esq.
NORTH ANNA ENVIRONMENTAL COALITION
' Charlottesville, Virginia Mailing Address: 412 Owns Drive January 14, 1979 Huntsville, Alabassa 35801 (205) 536-0678 Re: Settlement Hearing Messrs. Rosenthal, ?arrar, & Buct
- g @t / 4 Atc=ic Safety & Licensing Appeal 3 card s U. S. Nuclear Regulatory Cc==issien .m 7ashington, D. C. 20555 2C PUBLIC DXL"E"- ' ,/8 MP: (
) I In the Matter of Virginia Electric and Power Cc=pany b# 332.2Ig7'37 3 (North Anna Power Staticn, Units 1 and 2) , ,, ., ,. 5%
Decket Nos. 50 338 and 50-339 OL u %i.= 8
/s W Gentle =en: 4 .*
Once again the Coalition wculd ec==end the appeal 3 card fer re-taining jurisdiction over the vexed issue of settle =ent at North Anna.
In the brief period of just over one year, three sets of Techni-cal Specifications on North Anna's abucr=al and differential settle-
=ent have been issued by the 3RC Staff in conjunction with VEPCO.
No sets of these Technical Specifications are now ad=itted to contain significant errors. The third set - issued just 18 days af ter the second - contains several changes and additiens of a high17 ques-tionable nature. ( Exa=ple the unexplained abanden=ent of the
=easure=ent of average pu=pheuse settle =ent, that =easure=m t whose li=it was rapidly being reached. )
Both the for=at and the content of the Dece=ber 22, 1978 and January 9,1979 settle =ent docu=ents reflect the internal c: nfasien of the KEC Staff, pcssibly co=bined with intent to confase:
--They fail to juxtapcse old and new Tech Spec ficares.
-They fail to point cut significant changes in " base dates."
--They fail to mark textual changes, bcth c=issions and t he inclus icn of new =aterial, or to explain the=.
-They fail to address causes of " unanticipated" settle =mt.
3ct = cat significantly,
-They fail to provide settle =ent =easurements as of Dece=ber 1978 and to relate these current =easurere nts, total, average, and differential, to the Lew li=its propcs ed.
Te are sure that if the Appeal Scard has done the line by line ec= pari-son and analysis these disordered dccu=ents require, it is well aware of the foregoing deficiencies.
The Appeal 3 card =ust also be aware of, and addressing, the centin-uing question of integricy surrounding the settle =ent =atter: is 7IPCO gailty of additional "=aterial false stace=ents" for failure to report major settle =ent in Augast of 1977 under require =en ts o f 10 CFR 50.55(e }7 That are the results of the Inspection and 2nforce ent investigation into "Destrcyed and Reset Survt y Points" which prevented proper settle = cut
=easurement of Class I structures 7 7901290am
s In its letter of January 3 to the Appeal 3 card, the Coalition requested the Appeal Soard to take no action pending the receipt cf certain information.
In this letter of January 14, the Coalition asks the Appeal Board to hold a nublic hearing on the "unreviewed safety question" of abnormal and differential settle =ent at the North Anna si te, and to acquire its necessary information from the cross-exami.1ation of expert witnesses under oath. NAEC wculd hope the Appeal 3 card would call the following:
Dr. Paul Rizzo, ACES cenaultant Dr. Antonio Segovia, University of Maryland Dr. Milan Pavich, USC8 (saprolite studies)
Dr. J. Paul Mulilis, U.S. Army Engineers Te suggest the foregoing na=es aa a mini ==m, and also urge t hat the appeal 3 card call Dr. Ly=an Heller and his staff to explain their choice of limita and changes in limits on the record. YEPCO's gec-technical people should also be questioned on their contradictory statements and predictions regarding the effect of horizontal drains upon additional settlement.
The Coalition believes that the erratic settle =ent record, the approaching settlement limit (as of August 1978 per Mr. DeYoung),
and the recent unnerving performance by the 3RC Staff are in the=-
selves adequate and eloquent arg==ents for a hearing by the Appeal Board. Additionally, we would re.nind the Appeal 3oard that former NEC Project Manager, Robert Ferguson, earlier recc== ended a Shcw Cause hearing on settlement, and later described staff concern as to whether "this settle =ent wculd preclude the issuance of an operat-ing license."
Such a hearing might help to dispel the public impression that no matter the cost, REC's elastic regulations and 72PCO's flexible pipes will rescue a defective reactor foundation.
The nuclear industry frequently tells the public how tightly and =eticulously regulated they are by the NEC, but the original North Anna Technical Specifications allowed =ain steam valve houses to settle .45 and .31 feet respectively when the safe and correct a= cunt we are now told is .015 and .031, an error by a factor of 10, written by 7EPCO and approved by the 3RC Staff.
In the second odition of the Technical Specificaticna, issued on December 22, 1978, the NEC Staff argued at the bottes of page 5 e
under "; tan 1" that exceg?g could result if 72PCO's request to chat.gs average pt=phouse/ rem .15 feet to .33 feet were granted.
Thus it "=cdified" YZPCO's request to .22 feet.
p
' 3 It is only inspection of Table 3.7-5 (Revision 1) which re-veals this to be an EC modification without a_ difference because the " base date" has been changed frem December 1975 to July 1977:
7EPC0 has asked to be allowed total s ettle:ent of 8.52".
EC'S modification grants them exactly that:
-using Dr. Ri:zo'alugust 1977 total average settlement of 5.88"
-adding EC's =odification o f 2.64" from July 1977 Allowable total 8.52" Richard Foster, Attorney fer Intervenor Arnold, called EC Attorney Daniel Swanson to inquire if perhaps an error had been =ade in regard to the allowable total average settlement of the pn=pheuse...
The third edition of the Technical Specifications, issued on January 9,1979, had quite a different treatment of " Item 1" on pages 5 and 6. A major section of the first paragraph had been omitted. Mr. Foster's question had a remarkable effect.
The second para 6raph omitted any mention of = edifying YIPCO's request frcm .33' to .22' and total average settlement of the pn=p-hcuse was dropped without cere=cny or exclanation (or =ention of its proximity to the current limit of .15 feet). Instead, the EC Staff proceeds to take a new position en differential settlenent.
EC's December 22 second edition of the Technical Specifications stated on page 6 that
" . . differential settlement...should not exceed tb design basis of 0.25 feet for the expansion joints." (da not =entioned)
EC's January 9 third editics of the Technical Specifications stated on page 6 that
.. differential settle =ent...shculd not exceed the revised proposed Technical Specification limit of 0.22 feet after July,1977..."
No explanation is given for the change in the third edition, just as in the second edition no explanation is given for the changs in base date to Anaust 1978 cu Table 3.7-5 (Revision 1), a fact which =akes a material difference in measurement but is not alluded to in the text. To be allowed .25 feet item August 1978 provides a considerable =argin over
.25 feet from January 1976 and is inaccurately represented by the state-
=ent, "The technical specification of 0.25 feet for the expansien joints remains the sa=e."
Is the EC Staff itself confused, or is it atte=pting to deceive 7 Sither situation puts the public at disec=fiting risk.
4
" Item 3," starting on page 7 in both the second and third edi-ticus, is a very disturbing paragraph regarding " uncertainties and gaps in settlement =easurement data for the buried pipes..."
It appears that pipe-stress limits could be reached if the di%e settles another 2.4 to 3.6 inches frcm the last reported =easurement of Aug2st 3,1978 (not given). Given the " uncertainties and gaps" in data, it is impossible to understand how NRC arrived at the sa=e m:=ber it had originally chosen as allowable additional average settle =ent for the pamphouse from July of 1977: .22' or 2.64" as t he current limit for the buried pipes. Here, however, the new reference date is Angust 1978, with any reference to July 1977 having been dropped from this entry en Table 3.7-5 (Revision 1). (Shouldn't that be Revision 2,7)
" Item 5," starting on page 9 in both the secend and third edi-tiens, deals with crackine of the numcheuse structure. In the 18 days between the two editions, the 3RC Staff appears to have become ecn-siderably =cre concerned about this cracking prospect, doubling the text of that paragraph, adding seme lines about the " Cut-of-Plane Distortion" limit not previcualy mentioned despite its inclusien in Table 3.7 5 (Revision 1).
30th editions are fall of optimism about untested auxiliary service water pumps. Given the questionable conditions at the site, it would seem a mini =am action on the part of the 3RC Staff to rescind the re-lief frem testing granted VIPCC in 1977, and, in the light of the new situation, require the pu=ps to be tested regularly.
The 3RC Staff concedes that certain mazi=um allowable limits are possibly within reach and "cannot be increased withcut =cdifications if any pu=phouse settle =ent occurs beyond the linits here in specified."
3ecause of that admittedly narrower margin, the Coalitien believes that the Appeal Board should reauire reporting when 504 of the current limit is reached as opposed to 75% new in effect. 75% and a 6C-day repcrt make an erroneous assu=ption about the predictably gradual rate of set-tlement which actual e.rperience of 1975 75 and 1977 does not suppcrt.
NA:iI: has no ti=e for necessary further analysis. We do, however, as% that the Acceal 3 card honor and explore these questions raised before it by the Coalition from 1[ay 1978 on plus these to the AC33 and Staff which were also submitted to the appeal 3 card. We are sure tnat :he Appeal 3 card has seicus questions of its cwn arising frem the trcubling differences in the three editicus of Technical Specificatiens, questions which =sy parallel and go beyond those raised by NAEC in this letter.
We close by asking cuce again that the Appeal 3 card hold a public hearing on North enna's abnormal and differential settlement and the significant hazards consideratiens which it represents.
Sincerely, 7 ne Allen Mrs. ?. M. )
resident, NAIC cc: Dr. Paul Ris:o Dr. antenio Segevia, Messrs. Poster, Maupin, i Swanscn, Esq.