Similar Documents at Ginna |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999 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
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 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
[Table view] Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20198M9631985-06-17017 June 1985 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
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July 27, 1974
- The' Honorable Dixy Lee Ray j , Ch a'irman The Atomic Energy Commission i Washington, D.C. 20545 ,
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Dear Chairman Ray:
i ,
1 Your attention is called to matters relating to overex-j posures' suffered by workers at the' Indian Point'I and Ginna J
plants. In the Indian Point case, the' corrective' action pro-posed by Consolidated Edison and accepted by the AEC is clearly'
, ; inadequate'in preventing future overex'posures.- In both~ cases,-
l l the AEC's lack of guid'ance in establishing worker control standards is at l' east partly responsible for the' overexposures.-
~
) {
{ Indian Point overexposures:-
l
- d l The Indian Point cases involve eight' individuals'who were i allowed to exceed their quarterly dose limits, over the period
- , November 1972 to December 1973. Two cases involved 18 year j olds who were overexposed before their ages were d.iscovered.
- Uncertainty pervades the remaining over'xposures.- e In each'of
}
the six cases', dose by film badge was, greater than 3 ' rem, but i dose by dosimeter was less than 3'ren.
i ,
j In the' worst case, the' film badge dose'was nearly four i
times that of the~~ corresponding doslmeter value (2290'aren vs.
575 mrem, during September 1973;' reported by letter' from Con Edison to Directorate of R,egulatory Operations - (DRO) on November 23, 1973). The' only mention Con Edison makes' of any efforts to resolve the' film-dosimeter discrepancy appears in the Novem-l ber 23 letter. The company assures DRO that Con Edison is
" accelerating our investigation" of the~ discrepancy. Apparently ,
a the acceleration has not been rapid enough to provide answers at this time.
{
The company's proposed corrective action 'for the dis-l crepancies is to require workers to wear thermoluminescent dosimeters (TLD's) as a measuring
- device. But the' company has not determined the causes of th e film-dosimeter differences.-
Nor has it evaluated relative accuracies of the' two methods i when a difference occurs. The company in fact has provided no i public evidence tha't it is investigating eithe'r problem. To i use the TLD's without answers to these problems is merely to add a third potential discrepancy.
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Question (1) : Con Edison's public files'are silent on its efforts to resolve the film-dosimeter discrep'ancies.- Has the company kept the AEC informed of its efforts.to solve ;
the'se problems? Has the~ABC required the' company ~to adequately l i
inform the AEC of tho' company's efforts?' . -
Ginnaovere$p'osures: f j i Additional problems have occurred at tho' R.E. Ginna plant. :
In a letter to DRO dated March 25, 1974..Roch6 ster Gas and !
l Electric (RGE) reported that 40 men ha'd received film badge e v l
- doses of 3 ren or, greater in a quarter, while the' dosimeter i
doses for the same men were all less than 2500 mrea. In four cases, th6 ' dose by film badge was. greater than 5 rem. ;
RGE felt that the' discrepancies'were'due to improper supervision of workers - all'40imon'were employed by an outside contractor for maintenance'on thi spent fuel pit.. As corrective action, Ginna now requires that any contractor personnel be
, closely supervised by RGE personne1~.- RGE was apparently unaware
! of the Indian Point problems, and' believed tha't worker control would eliminate the Ginna problem. In 1ight of similar occur-i ences at two plants, however, the possibility of a generic
! discrepancy cannot be dismissed.
Question (2): Are tho' Indian Point and Ginna cases iso-lated incidents, or does a, generic film-dosimet'er discrep~ancy
~
exist? If a generic problem does' exist, wha't action ha's tho' AEC initiate'd to solve itf..
Inadequacy of. Con Edison corrective action:
As further corrective action for its overexposures, Con .
Edison has established a limit of 2 :ren, after'which'a worke~r e
is excluded from radiation work'for the'~ remainder of thi~ quar-ter. This limit is supposed to prevent the' worker from receiving a dose by film badge'whi'ch might be greater than 3 rem per quarter.
' ~
However, in four out of the six cas'es involving, greater than 3 rem exposure, thi's limit would not ha've prev'en'ted tho'exces'-
. sive doses.- Consider the' following cases:-
- 1. An overdose during April 1973'was reported by a Con Edison letter to DRO on June 18,. 1973. The' individual received i
1980 area by dosimeter during April'5 and 11. Whe~n his film badges for tho'se' days were developed several days -later', they gave an exposure of 3080 mrea'.-
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- 2. An overdose'during August 1973 was reported by a Con Edison letter to DRO on September 14, 1973. An individual who had no previous exposure for the quarter entered a h.i'gh ' radiation I
area wearing an 0-2000'aren dosimeter. He'left the' area after noticing the dosimeter was off scale. His film- badge who'n developed read 3210 aren.
- 3. An overdose during September 1973 was reported by a Con Edison letter to DRO on November 23,.1973/ An individual's exposure during July and August 1973 was 925 aren by dosimeter and 1420 area by film. His dose by dosimet'er for September was -
575 mrem; when added to the film dose for tho' previous two months, this would have given 1995 mrem total exposure. When the' Sept-ember film badg,e was developed later, it, gave an exposure of 2290 mrem for a total of 3710 mrea.
- 4. An overdose during October 1973'was reported by a Con Edison letter to DRO on December .13, 1973i- The individual's l exposure earlier' in the' month was 10S0 mren by dosimeter' and 1030 mren by film. His next dosimeter reading was 925 aren', for a total of 1975 mrem. When thehfilm badge was developed it read 2700 'arem for a total of 3730 mrem' for the' quarter.
Clearly, in none of these four cases would tho' 2'ren limit have prevented overexposure by film. It is hard to believe that the AEC would have accepted Con Edison's proposed corrective action, had the' agency been completely aware of th'e' inadequacies,-
as it should ha've been~. But th,e'Rugional reply to Con Edison's proposed action was little more th' n aan acknowledgment '(Reg' ion I letter to Con Edison, May 16i 1974)'.
Question (3) : Was the' AEC aware'of this case ~by case inadequacy in the~' company's corrective action? If the' AEC was not aware of the' inadequacy, why~ was it overlooke'd? If the~AEC was aware of the inadequacy, why did it accept the company's action?
Consolidated Edison's program seems more inadequate who'n compared even to RGE's pr, o gram to control radiation exposures.
At Ginna, the following controls were'in effect prior to tho' overexposures:
- 1. RGE personnel were assigned to zero the' dosimeters of contractor personnel.
- 2. Daily dosimeter lists were maintained.
- 3. Men were' restricted from radiation work when tho' dosi-meter dose reache'd 1920 aren.in a quarter. When a 1.3' factor is applied for possible film dose differences,'this,gives 2500 aren adjusted exposure.
- 4. A daily dose list with the 1.3' factor was prepared in order to restrict men below the 2500 arem level. Autho'rization in writing was required for any man to exceed 2500 arem adjusted.
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The Con Edison' corrective action is thu~s less effective than tho' RGE program in effect before the Ginna overexposures.
Since RGE's program was insufficient to prevent overexposure, it is even more puzz' ling that the AEC accepted Con Edison's corrective action without comment.
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Question (4).: . Regulatory Guides ~8.8 and'8.'10,give'no more than, general, guidelines for limiting radiation exposures.- Other than the's'e Guides', does tho' ABC have'any standards or require-ments for nuclear plant programs to control worker exposure?
Necessary ABC action:
It is not unexpected that different nuclear plants ha've different techn~ical specifications, in light' of the present
> non-standardization of plant systems. It is more inexplicable l
that an apparen't ho'.dge-podge of worker control programs exists
- in different plants. The' AEC should review and standardize' each plant's instructions for preventing overexposures'. Such action will result in advancing the' he'alth 'of nuclear workers.
The' Code of Federal Regulations, 10'CFR 20.601,1 provides for civil penalties in the~ case of radiation overexposures.-
The Consolidated Edison overexposures involve recurring inci-dents for over a year. The company ha's taken no discernible action to resolve tho' film-dosimeter discrepancies whi'ch' con-tributed to the incidents. In a show or' callous negligence, ~
the company ha's establishe'd corrective action which if applied to previous cases' would have been insufficient to prevent overexposures.' For these reasons,-it is urged tha~t the' AEC demonstrate its concern for worker safety by invoking th e's e regulations.-
S i n c e r'e l'y ,
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Ralph Nader l
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