ML17258A668
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| ML17258A668 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/25/1982 |
| From: | Caplan R Sierra Club |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8203300163 | |
| Download: ML17258A668 (6) | |
Similar Documents at Ginna | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999
[Table view]Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated IR 05000244/19990081999-10-14014 October 1999 Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs IR 05000244/19992011999-09-24024 September 1999 Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30 Category:INCOMING CORRESPONDENCE MONTHYEARML17250B3041999-10-20020 October 1999
[Table view]Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30 Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC MONTHYEARML20198M9631985-06-17017 June 1985
[Table view]Forwards Allegations of Safety Violations of Nuclear Regulatory Law or Westinghouse QA Requirements.Investigation Requested.Related Info Encl ML20127D6551985-03-15015 March 1985 FOIA Request for Repts WASH-1520,WASH-740,1964 Update of WASH-1250 & US-AEC-IDO-19-302 Plus All Records Re 610103 Accident at SL-1 Reactor in Idaho & 1982 Incident at Facility Involving Tube Leaking ML20114A8031984-07-10010 July 1984 FOIA Request for All Correspondence of 1982-83 Between Util & NRC Re Shipment Routes for Irradiated Fuel Between Former Reprocessing Plant at West Valley & Facilities ML20101D4431984-06-0808 June 1984 FOIA Request for 1984 Correspondence Between Rochester Gas & Electric Corp & NRC Re Routes,Dates & Cask Types for Shipments of Irradiated Fuel Between West Valley & Ginna Nuclear Power Plant ML20080E8281984-02-0202 February 1984 Requests Copy of Rules & Rights for Intervenors in Upcoming full-term License Hearings ML17255A7331984-01-26026 January 1984 Charges NRC W/Harassment & Intimidation Re Licensing Requalification Exam.Author Livelihood Jeopardized by Unlawful Examiner Actions.Forced Exam Unconstitutional Under Fourth Amend, Unlawful Search & Seizure. ML20080C2091983-11-29029 November 1983 FOIA Request for Correspondence Between Nrc,Jcp&L & Rochester Gas & Electric Re Shipment of Irradiated Fuel from West Valley,Ny & Correspondence on Route Applications Between Listed Labs & Savannah River Plant ML17256A6311983-02-28028 February 1983 Requests Info Re Override Capability & Problems Encountered When Manual Isolation Bypassed,Per Press Release 83-17 ML20065B3071982-10-10010 October 1982 FOIA Request for Rept, Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125, NUREG-0909 & NUREG-0916 ML20027A8811982-09-0101 September 1982 FOIA Request for Four Categories of Info & Questions Re 820125 Steam Generator Leak at Facility ML17256B0891982-05-22022 May 1982 Opposes Facility Restart Until Exact Cause of 820125 Rupture Eliminated,Workable Emergency Sys & Evacuation Plan Developed,Safe Radwaste Disposal Sys Implemented & Independent Monitoring Sys Established ML20052A2621982-03-29029 March 1982 FOIA Request for Identification of Persons Contacted Re 820125 Incident at Facility,Info Concerning NRC Investigation of Drug or Alcohol Use by Plant Personnel & If Medical Investigation ML17258A6681982-03-25025 March 1982 Corrects Page 3 to 820311 Petition for Order to Show Cause ML17309A2361982-03-11011 March 1982 Forwards Petition for Order to Show Cause Why Facility OL Should Not Be Suspended or Why Permission to Restart Reactor Should Not Be Withheld Until Actions Have Been Taken to Assure Protection of Public Safety ML17258A6111982-03-0202 March 1982 Requests Notification of Meetings Held Re 820125 Facility Accident.Minutes & Records Also Requested ML20054C8701982-03-0101 March 1982 FOIA Request for Summary of NRC 820301 Meeting W/Rochester Gas & Electric Corp ML20052F0861982-02-0909 February 1982 FOIA Request for Draft Rept Re 820125 Incident at Facility ML20052D3731982-02-0505 February 1982 FOIA Request for Info Re Jan 1982 Incident at Facility ML17258A3161981-11-12012 November 1981 Requests That TB Cochran Be Removed from Distribution List for Facility ML19290C8311979-12-17017 December 1979 Request Notice of Any Developments Re Use of Mixed Oxide Fuel in Lwrs.Forwards Inside NRC 791203 Article Re Possible Use of Mixed Oxide Fuel at Facility ML17249A4661979-12-0606 December 1979 Requests Facility Not Reopen Until All Findings Available on TMI-2 ML19208B7441979-08-22022 August 1979 FOIA Request for Repts,Documents & Correspondence Re 1973-74 Incident Involving Workers Allegedly Overexposed to Radiation at Facility ML19208B7301979-08-20020 August 1979 FOIA Request for Rept Re 1974 Worker Radiation Overexposure at Facility ML17249A4801979-04-0404 April 1979 Requests Facility Be Closed Until Review of Documentation Assuring Quality & Reliability of Electrical Connectors in Facility Reactor Safety Sys & Review of TMI Accident to Determine Reactor Safety Sys Adequacy ML17244A4561979-04-0202 April 1979 Urges NRC to Keep Ginna Nuclear Plant Closed Until Safety of Plant Sys Can Be Assured.States Nuclear Energy Is a Threat to Human Safety ML17249A4621979-04-0101 April 1979 Requests Facility Not Reopen Until Thorough Review Conducted on TMI-2 Accident ML17249A4631979-04-0101 April 1979 Requests Facility Not Reopen Until Safety Sys Checked ML20084H0451975-02-10010 February 1975 Responds to Describing Criteria for Enforcement Action & Radiation Monitoring Programs.Displeasure W/Info & Lack of Info in Ltr Expressed ML20084H0551974-07-27027 July 1974 Discusses Personnel Overexposures to Radiation at Facility. Review & Standardization of Facilities Instructions for Preventing Overexposures Recommended ML20235D4461971-06-0303 June 1971 Comments on Idaho Nuclear Safety Repts on Tests 845 - 850 of Semiscale Blowdown & Emergency Core Cooling Project. Concerns Over LOCA & Public Safety Raised.Aec Should Suspend Listed Licenses 1985-06-17 |
Text
'REGULATORY I RMATION DISTRIBUTION SYS (RIDS)ACCESSION NBR;8203300163 DOC~DATE!82/(03/?5 NOTARIZED:
.NO, DOCKEt FAC IL>>50~244 Robert Erpme t 0 anna Nuc l ear P 1 ant P Uni<t 1 E Rochester G 05000244 AUTH.NAME AUTHOR (AFFILIATION CAPLANE R~N.'Si er r a Cl ub R E<C I P, NAME RECIPIENT AFFII.'IATION
~DENTONE H~Of f ice of Nuclear Reactor'Regul ationE Director~<"SUBJECT!'Cor'rects Page 3 tto 8203 1 1'petition f or'rder to shoe cause~DISTR)BUTIOE CODE;YESES.(COPIES'RECEIVED:LTR, r',:E<<CL
~SIIE:," TITLE: Request-for NRR Action (e.'g~2.206'Peti t7ons)8 Related TCor r espondenc NOTES: 1-'opy: SEP'Sect.Ldr.05000244 RECIPIENT I D CODE/NAME.ORB¹5 BC LYONSE J~Oi INTERNAL~EDO/ACB ELD/RED NR R/P PA'8 SCOP IES L'TTR ENCL REC IPIENT ID"CODE/NAME ORB'5 L(A ELO NRR, DIR 04"COPIES LT'TR ENCL EXTERNAL: LPDR NSIC 03 (05 NRC'<P DR NTIS 02 (Q.TOTAL<<V<<DER OP COPIES REQUIRED: UTTR P5"E<(<<CL A 1 kt tII~l tffg Il Itk II A n AWA A+~/j lkl I I I J r jj jj)Itkt lj I ERRA.=~CLUB SI C 4<iisg MAR88 19'~.,-"%It egg".,".~jj
..'e: Docket No.5~244 Harold Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
Dear Mr.Denton:
530 Bush Street San Francisco, California 94108 (415)981-8634 Please reply Co: 278 Washington Blv Oswego, New York March 25, 1982 p>p The Sierra Club wishes to correct an inadvertent omission from its Petition for Order Co Show Cause, which was submitted Co your'ffice on March ll, 1982.Page 3 of Che Petition should be corrected to include 2.b.and should read as follows: 2.The adequacy of the steam generator Cube testing program should be evaluated and a determination made regarding the following issues: a.Is the routine multi-frequency eddy current testing method being employed at Ginna the best available given current state-of-Che-art?
If not, what Justification is there for not employing Che best available technology, in light of chronic Cube degredation problems at Ginna and at other PWR's and Che existence of techniques such as fiber optic examination?
b.Is Che frequency of required testing of tubes sufficient to prevent future tube rupture or other serious break'?c.Does Che current testing program, which only tests a sample of Cubes and which does not test their full length, provide sufficient information Co prevent tube failure'?<<ig3 s" 8203300163
.820325.>PDR, ADOCK 05000244,-'PDR',;",',I,'...'.,"..
II~~~II~~Ii V~'I~~'~~
Sierra Club, page 2 Ve are sorry for any inconvenience to your office due to this omission.Very truly yours, Ruth N.Caplan, Chair Sierra Club National Energy Committee 0 4~t'I.t, tt~t t~4~it~', I~I.t~'itta v,,t
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