ML20107F946
From kanterella
Jump to navigation
Jump to search
| ML20107F946 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 10/27/1984 |
| From: | Drey L AFFILIATION NOT ASSIGNED |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8411070180 | |
| Download: ML20107F946 (1) | |
Similar Documents at Callaway | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K1051999-10-19019 October 1999
[Table view]Ack Receipt of Ltr Dtd 990707,which Transmitted Rev 29 to Callaway Plant Physical Security Plan,Under Provisions of 10CFR50.54(p).Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML20217G2071999-10-14014 October 1999 Forwards Insp Rept 50-483/99-10 on 990913-16.No Violations Noted.Insp Was to Review Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise ML20217B5901999-10-0505 October 1999 Informs That Staff Concludes That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Callaway Plant,Unit 1 ML20217B5711999-10-0505 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & Uec Responses for Callaway NPP Unit 1 ,990224 & 990628.Informs That Staff Reviewed Responses & Concluded That All Requested Info for GL 98-01 Provided ML20212G0221999-09-22022 September 1999 Forwards Insp Rept 50-483/99-11 on 990812-20.No Violations Noted.Team Found,Weakness in flow-accelerated Corrosion Monitoring Program Resulted in No Previous Insp of Pipe Segment Which Failed ML20212D9341999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Callaway Plant.In Area of Ep,C/As Taken in Response to Problems Identified During Previous Exercises Warrant More in-dept Review.Details of Insp Plan Through March 2000 Encl ML20217D5791999-09-15015 September 1999 Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4921999-09-13013 September 1999 Forwards Insp Rept 50-483/99-08 on 990725-0904.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20212B1521999-09-10010 September 1999 Forwards Insp Rept 50-483/99-07 on 990809-13.No Violations Noted.Inspectors Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML20211N0321999-09-0202 September 1999 Forwards SE Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20211B0241999-08-18018 August 1999 Ack Receipt of Ltr Dtd 990714,transmitting Scenario for Licensee Upcoming Biennial Exercise.Based on Review,Nrc Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives ML20210T9121999-08-13013 August 1999 Forwards Insp Rept 50-483/99-06 on 990613-0724.One Severity Level 4 Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ML20210P0371999-08-10010 August 1999 Forwards SE Granting Licensee 980710 Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code for Second 10-year Interval ISI at Plant,Unit 1 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ML20210H6381999-07-30030 July 1999 Forwards SE Accepting Relief Request for Approval for Use of Alternate Exam Requirement for Plant Inservice Insp Program A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20210B5611999-07-20020 July 1999 Forwards Review of Ltr & Encl Objectives for Plant,Unit 1,1999 Emergency Plan Exercise Scheduled for 990914 ML20210B4021999-07-19019 July 1999 Ack Receipt of Facility Emergency Plan Implementing Procedure EIP-ZZ-00101, Classification of Emergencies, Rev 23,issued on 990513,under Provisions of 10CFR50,App E, Section V ML20210B4401999-07-19019 July 1999 Ack Receipt of Revs to Facility Radiological Emergency Response Plan,Chapters 8.0 & 4.0,issued Respectively on 990512-14,under Provisions of 10CFR50,App E,Section V ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209E5591999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.TAC MA0531 Closed ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20196J9501999-07-0202 July 1999 Ack Receipt of Plant Ep,Rev 22,received on 981207 & Submitted Under Provision of 10CFR50,App E,Section V.Changes Does Not Decrease Effectiveness of EP & Continues to Meet Stds of 10CFR50.47(b).NRC Approval Not Required ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20196F8101999-06-25025 June 1999 Informs That J Donohew Will Assume Project Manager Responsibilities,Effective 990621 ML20196H2521999-06-25025 June 1999 Forwards Insp Rept 50-483/99-05 on 990502-0612.Two Violations Occurred & Being Treated as Noncited Violations, Consistent with App C of Enforcement Policy ML20196F8181999-06-24024 June 1999 Forwards RAI Re 990111 Request for Relief from Certain ASME Code ISI Requirements for Containment Liners.Response Requested within 30 Days from Date of Agreement ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve IR 05000483/19990041999-06-18018 June 1999 Refers to GL 96-05 Issued by NRC on 960918,UE Responses & 970313 & NRC Insp Rept 50-483/99-04,dtd 990427. Forwards Request for Addl Info Re GL 96-05 Program at Callaway Plant,Unit 1 ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H0971999-06-14014 June 1999 Discusses Une 990407 Request That Proprietary Document Entitled, Thermal Stability Assessment - Electrosleeved Tubes, Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20207H3751999-06-14014 June 1999 Discusses 990407 Une Request That Proprietary Version of Document Entitled, Evaluation of Severe Accident Simulation, Dtd April 1999,be Withheld from Public Disclosure.Determined Info Proprietary & Will Be Withheld ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20207G3201999-06-0707 June 1999 Ack Receipt of Change Notice 98-008 Dtd 980918,which Transmitted Changes to Callaway Plant Ep,Rev 21,under Provisions of 10CFR50,App E,Section V.No NRC Approval Required.No Violations Identified ML20207G3151999-06-0707 June 1999 Ack Receipt of Callaway Plant EP Implementing Procedure EIP-ZZ-001001M,Classification of Emergencies,Rev 22,issued on 981222 Under 10CFR50,App E,Section V Provisions.No Violations Identified ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS 1999-09-22 Category:INCOMING CORRESPONDENCE MONTHYEARML20217D5791999-09-15015 September 1999
[Table view]Provides Formal Documentation of Reviews & Discussions Re Technical Ltr Rept for Proprietary Info.Review of Ltr Was Discussed in Telcon & Via e-mail Messages. Summary of Telcons as Documented on 990708,included ML20212A4701999-09-10010 September 1999 Rssponds to NRC 990709 RAI Re Util Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection Iwe. Acceptance Criteria for Liner Plate Pressure Boundary Thickness Will Be Limited to 10% Nominal Thinning ML20210R7241999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for 990101-990630,IAW 10CFR26.71(d) ULNRC-04085, Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power1999-08-11011 August 1999 Forwards Rev 4 to Callaway Plant Cycle 10 COLR, Per TS 6.9.1.9.COLR Has Been Revised to Update Rod Bank Insertion (Ril) Limits,As Function of Rated Thermal Power ULNRC-04079, Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Forwards 180-day Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal ULNRC-04075, Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves1999-07-28028 July 1999 Forwards Response to NRC 990618 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of SR Motor-Operated Valves A93443, Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves1999-07-28028 July 1999 Forwards Addl Info as Committed to in Telcon Between Amerenue & NRC Personnel on 990616,re GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves ULNRC-04076, Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs1999-07-28028 July 1999 Informs of Implementation of Amend 131 to License NPF-30, Revising OL to Reflect Requirement in TS 3/4.7.1.7 for Four Operable ASD Lines & Associated Revs,Rather than Three Operable ASDs 05000483/LER-1998-008, Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved1999-07-27027 July 1999 Forwards Amended Response to GL 81-07, Control of Heavy Loads, to Address Corrective Action Described in LER 98-008-00.Discrepancy Between Earlier Submittals of Snupps Rept on Control of Heavy Loads & TS Re RHR Sys,Resolved ULNRC-04070, Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power1999-07-27027 July 1999 Forwards Rev 3 to Callaway Plant Cycle 10 COLR, IAW TS 6.9.1.9.COLR Has Been Revised to Update RAOC Axial Flux Difference (Afd) Limits,As Function of Rated Thermal Power ULNRC-04071, Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-021999-07-27027 July 1999 Informs That Util Anticipates Approx Ten Licensing Actions That Could Occur During Fys 2000 & 2001,in Response to Administrative Ltr 99-02 ML20212A3291999-07-15015 July 1999 Forwards Scenario Manual Containing Description of Callaway Plant 1999 Biennial Emergency Response Plan Exercise to Be Conducted 990914.Correspondence to Satisfy 60-day Submittal Requirement ML20209F3471999-07-0909 July 1999 Forwards Response to NRC 990624 RAI to Complete NRC Review of Relief Request to Allow Use of 1998 Edition of ASME Section Xi,Subsection IWE ML20209H2471999-07-0707 July 1999 Forwards Rev 29 to Physical Security Plan,Per 10CFR50.54(p). Rev Withheld,Per 10CFR73.21 ML20209C0171999-06-28028 June 1999 Forwards Special Rept 99-01 Re Fifteenth Year Inservice Containment Bldg Tendon Surveillance Failure.Observed Voids in Sheathing Filler Grease Do Not Indicate Degradation of post-tensioning Sys,Based on Encl Evaluation ML20209B6851999-06-28028 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Nuclear Power Plants. Disclosure Rept Encl ML20196G5621999-06-21021 June 1999 Informs NRC of Implementation of Amend 132 to Callaway License NPF-30 to Allows Installation of Electrosleeves for Steam Generator Tube Repair for Two Cycles Following Installation of First Electrosleeve ML20212J2441999-06-18018 June 1999 Submits Request for Alternate Exam Requirements for Plant Re ISI Program Plan.Plant Does Not Torque Bolted Connections to Stress Values Greater than 100 Ksi ML20195H9731999-06-11011 June 1999 Forwards Requested Addl Info Related to Relief Request ISI-16,encountered During Refuel 9 ML20195J9301999-06-0808 June 1999 Informs That Refuel 9 OAR-1 Owners Data Rept for ISI & Summary Rept for Interval 2 Was Submitted with Typographical Error,In That Commercial Service Date Should Be 841219,vice 941219.Please Substitute Encl Corrected Document ML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 A98803, Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS1999-05-27027 May 1999 Forwards Certified ITS & ITS Bases for Callaway Plant,In Response to NRC 990402 Draft SE for License Amend to Convert TSs to Format & Expanded Bases of ITS ML20196L2911999-05-19019 May 1999 Forwards Responses to NRC 990315 RAI Concerning GL 95-07, Pressure Locking & Thermal Binding of MOV Gate Valves A36791, Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl1999-05-17017 May 1999 Forwards Response to NRC 990510 RAI Re GL 96-06 with Respect to Analysis of Water Hammer & two-phase Flow Issues. Supporting Calculation Also Encl ULNRC-04034, Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions1999-05-17017 May 1999 Forwards Amerenues Risk Evaluation Summary & Provides Listing of Other Documents Which Have Been Previously Provided to Support Evaluation of Electrosleeves at High Temp Severe Accident Conditions 05000483/LER-1998-003, Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept1999-05-12012 May 1999 Forwards LER 98-003-01 Re Inadvertent Actuation of ESFAS Due to 'A' SG High Level During Refuel 9.Rept Is Submitted to Report Change in C/A from That Reported in Original Rept ML20206Q9551999-05-12012 May 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-04.Corrective Actions:Une Commits to Make Available for NRC Review,Action Plan Outlining Scope & Completion Dates of Project ULNRC-04027, Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 9905281999-05-0404 May 1999 Forwards Comments on Draft SE Re Proposed Conversion to Improved Tss.Copy of ITS & ITS Bases Will Be Provided by 990524,to Support Issuance of License Amend on or About 990528 ML20206E3211999-04-28028 April 1999 Forwards Special Rept 98-03 Re Inservice Insp of CP Sgs,Per Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage.Rept Is Being Resubmitted Due to Typos in Original Rept ML20206E5781999-04-23023 April 1999 Informs That R Schukai Is No Longer Employed with Amerenue & Info Sent Is No Longer Required.Name Should Be Removed from Mailing Lists.Mailing Label Used by Company Which May Assist in Matter,Submitted ULNRC-04018, Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date1999-04-21021 April 1999 Submits follow-up Items Re Proposed Conversion to ITS Sections 1.0,3.3,3.4,3.6,3.7 & 3.9.Suppl to Ltr Will Be Submitted at Later Date ML20205Q7751999-04-16016 April 1999 Forwards Special Rept 98-03 Concerning ISI of Callaway SGs Performed in Apr 1998 During Callaway Plants Ninth Ro. Rept Documents Final SG Insp Results ULNRC-04015, Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.211999-04-15015 April 1999 Forwards Cash Flow Projection & Certification to Satisfy Guarantee of Payment of Retrospective Premiums,Per 10CFR140.21 ULNRC-04005, Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.7901999-04-0707 April 1999 Forwards Proprietary & non-proprietary White Paper Entitled, Evaluation of Severe Accident Simulation, as Addl Info to Facilitate Approval of Requested Amend to Revise TS to Use Repair SG Tubes.Proprietary Info Withheld,Per 10CFR2.790 ULNRC-04004, Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld1999-04-0707 April 1999 Forwards Proprietary Thermal Stability Background Data Along with Time/Temp Graph Requested in 990402 Telcon with NRC & Contractor,Argonne Natl Lab.Proprietary Info Withheld ULNRC-04007, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date1999-04-0707 April 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6 & 3.7.Encl Includes mark-ups of ITS Sections 3.5,3.6 & 3.8.Suppl to Ltr Will Be Provided at Later Date ULNRC-04000, Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w)1999-04-0101 April 1999 Forwards Rept Re Present Level of Insurance & Sources of Insurance Applicable to Callaway Plant,Per 10CFR50.54(w) ULNRC-03998, Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.751999-03-30030 March 1999 Forwards Required Financial Info Re Decommissioning Callaway Nuclear Plant,Per 10CFR50.75 ML20205G2211999-03-25025 March 1999 Submits Rev 28A to Callaway Plant Physical Security Plan, Incorporating Addendum Re Security Sys Replacement Transition Plan,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20205R5251999-03-25025 March 1999 Forwards Special Rept 98-03 Re Results of Tenth SG Tube Inservice Insp,Per Requirements of Plant TS 4.4.5.5.b.Insp Was Performed in Apr 1998 During Plant Ninth Refueling Outage ULNRC-03988, Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 101999-03-19019 March 1999 Requests Approval of Alternative Exam ISI-12A Per 10CFR50.55a(a)(3)(i) & (II) for 1989 Edition of ASME Section IX,IWA-5242(a) for Class I Bolted Connections Inside Bioshield for RFO 10 ULNRC-03991, Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette1999-03-19019 March 1999 Forwards 1998 Annual Rept of Individual Monitoring Results, Per 10CFR20.2206.Rept Provided in Electronic Format on Diskette IAW Gudiance of Reg Guide 8.7.Without Diskette ML20204F7211999-03-17017 March 1999 Forwards Amended Fitness for Duty Program Performance Data for Six Month Period Beginning Jul-Dec 1998 ML20204E1331999-03-17017 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-483/99-02 on 990208-12.Corrective Actions:Will Revise Security Plan to Increase Min Staffing by Three Armed Security Force Response Personnel Per Shift ML20207C3631999-03-12012 March 1999 Forwards Exam Matl & Associated QA Checklist for Written Exam to Support Plant RO Retake Exam Scheduled for 990423. Exam Matls Requested to Be Withheld from Public Disclosure Until After Exam Completion 05000483/LER-1998-001, Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability1999-03-10010 March 1999 Forwards LER 98-001-01,being Submitted to Clarify Scope of Original Reviews Performed for Corrective Action Number 3 in LER 98-001-00.Reviews Have Identified Case of Failure to Properly Establish Equipment Operability ULNRC-03979, Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date1999-03-0909 March 1999 Submits follow-up Items Related to Proposed Conversion to ITSs Sections 3.3,3.4,3.6,3.7,3.8,3.9 & 5.0.Suppl to Ltr Dtd 970515,will Be Provided at Later Date ULNRC-03975, Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl1999-03-0505 March 1999 Informs of No Reportable ECCS Evaluation Model Revs for Callaway During Time Period from Mar 1998 to Mar 1999,IAW 10CFR50.46.ECCS Evaluation Model Margin Assessment Encl ULNRC-03971, Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded1999-02-26026 February 1999 Forwards Annual Personnel Exposure & Monitoring Rept for 1998, Per TS Sections 6.9.1.4 & 6.9.1.5.Rept Includes One Incident of Specific Activity Analysis of RCS in Which Limits of TS 3.4.8 Were Exceeded ML20207A4311999-02-17017 February 1999 Forwards semi-annual Fitness for Duty Program Performance Data Rept for Callaway Nuclear Plant for Period of 980701-981231 1999-09-15 Category:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC MONTHYEARML20151Z1391988-08-18018 August 1988
[Table view]Requests Info Re Changes Expected in 1,000 Mwe Reactors in Which Fuel Design & Operating Life Changed ML20235H2201987-06-16016 June 1987 Requests Addl Info Re Two Level IV Violations Issued to Union Electric Involving Primary Coolant Leak in Aug 1986 at Facility ML20133J4841985-09-23023 September 1985 FOIA Request for Four Categories of Documents Re QC at Facility.Newspaper Articles Re Problems W/Qc Encl ML20128Q6401985-05-0808 May 1985 FOIA Request for Three Categories of Documents Re Facility ML20133H5721985-05-0808 May 1985 FOIA Request for Documents Re Facility,Including All Contacts Between DOE Task Force on Commercial Nuclear Power, White House Cabinet Council Working Group & NRC Concerning OL ML20128P9121985-03-25025 March 1985 FOIA Request for Records & Info Re Insp Rept 50-483/84-45 ML19301D2531985-03-11011 March 1985 Requests Listed Info Re Measurement of Transuranics in Facility Low Level Radwastes to Be Packaged for Burial,Per J Holonich 831221 Response to 831111 Request.Answers Not Found in Tech Spec 3/4 11.3 Concerning Solid Radwastes ML20126E1841985-02-0101 February 1985 FOIA Request for Documents Re Five Categories of Documents, Including Insp Repts 50-483/84-30,50-483/83-13,50-483/83-09 & 50-483/84-45 ML20100J8591985-01-30030 January 1985 Expresses Disappointment W/Nrc Decision Not to Pursue Addl Available Info Re Serious Safety Allegations Provided in 840928 2.206 Petition.Nrc Approach to Whistleblowers Uses Inadequate Insp Efforts ML20206P1231984-12-0303 December 1984 FOIA Request for Info Re Facility,Including 840928 Citizens Petition Submitted Per 10CFR2.206 & J Keppler Memo to H Denton Re Facility Readiness for Full Power License ML20107F9461984-10-27027 October 1984 Requests Info Re Flaw Indication (Crack) Discovered on 840806 at Indian Point 2 Vessel During 10-yr Inservice Insp ML20108C0571984-10-17017 October 1984 Requests Notice 14 Days Prior to Issuance of OL in Order to Consider & Pursue Other Legal Remedies.Nrc Consideration of 841002 10CFR2.206 Petition Insufficient ML20098F4131984-09-28028 September 1984 Requests Suspension of Low Power License Until Investigation of Each of Listed Allegations & Appropriate Reinsp Performed to Determine Extent of Problems Raised by Each Allegation ML20102B6681984-08-22022 August 1984 FOIA Request for Documents Re NRC 840612 Interviews Concerning Facility & Allegations Made During Interviews ML20107J8971984-08-0707 August 1984 FOIA Request for All Documents Re 840704 Incident Involving Eight Switched Off Circuit Breakers & 840602-03 Incident Involving Large Amount of Water Spilled on Reactor Bldg Floor ML20112G3911984-05-17017 May 1984 FOIA Request for Repts Re Facilities,Including SALP Repts, Const Audit Team Repts & Const Deficiency Repts from Start of Const to Present ML20084M1351984-05-10010 May 1984 Requests Explanation of Criteria Used to Determine Which critical,safety-related Component & Piping Sys Welds Exempt from ASME Code Insps ML20112F5721984-04-13013 April 1984 FOIA Request for G Mizuno to J Ellis Re Plant,Ltr to ASLB Judges W/Four Encls,Aslb Chairman Block 831228 Order on QA Design of Plant & IE Snupps Callaway 1 Rept. Forwards Documents ML20090L6511984-03-15015 March 1984 FOIA Request for Four Listed Categories of Documents, Including Design Verification,Welder Qualification & Proposed Fuel Load Date ML20091K5031984-03-15015 March 1984 FOIA Request for All Documents Re Four Items.Items Include Decision Re Design Verification Activities,Per DG Eisenhut ,Ie Rept 78-04 & Basis of Jg Keppler 781102 Conclusions Concerning Welder Qualifications ML20086N2361984-02-13013 February 1984 Requests Tubing Info from Eddy Current Steam Generator June,Jul,Aug & Sept 1983 Insps ML20076F5881983-08-21021 August 1983 Requests Info Re Likelihood of Plant Operation.Plant Operation Opposed ML20081J7051983-06-16016 June 1983 FOIA Request for Drafts of Integrated Design Insp Program Rept for Facility & Matl Outlining Criteria Used to Select Plants for Review ML20064N6541983-02-0909 February 1983 Confirms 830101 & 07 Telcons Re Objection to Applicant 830121 Proposed Change of Schedule.Change Unjustified.Ruling on Contentions 16 - 20 Omitted from 821207 Memorandum & Order Requested ML20063N7601982-09-23023 September 1982 Advises That No Radiological Emergency Response Plan or Std Operating Procedure Has Been Developed or Accepted by Montgomery or Gasconade Counties,Mo,As Reported in RW Krimm 820817 Memo ML19255A5961982-02-15015 February 1982 Requests Info Concerning Documents Withheld from Public Disclosure Re Facilities Setpoint Methodology.Specifically, Whether Methodology Refers to Westinghouse Radioactive Waste Alarm Monitoring Sys ML20039B5011981-12-17017 December 1981 Requests Schedule for Actions by Union Electric Co to Close Out All Open Items,Confirmatory Items & Licensing Conditions in Ser.Related Document Encl ML19303A2971981-11-30030 November 1981 Comments Negatively on Des.Possibilities of Monitoring Sys Failure & Inadequate Detection of Highly Radioactive Liquid Waste Streams & Other Unplanned Releases Have Been Ignored ML20041A0601981-11-29029 November 1981 Comments on Facility Des (NUREG-0813).No Apparent Info Given on Probable Emission Levels Occuring in Case of Most Probable Accidents ML20041A0621981-11-28028 November 1981 Requests Listing of Precautions to Be Implemented to Avoid Leakages Along Piping from Plant to Ms River ML20041A0711981-11-28028 November 1981 Requests Info Re Precautions Taken to Avoid Steam Generator Problems Occurring at Westinghouse Plants ML20041A0701981-11-28028 November 1981 Requests Info Re Beir 3 Rept Estimates Concerning Excess Genetic Disorders ML20041A0691981-11-28028 November 1981 Submits That Facility Des Minimizes Worker Exposure Rate. Description of New & Accurate Monitoring Processes & Worker Shielding to Be Used at Facility Requested ML20041A0661981-11-28028 November 1981 Requests Info Re Correlation of Statistics Concerning Beir 3 Rept Estimate That Three of 10 Cancer Deaths Could Be Among 1980 Reactor Workers ML20041A0681981-11-28028 November 1981 Opposes Facility Licensing Because Westinghouse Reactors Cause Numerous Problems,No Workable Evacuation Plan Exists, Waste Problem Not Solved,Radiation Is Dangerous,Conservation Is Working & Alternate Energy Sources Are Less Costly ML20038C1371981-11-24024 November 1981 Comments on NUREG-0813,DES Re Environ Impact of Facility. Opposes Issuance of OL ML19303A2961981-11-24024 November 1981 Comments on NUREG-0813,DES for Facility.Section 5.9.4.2, Accident Experience & Observed Impacts Is Misleading ML19303A2921981-11-0303 November 1981 Comments on NUREG-0813,facility Des.Document Is Contradictory & Unjustified.Recommends That Entire Rept Be Rewritten ML20126M2181981-05-13013 May 1981 Requests Clarification of Words & Symbols in NUREG-0654, Revision 1.Certificate of Svc Encl ML20126G1111981-03-17017 March 1981 Requests Notification of Whether Request to Intervene Has Been Granted.Also Requests That Hearings Be Held in Burlington or at Plant Site,Due to Travel Required for Attendance at Hearings in MD ML20049A4291981-01-30030 January 1981 Suppls Request to Participate as Local Govt Representative by Informing of Position in Govt ML20062L1231981-01-11011 January 1981 Forwards to State of Mo Clean Water Commission & Mo Dept of Resource 801215 Response Re Issuance of Ol. Petition Protesting Licensing of Facility Provided ML19340E9181980-12-24024 December 1980 Requests to Represent City of Owensville,Mo in Proceeding. Certificate of Svc Encl ML19347C6421980-12-22022 December 1980 Requests to Make Limited Appearance Statement on Behalf of City of Chamois,Mo ML19347C6451980-12-22022 December 1980 Requests to Make Limited Appearance Statement on Behalf of City of Owensville,Mo.Certificate of Svc Encl ML20027A6461980-12-22022 December 1980 Requests to Make Limited Appearance Statement in Proceeding. Certificate of Svc Encl ML19347C6461980-12-22022 December 1980 Requests to Make Limited Appearance Statement on Behalf of Auxvasse,Mo School District ML19347C6401980-12-22022 December 1980 Requests to Make Limited Appearance Statement on Behalf of City of Rhineland,Mo.Certificate of Svc Encl ML20062L0441980-12-0909 December 1980 Requests Info Re Requirements for Util in Limiting Discharge Into Mo River According to NRC & Federal Regulations ML19337B5951980-09-28028 September 1980 Requests Correction of Typographical Errors Re 800922 Petition for Leave to Intervene 1988-08-18 |
Text
r1 N
= Mrs. Leo Drey
' 515 West Point Avenue Universley City, Mo 63130 0ctober 27, 1984
- Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
E lt was_ nice having the opportunity finally to meet you in person in the elavator. descending (!) from the NRC's briefing on October 4, the day it was decided by the Commissioners that our Callaway plant here
-in Missouri is just in fine shape and in perfectly competent hands to be operated safely at full power. I certainly wish I could agree with either conclusion.
I am writing to ask if I may please trouble you for information about the flow Indication (crack) discovered on August 6,1984 in the indian Point 2 reactor vessel during the 10 year in-service inspection?
Have you decided as yet whether the crack is one to two inches in depth, or no greater than a third of an inch; and do you still believe it is approximately two inches in length? Are you relying upon Consolidated Edison, Westinghouse (as Coned's In-service contractor),
Coned's independent consultant from Combustion Engineering, or NRC staff members to determine the actual measurements of the crack?
Because I believe our Callaway reactor vessel was also fabricated by Combustion Engineering, I find this " indication" to be particularly troublesome.
Sincerely,
/
\
(JWR SEEBil
- -
Retrieved from "https://kanterella.com/w/index.php?title=ML20107F946&oldid=2797126"