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Category:CORRESPONDENCE-LETTERS
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 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 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested 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 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 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 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20210K1621999-07-0707 July 1999 Informs That Licensee in Process of Preparing Scope of Service Delineation for Environ Assessment to Be Performed for New Airport Located Near Russellville,Ar,To Identify Anticipated Environ Impacts from Various Agencies 1CAN079902, Documents ANO-1 Position Discussed on 990705,with Members of NRC Staff & Formally Requests Enforcement Discretion from Requirements of TS 3.7.2.C to Allow Continued Power of Operation1999-07-0606 July 1999 Documents ANO-1 Position Discussed on 990705,with Members of NRC Staff & Formally Requests Enforcement Discretion from Requirements of TS 3.7.2.C to Allow Continued Power of Operation ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 0CAN069906, Forwards Corrected Pages to 1997 & 1998 Annual Radiological Environ Operating Repts, Issued 980430 (0CAN049804) & 990506 (0CAN059902).Ltr Number & Page Number Are at Top of of Corrected Pages to Replace Originally Pages1999-06-30030 June 1999 Forwards Corrected Pages to 1997 & 1998 Annual Radiological Environ Operating Repts, Issued 980430 (0CAN049804) & 990506 (0CAN059902).Ltr Number & Page Number Are at Top of of Corrected Pages to Replace Originally Pages 1CAN069905, Forwards non-proprietary Version of Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs1999-06-17017 June 1999 Forwards non-proprietary Version of Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs 0CAN069903, Submits Rept of Each Change to or Error Discovered in Acceptable Evaluation Model or in Application of Such Model for ECCS That Affects Peak Cladding Temp,Iaw 10CFR50.46(a) (3)(ii)1999-06-10010 June 1999 Submits Rept of Each Change to or Error Discovered in Acceptable Evaluation Model or in Application of Such Model for ECCS That Affects Peak Cladding Temp,Iaw 10CFR50.46(a) (3)(ii) 2CAN069901, Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 20001999-06-0202 June 1999 Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 2000 1CAN069901, Submits 10CFR50.46 Rept Re Inconsistent Input in SBLOCA Analysis.Rept Submitted in Accordance with Recommendations Stated in Notice1999-06-0202 June 1999 Submits 10CFR50.46 Rept Re Inconsistent Input in SBLOCA Analysis.Rept Submitted in Accordance with Recommendations Stated in Notice 0CAN059906, Forwards Response to NRC 990402 RAI Re GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-05-28028 May 1999 Forwards Response to NRC 990402 RAI Re GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs ML20207E4341999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft 1CAN059904, Informs NRC That Wl Franklin No Longer Has Need to Maintain Operating License on Ano,Unit 1.Requests License for Wl Franklin Be Withdrawn1999-05-20020 May 1999 Informs NRC That Wl Franklin No Longer Has Need to Maintain Operating License on Ano,Unit 1.Requests License for Wl Franklin Be Withdrawn 2CAN059906, Informs That ANO-2 UFSAR Will Be Revised to Include Comprehensive Discussions of Each Category of Containment Penetration Overcurrent Protective Devices,Per NRC Review of 980806 TS Change Request Re Relocation of TS Table 3.8-11999-05-18018 May 1999 Informs That ANO-2 UFSAR Will Be Revised to Include Comprehensive Discussions of Each Category of Containment Penetration Overcurrent Protective Devices,Per NRC Review of 980806 TS Change Request Re Relocation of TS Table 3.8-1 1CAN059902, Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program1999-05-17017 May 1999 Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program 2CAN059905, Expresses Appreciation for Staff & Mgt Team Efforts in Aggressively Pursuing Risk Informed ISI Initiative1999-05-14014 May 1999 Expresses Appreciation for Staff & Mgt Team Efforts in Aggressively Pursuing Risk Informed ISI Initiative ML20206P7681999-05-10010 May 1999 Forwards Applications for Renewal of Operating License (Form 398) for MW Little & F Uptagrafft.Without Encl 2CAN059903, Forwards Rev to Footnote Submitted to Provide Clarity to Aforementioned Guidance1999-05-10010 May 1999 Forwards Rev to Footnote Submitted to Provide Clarity to Aforementioned Guidance ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206H7121999-05-0606 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept, for Ano.All Radionuclides Detected by Radiological Environ Monitoring Program During 1998 Were Significantly Below Regulatory Limits 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEAR2CAN099009, Requests Interim Relief from Inservice Testing Re Performing Partial Stroke Test for Check Valve 2SI-16A.Valve Currently Required to Be Tested by 9009251990-09-21021 September 1990 Requests Interim Relief from Inservice Testing Re Performing Partial Stroke Test for Check Valve 2SI-16A.Valve Currently Required to Be Tested by 900925 0CAN099002, Discusses Validation of Nonlicensed Operator Staffing,In Response to Insp Repts 50-313/90-01 & 50-368/90-01.Concludes That Current Level of Three Nonlicensed Operators Per Shift, Adequate to Meet Demands of Operations Under EOP1990-09-14014 September 1990 Discusses Validation of Nonlicensed Operator Staffing,In Response to Insp Repts 50-313/90-01 & 50-368/90-01.Concludes That Current Level of Three Nonlicensed Operators Per Shift, Adequate to Meet Demands of Operations Under EOP 0CAN099007, Forwards Operator Licensing Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-14014 September 1990 Forwards Operator Licensing Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 2CAN099004, Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis1990-09-0707 September 1990 Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis 0CAN099001, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/90-19 & 50-368/90-19.Corrective Actions:Surveillance Procedures Reverified & Revised1990-09-0707 September 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/90-19 & 50-368/90-19.Corrective Actions:Surveillance Procedures Reverified & Revised 1CAN099003, Requests one-time Rev to Natl Exam Schedule for Operator License & Requalification Exams at Facility to Allow Testing in Aug,Rather than Feb of 19911990-09-0606 September 1990 Requests one-time Rev to Natl Exam Schedule for Operator License & Requalification Exams at Facility to Allow Testing in Aug,Rather than Feb of 1991 0CAN089009, Informs of Relocation to New Generation Support Bldg Just Outside Protected Area Southeast of Administration Bldg1990-08-31031 August 1990 Informs of Relocation to New Generation Support Bldg Just Outside Protected Area Southeast of Administration Bldg 0CAN089006, Forwards Semiannual Radiological Effluent Release Rept for First & Second Quarters 1990 & Changes to ODCM & Process Control Manual1990-08-30030 August 1990 Forwards Semiannual Radiological Effluent Release Rept for First & Second Quarters 1990 & Changes to ODCM & Process Control Manual 0CAN089008, Forwards Facility fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.73(d)1990-08-29029 August 1990 Forwards Facility fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.73(d) 0CAN089005, Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 9010011990-08-27027 August 1990 Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 901001 1CAN089011, Requests Relief from ASME Code Section XI Requirements Re Exercise & Stroke Time Testing for Low Pressure Injection Valves CV-1432 & CV-1433.Valves Located in Bypass Lines Around Decay Heat Coolers1990-08-16016 August 1990 Requests Relief from ASME Code Section XI Requirements Re Exercise & Stroke Time Testing for Low Pressure Injection Valves CV-1432 & CV-1433.Valves Located in Bypass Lines Around Decay Heat Coolers 2CAN089009, Requests Addl Time to Respond to NRC 900607 Request for Info Re Second 10-yr Interval of Inservice Insp Program. Response Will Be Submitted No Later than 9010311990-08-13013 August 1990 Requests Addl Time to Respond to NRC 900607 Request for Info Re Second 10-yr Interval of Inservice Insp Program. Response Will Be Submitted No Later than 901031 0CAN089002, Responds to Recommendations from Insp Repts 50-313/90-04 & 50-368/90-04 on 900202 That Reporting Format for Semiannual Radioactive Effluent Release Repts Be Revised to Comply W/ Reg Guide 1.21,Rev 11990-08-0808 August 1990 Responds to Recommendations from Insp Repts 50-313/90-04 & 50-368/90-04 on 900202 That Reporting Format for Semiannual Radioactive Effluent Release Repts Be Revised to Comply W/ Reg Guide 1.21,Rev 1 05000313/LER-1989-041, Revises Commitment Completion Date for LER 89-041-00 Re Proper Method of Calibr of Startup Feedwater Control Valves CV-2623 & 2673 to 900915.Delay Due to Time Needed to Review & Implement New Calibr Guidance Criteria1990-08-0202 August 1990 Revises Commitment Completion Date for LER 89-041-00 Re Proper Method of Calibr of Startup Feedwater Control Valves CV-2623 & 2673 to 900915.Delay Due to Time Needed to Review & Implement New Calibr Guidance Criteria 2CAN089006, Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info1990-08-0202 August 1990 Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info ML20081E0891990-07-31031 July 1990 Advises That Since Guidance Contained in Reg Guide 1.97 Not Addressed in Submittals Re Generic Ltr 82-33,further Clarification of Position Re Compliance W/Generic Ltr Appropriate,Per .Ltr Will Be Submitted by 901215 0CAN079014, Amends Commitment Date for Mods to Svc Water Pump Design,Per Insp Repts 50-313/89-30 & 50-368/89-30.Project Scoping Rept Expected to Be Completed by 9009301990-07-31031 July 1990 Amends Commitment Date for Mods to Svc Water Pump Design,Per Insp Repts 50-313/89-30 & 50-368/89-30.Project Scoping Rept Expected to Be Completed by 900930 0CAN079024, Forwards Revised Response to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Specific Communication Meetings Will Be Conducted W/Staff Re Decontamination Practices & Procedures1990-07-31031 July 1990 Forwards Revised Response to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Specific Communication Meetings Will Be Conducted W/Staff Re Decontamination Practices & Procedures 0CAN079020, Forwards Update to Status of Remaining Open Items on Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Encl Withheld (Ref 10CFR2.790)1990-07-31031 July 1990 Forwards Update to Status of Remaining Open Items on Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Encl Withheld (Ref 10CFR2.790) 0CAN079018, Certifies That Info Contained in Rev 12 to QA Manual Operations Freighted to NRC on 900723 & Accurately Represents Changes Made Since Previous Submittal,Per 10CFR50.54(a)(3)1990-07-24024 July 1990 Certifies That Info Contained in Rev 12 to QA Manual Operations Freighted to NRC on 900723 & Accurately Represents Changes Made Since Previous Submittal,Per 10CFR50.54(a)(3) 0CAN079021, Forwards Rev 12 to QA Manual Operations1990-07-23023 July 1990 Forwards Rev 12 to QA Manual Operations 0CAN079019, Forwards Rev 12 to QA Manual Operations.W/O Encl1990-07-23023 July 1990 Forwards Rev 12 to QA Manual Operations.W/O Encl 0CAN079011, Suppls Response to Violations Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Re Isolation Valve CS-26. Corrective Actions:Special Work Plan Developed & Valve Cs-26 Local Leak Rate Tested on 9002161990-07-20020 July 1990 Suppls Response to Violations Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Re Isolation Valve CS-26. Corrective Actions:Special Work Plan Developed & Valve Cs-26 Local Leak Rate Tested on 900216 2CAN079008, Forwards Response to NRC Questions on CEN-386-P Re Extended Burnup Rept & Statistical Treatment of Elastic Strain in Fuel Cladding at end-of-life & Measured Axial Fuel Rod pellet-to-pellet Gaps1990-07-17017 July 1990 Forwards Response to NRC Questions on CEN-386-P Re Extended Burnup Rept & Statistical Treatment of Elastic Strain in Fuel Cladding at end-of-life & Measured Axial Fuel Rod pellet-to-pellet Gaps 0CAN079006, Provides Update to Util Providing Results of Comparison of Station Blackout Rule Submittals to NUMARC Guidance1990-07-17017 July 1990 Provides Update to Util Providing Results of Comparison of Station Blackout Rule Submittals to NUMARC Guidance 2CAN079001, Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip1990-07-0505 July 1990 Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip ML20043H5161990-06-19019 June 1990 Informs of Changes of Responsibility for Plant Emergency Plan,Effective 900605 ML20043H3121990-06-18018 June 1990 Forwards Responses to Remaining NRC Questions Re Seismically Qualified,Partially Protected,Condensate Storage Tank (Qcst).Analyses in Calculations Demonstrate That Qcst Tank Foundation & Drilled Piers Adequate W/O Mod ML20043F3321990-06-15015 June 1990 Submits Addl Info on Tech Spec Change Request for Seismic Instrumentation,Per 890809 Request.Licensee Concurs W/Nrc Recommendation Re Editorial Change ML20043G0661990-06-13013 June 1990 Responds to Deviations Noted in Insp Repts 50-313/90-11 & 50-368/90-11.Corrective Actions:Further Evaluations Conducted to Develop Optimum List of post-accident Instruments Requiring Identification on Control Panels ML20043H3471990-06-11011 June 1990 Forwards Rev 19 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043G3801990-06-11011 June 1990 Responds to Violations Noted in Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Decision Made to Staff Unit 1 Exit Location Point W/Health Physics Technician 24 H Per Day ML20043F5121990-06-0808 June 1990 Forwards List of Directors & Officers of Entergy Operations, Inc.Operation of All Plants Transferred to Entergy on 900606 ML20043F4341990-06-0707 June 1990 Informs of Receipt of Necessary Approvals to Transfer Operating Responsibilities of Plant to Entergy Operations, Per Amends 128 & 102 to Licenses DPR-51 & NPF-6, Respectively.Extension of Amend Request Unnecessary ML20043E6561990-06-0707 June 1990 Requests That Listed Distribution Be Made on All Future NRC Correspondence.Correspondence to Ns Carns Should Be Addressed to Russellville ML20043E4991990-06-0505 June 1990 Provides Supplemental Response to Violations Noted in Insp Repts 50-313/89-02 & 50-368/89-02.Corrective Actions:Listed Program Enhancements Being Implemented to LER Process to Provide Timely Determinations of Condition Rept ML20043E3851990-06-0404 June 1990 Concurs w/900516 Ltr Re Implementation of SPDS Complete for Both Units & Requirements of NUREG-0737,Suppl 1 Met ML20043E3771990-06-0404 June 1990 Forwards Response to Concerns Re Control Room Habitability Survey.Addl Mods Identified Will Enhance Overall Reliability of Control Room Sys & Changes Designed to Increase Performance,Effectiveness & Response of Habitability Sys ML20043C0821990-05-25025 May 1990 Withdraws 900410 Request to Amend Tech Spec Table 3.3-1 Re Applicable Operational Modes for Certain Reactor Protective Instrumentation Operability Requirements ML20043B6531990-05-22022 May 1990 Forwards Rev to Industrial Security Plan to Eliminate Need to Protect Certain Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21) ML20043B7091990-05-21021 May 1990 Forwards Revised Maelu Certificate of Insurance for Nuclear Onsite Property Insurance Coverage for 1990,changing Policy Number from X89166 to X90143R ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A5991990-05-15015 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Repts for Feb & Mar 1990 for Arkansas Nuclear One,Unit 1 ML20042H0551990-05-0909 May 1990 Forwards Civil Penalty in Amount of $50,000 for Violations Noted in Insp Repts 50-313/86-23 & 50-368/86-24 Re Environ Qualification of Electrical Equipment Important to Safety. Comprehensive Corrective Actions Undertaken ML20043B0841990-05-0909 May 1990 Corrects 900309 Ltr Re Completion of Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Design Change Package Addressing Perimeter & Interior Lighting Scheduled to Be Onsite Late Summer 1991 ML20043A8361990-05-0707 May 1990 Responds to Violations Noted in Insp Repts 50-313/90-05 & 50-368/90-05.Corrective Actions:Personnel Involved Received Counselling Re Incident & Operations Personnel Being Trained on Significance of Surveillance Requirements ML20042F4371990-05-0404 May 1990 Requests 90-day Extension to Provide Addl Time for Reviews of Amends 128 & 102 to Licenses DPR-51 & NPF-6,respectively, Re Ownership Transfer ML20042G4771990-05-0404 May 1990 Forwards Summary of Util Exercise Critique Board Evaluation of Radiological Emergency Preparedness Exercise REX-90,per Insp Repts 50-313/90-08 & 50-368/90-08 ML20042F3351990-05-0303 May 1990 Forwards Nonproprietary Suppl 1 to CEN-386-NP & Proprietary Suppl 1 to CEN-386-P, Responses to Questions on C-E Rept CEN-386-P, 'Verification of Acceptability of 1-Pin Burnup Limit....' Proprietary Rept Withheld (Ref 10CFR2.790) ML20042F2701990-04-30030 April 1990 Provides Exam Schedules for Reactor Coolant Pumps a & B in Revised Inservice Insp Program Plan.Insps Scheduled for Refueling Outages 1R10 & 1R12 for Pump a Exams & Refueling Outages 1R10,1R12 & 1R14 for Pump B Exams 1990-09-07
[Table view] |
Text
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501)371-4000 December 17, 1984 0CAN128404 Mr. Ira Dinitz, Insurance Indemnity Analyst Licensee Relations Section Office of the State Programs Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Nuclear Liability Insurance Gentlemen:
Your November 26, 1984 letter (0Ch18420)statedthatthefollowing endorsements to our Nuclear Liability Insurance policies had not been received:
- 1) Policy NF-210 -
Endorcement Nos. 47-52, 17-21, and 11-15; and
- 2) Policy MF-74 -
Endorcement Nos. 41-44.
You also indicated that Amendment 2 to Indemnity Agreement B-65 had not been received. Enclosed are the requested endorsements and Amendment 2 to Indemnity Agreement B-65.
Also we would like to inform you that Mr. John M. Griffin is now Sr. Vice President,EnergySupplyandrequeststhatfuturemailbeaddressedtohim at P. O. Box 551, Little Rock, AR 72203.
Very truly yours, 330 04 sg2 P
Mock 050gjQ3 ppR J. Ted Enos J Manager, Licensing JTE:SAB:sh Enclosures f00$
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Nuclear Energy Liability insurance NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION
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b/ 1) ADVANCE PREMlUM AND STANDARD PREMlUM ENDORSEMENT
- 2) CHANGES IN SUBSCRIBING COMPANIES AND IN THEIR '
PROPORTIONATE LIABILITY ENDORSEMENT l.i Calendor Year 1974 lo. ADVANCE PREMlUM: It is agreed that the Advance Premium due the companies for the period designated above is: $ 2,000.00
- b. STANDARD PREMlUM AND RESERV'E PREMlUM: In the obsence of a change in the Advance Premium indicated above, it is agreed that, subject to the provisions of the industry Credit Rating Plon, the Standard Premium is sold Advance Premium and the Resene Premium is: $ 1,340.00 2.- It'is agreed that with respect to bodily injury or property demoge caused, 'during the effective period of this endorsement, by the nuclear energy hozord:
- a. The word " companies" wherever used in the policy means the subscribing companies listed on the reverse side of this endorsement.
- b. The policy shall be binding on such companies only.
y- c. Each such company shall be liable only for its proportion of any obligation assumed or expense incurred under the policy because of such bodily injury or property damage os designated on the reverse side of this endorsement.
- 3. It is agreed that the effective period of this endorsement is to the close of December 31st of the Calendor Year designated in the caption above, or to the time of the termination or concelation of the policy, if sooner.
(over) is * .lonvary 1, 197 4 NF-210 7,go,,,p,n og por;qy, 12:01 A.M. Standard Time luued - Arkansas Power & LiRht Company n,w .ggo,, November 1,1973 For the SuburMag Compaeles By -- (M IMMW
/ General Mornger
(/ RE0SAMEN & ASSOCIATES, INC.
Indorsement No II r Countmigned t>y
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- 8 Nuclear Energy Llobility Insumnce NUCLEAR ENERGY LIABILITY INSUltANCE ASSOCIATION b) 1.1 Amendment of Condition 4 Endorsement i
It is agreed that with respect to bodily injury and property damage caused after the effective data of this endorsement by the nuclear energy hazard the figure $73,625,000 stated in condition 4 of the policy is amended to read $85,250,000.
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Esenho Deas d g-- January _1, 1974 To ben a pst d W m NF-210 12:01 A.M. senadasd Time 3,,,,g Arkansas Power & Light Company January 15,_1974 N du subscriWas r a-pa 6 Dune d h By ) eard
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Nuclear Energy Llobility Insurance NUCLEAlt' ENERGY LIABILITY INSURANCE ASSOCIATION U .e
. Addrews of Nuclear Enerny I,f ability Insurance Associntion Endorsement It is agreed that the address of the Nuclear Energy Liability Insurance Association appearing in the " Company Representation" condition of the policy is amended to read:
The Exchange Farmington Avenue Farmington, Connecticut 06032 J
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12:01 A.M. senadard he Issued u Arkansas Power & Light Company g g,f March 15, 1974 'l , For the Subsen%g Comunies
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Nuctocr Energy liabbity insurence NUCLEAR ENERGY LIABillTY INSURANCE ASSOCIATION D
INCREASE OF LIMIT OF LIABILITY ENDORSEMENT l.:
It is aa. rend tiat:
- 1. The limit of liability stated in Item 4 of the declarations of the policy is amended to read $ As ?so non .
This amenced limit applies with respect to obligations assumed or expenses incurred because of bodily injury or property dr. age caused, during the period from the effective date of this endorsement to the date of termination of the policy, by the nuclear energy hazard,
- 2. .The limit of liability stated in Item 4 of'the declarations and the amended limit of liability stated in paragraph 1 above shall not be cumulative, and each payment made by the companies after the effective date of this endorsement for cny loss or expense' covered by'the policy shall reduce by the amount of sitch payment both the limit of liability stated in Item 4 of the declarations and the amended limit stated V in paragraph 1 above, regardless of which limit of liability applies with respect to the bodily injury or property damage out of which such loss or expense arises, e
Thit: Ss to oortify that this E the a. iginal Endorsecent Mo Pn1;.r: Temt th.
is a true copy of
\ 7 ( acility Form) No. NFNodin: lO. / mdo a part of Nuclear Encrey Lit t . ,
ty i 5urasco is afforded henu n er d CHA . BAR - , UNDERWP.lTING MAMAGER NUCLEAR ENERGY LIA ttlTY INSURANCE ASSOCIATION Efective Date of this Endone=, Ma\y10, 1974 To fe m a put of PoG y No MP 91n '
12:01 A.M. Stand.ud Tune haued ta Arkansas Power and Licht rmmnv Date of hme May 30. 1974 For the Su!scr1Ing Campeds
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Nuclear Energy Liability Insurance NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION O
ADVANCE PREMIW1 AND SYANDARD PRDilmt ENDORSEMENT Calendar Year m if.
It is agreed that Items la. and Ib. of Endorsement No. 11 are amended to read:
la. ADVANCE PREMIUM: It is agreed that the Advance Premium due the companies for the period designated above is:
$ 7,625.67 lb. STANDARD PRDlIM1 AND RESERVE PRDlIUM: In the absence of a change in the Advance Premium indicated above, it is agreed that, subject to the provisions of the Industry Credit Rating Plan, the Standard Premium is said Advance Premium and the Reserve Premium is: $ 5,109.28 Additional Premium: $5,625.67 Pita is 13 5dMify that th!c E- 1 . r 'S
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...,.2 is afforded hereunder en,, L DAQ , f.. '.'RIT!r!3 MANAGER r&i. SEA ErlERGY l' ABilliY I! EUl;/.3CE *,SSOCIATION Effectice Date of \
this Endorsemear .lanuary 1: 1974 To form a part of Policy No ILot .Uf. Staadarj Trne A'U 'llO Issued m Arkansas Power and Liche enmnnny Date of Issue . May 30. 1974 For the subscribias cornpanies
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Endorsernent No Countersigned by bE36 L';. . - - - - .
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Nuclear Energy Liability insurance NUCLEAR ENERGY f. LABILITY INSURANCE ASSOCIATION V 1) ADVANCE PREMIUM AND STANDARD PREMIUM ENDORSEMENT
- 2) CHANGES IN SUBSCRIBING COMPANIES AND IN THEIR PROPORTIONATE LIABILITY ENDORSEMENT Calendarhs$r 1975 la. ADVANCE PREMIUM: It is agreed that the Advance Premium due the companies for the period designated above is: $ 161 ?nn.no
- b. STANDARD PREMIUM AND RESERVE PREMIUM: In the absence of a change in the Advance Premium indicated above it is agreed that, subject to the pro-visions of the Industry Credit Rating Plan, the Standard Premium is said Advance Premium and the Reserve Premium is: $ 120,187.00
- 2. It is agreed that with respect to bodily injury or property damage caused, during the effective period of this endorsement, by the nuclear energy hazard:
- a. The word " companies" wherever used in the policy means the subscribing companies listed on the reverse side of this endorsement.
- b. The policy shall be binding on such companies only.
- c. Each such company shall beliable only for its pro-portion of any obligaticr. assumed or expense incurred under the policy because of such bodily injury or
' \,,,,,/ property damage as designated on the reverse side of this endorsement.
- 3. It is igreed that the effective period of this endorsement is to the close of December 31st of the Calendar Year designated in the caption above, or to the time of the termination or cancelation of the policy, if sooner.
(over) i 3 M D'" *' t this Endorse. , Ja nua ry 1. 147s; 7. ro,m a pan of Policy Na NF-210 12:01 A.M. Standard Time 3,,g . Arkansas Power & Light Company Date o( Isme December 17. 1974 rso By yo,i d.c,s; ,, .y ;c,rq&2r%-
V- V' Generaf Manoner .
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NE-35 (1/1/75) #
Nuclear Energy Liability insurance NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION t'.
Amendment o f Condition 4 Endorsement It is agreed that with r spect to bodily injury or property damage caused after the effective date of this endorsement by the nuclear energy hazard, the figure $85,250,000 stated in Condition 4 of the policy is amended to read $96,875,000.
I V
Efective Deer of this Endow Ja ntra r y 1 _ 147 Ei To foam a part of Policy No NF-71O 12:01 A.M. Standard Tune Issued =a Arlenn aa n Pnupt- K, T.i ch t- Enmnnny Date of Iune da nuarv 10.197's for ,su ribing com nics V O By l
} 'WA%
V' General Manager
'----- 18 '
- p. CountersianedA_ ' ' 'N? f f # -
Nucisar Ensrgy Liability insurance NUCLEAR ENERGY LIABillTY INSURANCE ASSOCIATION INCREASE OF LIMIT OF LIABILITY ENDORSEMENT (After Prior increase)
It is agreed that: 1
- 1. The limit of liability stated in Item 4 of the declarations as amended by the increase of Limit of Liability EndorsemenL(s) listed below is further amer.ded to read $96,875,000. This amended limit applies with respect to obligations assumed or expenses incurred because of bodily injury or property damage caused, durir.g the period from the effective date of this endorsment to the date of termination of the policy, by the nuclear energy hazard.
- 2. The original limit of liability stated in Item 4 of the declara-tions, the limit (s) of liability stated in the Increase of Limit of Liability Endorsement (s) listed below and the amended limit of liability stated in paragraph 1 above shall not be cumulative, and each payment made by the cmpanies af ter the effective date of this endorsement for any loss or expense covered by the policy shall reduce by the amount of such payment the limit of liability originally stated in Item 4 of the declarations, the amended limit (s) of liability stated in the Increase of Limit of Liability Endorsment(s) listed below and the amended limit of liability stated in paragraph 1 above, regardless of which limit of liability 9 applies with respect to the bodily injury or property damage out of which such loss or expense arises.
Previous Increase of Limit of Liability Endorsment (s)
Endorsement No(s): 14 E d
_, March 21, 1975 To form a part of Policy No 12:01 A.M. Standard Tune hsued - Arkansas Power & Light Company
%gw March 21, 1975 For ,suucribing com nies 1
o .
By } %
V' General Monoger '
ICl" WcEN & rCCCIATES 19 L'/ V r"- -- - - t No Coutmigned l>y U- AL dl V/ IM /:-
s N
F Nuclear En:rgy .Linbility insurance NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION D
T..
ADVANCE PREMIUM AND STANDARD PREMIUM ENDORSEMENT Calendar Year 1975 It is agreed that Items la. and Ib. of Endorsement No. 17 are amended to read:
. la. ADUANCE PREMIUM: It is agreed that the Advance Premium l due the companies for the period designated above is:
l 3
166,941.20 I
lb. STANDARD PREMIUM AND RESERVE PREMIUM: In the absence of a change in the Advance Premium indicated above, it is-agreed that, sub' ject to the provisions of the Industry Credit Rating Plan, the Standard Premium is said Advance Premium and 124,550.31 the Reserve Premium is: $
Additional Premium: $5,741.20 Efective Date d e Endo m
- January 1, 1975 ro go,m a part of Policy No 12:ot ' A.M. Standard Time
, -Arkansas Power & Light Company I
Date of hue March 21, 1975 Toa the si i ains compa i I
v By 11 1 '
General Manager REGS;%;LN & /.SSOCIATES -
20 '
Endommunt No auntminned W '/~ / > / /.
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WM ' c u u.u s _ -______- +2_ \
.___. . - . . . . . - . . . . __ - _____--___-___-__-_-_u
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Nuclear Energy Liability insurance NUCLEAR ENERGY LIABillTY INSURANCE ASSOCIATION 3
ADVANCE PREMIUM AND STANDARD PREMIUM ENDORSD1ENT Calendar Year 1974 It is agreed that Items la. and Ib. of Endorsement No.
are imended te read:
la. ADVANCE PRDtIUM: It is agreed that the Advance Premium due the companies for the period designated above is:
$ 68.648.00 .
lb. STANDARD PREMIUM AND RESERVE PRD11UM: In the absence V: of~a change in the Advance Premium indicated above, it is agreed that, subject to the provisions of the Industry Credit Rating Plan, the Standard Premium is said Advance Premium and the Reserve Piamium is: $ 50.022.73 Return' Premium: $11,750.94 71:l ?. In to errtify t h i t t h ' .' ' a trine copy of the origin 91 Er .!o r.iex'.t 1 r.v li..; t b: t orlo: .9er. i . t. i.L .ir r an l being Inade prit t
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Efective Date of ~
.this Endorsemcoe Tapuagu 1 1074 To form a part of Policy No >
NF-210 12.0L A.MI$undarddtne Issued ta _A PIr o n g p_ g peggg._&_Li@ht Company te of Issue Apv41 7 1975 For the subscribing companies 1
BY__( N '
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D /llnLll/W__1__
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Nuclear Energy Liability insurance NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION AMENDMENTS OF DEFINITION OF " NUCLEAR ENERGY HAZARD" AND PART OF CONDITION 4, _" LIMITATION OF LIABILITY; COMON OCCURRENCE" (Indemnified Nuclear Facility)
It is agreed that:
- 1. In Insuring Agreement III. "DErINITIONS", solely with respect to an
" insured shipment" to which this policy applies as proof of financial protection required by the Nuclear Regulatory Connission Subdivision (2) of the definition of " nuclear energy hazard", as amended, is further amended to read: ,
(2) the nuclear material is in an insured shipment which is away from any other nuclear facility and is in the course of transportation, including the handling and temporary storage incidental thereto, within (al the territorial limits of the United States of America, its territories or possessions, or Puerto Rico; or (b) international waters or airspace, provided that the nuclear material is in the course of transportation between twc points located within the territorial limits described in (a) above and.
there are no deviations in the course of the transportation for the purpose of going to any other country, state or nation, except a deviation in the course ot~ said transportation for the purpose of going to or returning from a port or place of refuge as the result of an emergency.
- 2. Subdivision (b) of Condition 4. " LIMITATION OF LIABILITY;.COMON OCCURRENCE",
l as amended, is replaced by the following:
(b) source material, special nuclear material, spent fuel, waste, or tailings or wastes produced by the extraction or concentration of uranium or thorium from any ore processed primarily for its source material content
- in the course of transportation for which insurance is afforded under this policy and also arising out of such properties of other source material, special nuclear material, spent fuel, waste, or tailings or wastes produced by the extraction or concentration of uranium or thorium from any ore processed primarily for its source material content in the course of transportation for which insurance is afforded under one or more other Nuclear Energy Liability Policies (Facility Form) issued by Nuclear Energy Liability Insurance Association.
E,$'7o,"Ni .1annarv 1. 10 0 To form a part of PoHey No NF-210 issuesto ARKANSAS POW b II$}i Y" ,
Date of issue December 17, 1981 For m . cribias e panies my J 47 R saeor m (1f1/82) ai =o cooni.e.i SAMEN o1-,
'/ ' ' " '" ~ ~-' INSUNf**V.
, _d/,J
/
Nuclear Energy Liability insurance NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION ADVANCE PREMlUM AND STANDARD PREMlUM CALENDAR YEAR 1982 ENDORSEMENT
- 1. ADVANCE PREMIUM: It is agreed that the Advance Premium due the companies for the period designated above is:
f
$ 331.703.87 .
- 2. STANDARD PREMIUM AND RESERVE PREMIUM: In the absence of a change in the Advance Premium indicated above, it is agreed that, subject to the provisions of the Industry Credit Rating Plan, the Standard Premium is said Advance Premium and the Reserve Premium is:
$ 249.769.94 .
e Effective Date of NF-210 this Endorsement January 1,1982 To form a part of Policy No 12:01 A.M. Standard Time issued to ARKANSAS POWER & LIGHT COMPANY Date of issue naramhor 17. 1981 For the su scribing co panies I
\
f By
/U~ General Manager Endorsement No 48 Countersigned by /
r : m v. , w i. e n n
iL .
W5
& Nuclear Energy Liability insurance E NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION r
w '
E CHANGES IN SUBSCRIBING COMPANIES AND IN THEIR PROPORTIONATE LIABILITY ENDORSEMENT B Calendar Year 1982 h
h- 1. It is agreed that with respect to bodily injury or property damage caused, during the
{ effective period of this endorsement, by the nuclear energy hazard:
k a. The word " companies" wherever used in the policy means the subscribing companies y listed below.
- b. The policy shall be binding on such companies only.
- c. Each such company shall be liable for its proportion of any obligation assumed or e'xpense incurred under the policy because of such bodily injury or property k damage as designated below.
- - 2. It is agreed that the effective period of this endorsement is from the beginning of the effective date of this endorsement stated below to the close of December 31, 1982 or to the time of the tennination or cancellation of the policy, if sooner.
sus 5Calglas CStamit5 PROPORTION OF 1005 Aetna Casualty and Surety Co.. The.151 Farmington Ave. Martford. CT 061 % 9.957349 Aetna insurance Campany, 55 Cle St.. hartford, CT 06115 3.153160 Aff t11stad FM Imigrance Co.. Allendale Park. P.O. Son 7500. Johnston SI 02919 0.248934 Allianz lasurance Cmeany 6435 W1lshire 81,d.. Les Angeles. CA 90054 1.327647 M1 state Insurance Co.. Allstate Plara South . $1. Rorthtrook. IL 60062 4.978675 herican name Assurance Co.,102 Noteen Lane. Rew Tark, af 10005 0.871268 American Notertsts lasurance Co.. Long Grove. IL 60049 0.414490 Ottaantnous Cas4alty Corporation. 320-18th 5t.. Rock Island. !L 61201 0.414890 Centennial las6rance Co.. Atlantic Bu11 din 9. 45 Ws11 Street. New fort, af 10005 0.244934 Commercial Union lasurance Co.. One Beacon St. Boston. MA 02108 3.319116 c- Obanecticut indsmity Company. The 9 Farm Spef ags Ad.. Farmingtoe. CT 06032 0.414890 C Continental Casualt,y Co. CNA Plata. Chicago. IL 60685 4.14a895 Continental lasurance Co.. The. 80 Malden La.. asm fort. EY 10038 7.675457 Federal Insurance Co. 51 John f. tennedy Partway. Short utils, hJ 07078 3.493602 Firemen's Find Insurance Campenfes. P.O. Bos 3395. San Francisco. CA 9s11 9 5.310566 Generst Accident Insurance Campany of America. 414 Walnut St.. Philadelphia. PA 19105 1.327647 Manover Insurance Co.. The. 440 Lincola St.. Worcester. MA 01605 0.497867 Mortford Accident and Indsanity Co.. Martford Plata. Martford. CT 06115 7.053122 Nortford 5 team totier Insp. 8 las. Co.. The. M Prospect St. hartford CT 06102 0.497867 highlands Insurance Co. 600 Jefferson 51.. Nouston. TI 77002 0.414890 Meme IMannity Co. The. 59 Maiden Lane, how fort. NY 10038 3.651028 Insurance Co. of North America. P.O. Son 7720. Philadelphia PA 19101 1.659558 monarch Insurance Co. of Chie. The.19 Rector St. nom Tork. RY 10006 0.331912 horthern Insurance Campany of Ass brt. P.O. Bos 1228. Saltteore. NO 21203 2.240404 tertsusestern estional Ins. Co. 131 As. Jachsen St. Alleeuaee. WI 53201 0.663823 Shio Casualty Insurance Company. The.136 Rorth Thtre St. hamilton. 94 45025 0.1659%
Pactf tc ladamatty Co. 51 John F. Eannedy Portmay. Short Mills. IU 47078 0.331912 Peerless Insurance Co. 62 Maple Ave.. Isone.131 03431 0.124467 Protective Insursace Co. 3100 mm. Nortdian St., ladfanapells. IR 46208 0.240934 Providence tenshingtsa lasurance Ca. 30 Isoshington Place. Providence, al 02903 0.1659 %
Reliance Insurance Casteny. 4 P:;me Canter Plans. Philadelphia. PA 19103 0.995735 heyel lasurance Campany of America.150 W111 tan Street. New fort, af 10038 3.319116 5t. Paul Fire 4 marine Ins. Co., 385 unshington St. St. Paul. ful 55102 4.699969 Sesteerd Surety Co. 90 Willian 5t. aus fort. NT 10018 0.1659M State Fare Fire & Casus 1ty Campany.112 Cast lesshington St. 81osetngton. IL 61701 0.829779 Transameri a Insurance Company. P.O. Osa 54256. Les Anttles. CA 90054 0.829779 Travelers Indeuilty Campany. The. One faser Senere. Martford. CT 06115 10.787128 United States Fidelity and Guaranty Ca. 100 Light St.. Baltimore. NO 21202 10.455217 07960 3.119116 United turicyprance States Fire.
C ..Insurance Co.. P.O.ad.,
In n.. m.rtintaie Osa%. 2387.
il 60Norristown.
m RJ i. faut Effective Date of this Endortement s)anuary l .1982 To form a part of Policy No. NF-210 12:01 A. M. standard Time
~
15ued to Arkansas Power & Light Company For the su ribing com, ie5 Date of issue March 5.1982 By I A F~ General Manag8r idBSANEN INSURANCE s
Endorsement No. 49 Counter 5igned W Ild a m-sa 1 - ' -ww wry . e y -j C
f a.ms
Nuclear Energy Liability Insurance NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION ADVANCE PREMIUM AND STANDARD PREMIUM ENDORSEMENT CALENDAR YEAR 1981 It is agreed that , Items la. and Ib. of Endorsement No. 44 are amended to read: .
la. ADVANCE PREMIUM: It'is agreed that the Advance Premium due the companies for the period designated above is: $ 284,410.43 .
Ib. STANDARD PREMIUM AND, RESERVE PREMIUM: ,
In the absence of a change in the Advance Premium indicated above, it is agreed that, subject to the provisions of the Industry.
Credit Rating Plan, the Standard Premium is said Advance Premium and the Reserve Premium is: $ 213.826.93 . ;
Return Premium: $24,613.17 .
l tf.'is or men, January 1. 1981 To form a part of Policy No NF-210 12:01 A.M. Standard Time issued to Arkansas Power & Light Company Date of issue April 20, 1982 For the s scribing cor panies By L
/F' General Manager r
REESAMEN INSURANC'E Endorsement No 50 Countersigned by A4 - . V/ w[
NE-35 W"*P
- l, Noeleer Energy Liability insuranee NUCLEAR ENERGY LIABILITY INSURANCE ASSOCIATION Amendment of Address Endorsement it is agreed that item 1 of the Declaration, " Address" is amended to read:
Address: c/o Middle South Services, Inc.
P.O. Box 61000 New' Orleans, LA 70161 b
- t Effective Date of .y this Endorsemen, October 13, 1982 .
To form a part of Policy No 12:01 A.M. Standard Time issuedto Arkancac Pnw r r. Llaht Company Date of Issue October 18, 1982 For the su cribing c panies gy j hiEBSAMEN INf*"*!Ahe*'
Endorsement No 51 countersigned by gy 8,bC
_ - _- -__- - - - - -_ - - _ -_ 1 --_-
i-...
't- Nuclear Energy .Lialnlity " Insurance-
} -NUCLE AR ENERGY LI AlllLITY INS'URANCE ASSOCI ATION ADVANCE PREMlUM AND STANDARD PREMlUM CA ENDAR' YEAR 1983
~
ENDORSEMENT ,
- 1. ADVANCE PREMlUM: It 'is agreed that' the Advance Premium 'due the companies for the period designated above is:
S- 327.902.50 .
- 2. - STANDARD PREMlUM AND RESERVE PREMlUM:. In the absence of a change in . -
the Advance Premium indicated above, it is agreed that, subject to the provisions of' the industry Credit Rating Plan.- the Standard Premium is said Advance Premium and the Reserve Premium is:
S' 246.880.90 .
w
\
Effective Date of ThX Endorsement January 1,1983 To form a part of Policy No. NF-210 12:01 A.M. Standard Time issued to Arlennenc Pnver & T.ight._ Company
- Date of issue December 15. 1982 For the s ;cribing com anies
-) /
By ifA F.u.g r n..,a;;,
- ,.a. ; ~ r ,<. General
. . - - Manager
- Endorsement 'No. 52 Countersigned by ' / t b
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NUCLEAR ENERGY LIABILITY INSURANCE MUTUAL ATOMIC ENERGY LIABILITY UNDERWRITERS j AWANCE PREMI1M ENDORSEMENT
[ STANDARD PREMItM ENDORSEMNT and Calendar Year 1982
- 1. A WAMCE PREMIUM It is agreed that the Advance Premium due the companies for the calendar year designated above is $ 96,301.13 .
- 2. STANDARD PREMIIM AND RESERVE PREMI1M -
In the absence of a change in the Advance Premium indicated above, it is agreed that, subject to the provisions of the Industry Credit Rating Plan, the Standard Premiu's and Reserve Premium are:
Standard Premium $ 96,301.13 .
Reserve Premium S72,513.86 .
Effective Date of .To form a part this Endorsement January 1, 1982 of Policy No. MF 74 Issued to Arkansas Power & Light Company
'. Date of Issue January 6, 1982 Por the Subscribing Companies MTfUAL ATCHIC ENERGY LIABILITY UNDERWRITERS By a ggg3At4Et4 IMgugANCE
_f J -
^{
Endorsement No. 41 Countersigned by DY_
AtmlORIZED REPRESENTATIVE
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NUCLEAR ENERGY LIABILITY INSURANCE 6 .
U .
MUTUAL ATOMIC ENERGY LIABILITh UNDERWRITERS AMENDMENTS OF DEFINITION OF," NUCLEAR ENERGY HA7. ARD" AND PART. OF CONDITION -4 . " LIMITATION
- OF LIABILITY: COMMON OCCURRENCE" (Indemnified Nuclear Facility)
- 1t .is agreed that
- 11. In Insuring t.greement III,;" DEFINITIONS", solely with respect to- an " insured shipment" to which' this policy ~ applies as proof of financial protection required
' by the Nuclear Regulatory Commission, Subdivision (2) of the definition of
" nuclear energy hazard", as amended, is further amended to read:
(2)lthe nuclear material is in an insured shipment which is away from any
- other.. nuclear facility and is in the course of transportation , including
- the handling and temporary storage incidental thereto, within
-(a) the territorial limits of the United States of America, its territories
- or possessions, or Fuerto Rico
- or (b) international waters or airspace, provided that the nuclear material is in the course of transportation between two points located -within
~
- the territorial limits described in (a) above and there are no devia-tions in the course of the transportation for the purpose of going to .
any other country, state- or nation, except a deviation in the course of said transportation for the purpose of going. to or returning from a port or place of refuge'as the result of an emergency.
- 2. Subdivision (b) of Condition 4, LIMITATION OF LIABILITY: COMMON OCCUR-
- RENCE" . as amended, is replaced by the follcwing:
~
(b) source material, special nuclear material, spent fuel, waste, or tailings
~ . or wastes produced by the extraction or concentration of uranium - or-thorium from _any ore processed prtmarily for its source material content in. the course of transportation for which insurance is afforded under this policy and also arising out of such properties of other source material,
'special nuclear material, spent fuel, waste, or tailings or wastes produced by the extraction or concentration of uranium or thorium from any ore
= %,
t ie a . . .2 is . ,.- -
. .m,. , ,, , n
2-processed primarily for its source material content in the course of transportation for which hourance is afforded under one or more other Nuclear Energy Liability Policies (Facility Form) issued by Mutual Atomic Energy Liability Underwriters.
Effective Date of To form a part .
This Endorsement January 1, 1982 of Policy No. MF-74 12:01 A.M. Standard Time 1: sued to Arkansas' Power & Licht Company Date of Issue Feb'ruary 1, 1982 For e Subscribing Companies By Endorsement No. 42 Countersigned by 8M d. b nCESAMEN INSURANCE g._,
& &= 2 N ^ ^g"
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Page 2 of 2 ME-58
...a e-NUCLEAR ENERGY LIABILITY INSURANCE MUTUAL ATOMIC ENERGY LIABILITY UNDERWRITERS
- 1. AMENENENT T AD/ANCE PRDillM INDORSD1ENT
- 2. STANDARD PREMILM AND RESEIETE, PREMIIM ENDORSENENT
- 3. REmBN PRDGIN DUE
- 1. Advmoe Premim It is agreed that the Amended Advance Premim due the espanies for the calendar year 1981 is $82.570.77 .
- 2. Standard PImium and Reserve Preium Subject to the provisicms of the Industry Credit Rating Plan, it is agreed that the Standard Premim and Reserve Premium for the calendar year designated above are:
Stadard Premim $82.570.77 Reserve Premim ~ $62.078.78
- 3. Return Premian $7,145.73 .
Effective Date of 'Ib form a part i
this Endors ment January 1, 1981 of Policy No. MF-74 Issued to Arkansas Power ~& Light Company l
l Date of Issue April 20, 1982 Ibr the Subscribing campanies
( MHyE A'KNIC I!NEIGY LIABILITY 'm6 By 1 $ C[.
k ya A
REBSAMEN INSURANC Endors ment No. 43 Countersigned bysav # 23 = >d . ow autnorneo % a ..
ME-36 l
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NUCLEAR ENERGY LIABILITY INSURANCE j MUTUAL ATOMIC ENERGY LIABILITY UNDERWRITERS l
Amendment of Address Endorsement l
lt is agreed that item 1 of the Declarations, " Address" is amended to read:
l Address: c/o Middle South Services, Inc.
P.O. Box 61000 New Orleans, LA 70161 0
To form a part ENective Date of of policy No .MF-74 this Endorsement October 13. 1982 Arkansas Power & Light Company leeue to October 18, 1982 Date of Issua For the Suliscriliing Conipanics MI 'UAI, ATOMIC ENEllGY I,IA til,lTY tl )EftWillTEfts ity ; ll' d. & ll0 s RENA EN INSURANCE E,, . le ,_, .... , t N. . .
44 -.
- c. iiiiimigii...Miy EY n #d
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NUCLE'A ll ENERGY LI AUll.1I Y INSUHANCEL MUTUAL ATOMIC ENERGY'LIAlllLITY UNDEHWHITERS
' ADVANCE PREMlUM 'AND STANDARD PREMlUM CALENDAR YEAR 1983 ENDDRSEMENT .
- 1. ' ADVANCE PREMlUM: it is agreed that the Advance Premium due the compames for ' the period designated above is:
S. 95,197.50
- 2. ' STANDARD PREMlUM AND RESERVE PREMlUM: In the absence of a change in the Advance Premium indicated above, it is agreed that, subject to the provisions of
, the industry Credit Rating Plan, the Standard Premium is said Advance Premium and the Reserve Premium is:
S;7L 675.10 4
r
- Effective Date ol'-
-~ Th5 Endorsement January 1,1983 To form a part of Policy No. MF-74 12:01 A.M. Standard Time -
Issued to ArknnSaS_.fDWer AiLight Comoany
. Date of issue December 15, 1982 For the s triliig co min l
BY blh Y
, Ger}e,ral Manager End;rsement No.- 45 Counte< signed by > _'f/
m.
F~ " ~ ~-
~ ' 5'b * ~,
UNITzo =,: srs
- 'N. / , ATOMIC ENERGY COMMISSION I/f'i * '
WASHINGTON. D.C. 20545 k . ; .!C . i,;!
%&lE Docket Nos. 50-313 50-368 -
AMENDMENT TO INDEMNITY AGREEMENT NO. B-65 AMENDMENT NO. 2 Effective UAY % 1374 , Indemnity Agreement No. B-65, between Arkansas Power and Light Company and the Atomic Energy Commission, dated November 8,1972, as amended, is hereby further amended as follows:
Item 2a of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefor:
Item 2 - Amount of financial protection
- a. $1,000,000 (From 12:01 a.m. , November 8,1972, to 12:00 midnight, MAY 2 0 1974 ,
inclusive)
$110,000,000 (From 12:01 a.m., MAy 21-wsn7,, )
Item 3'of the Attachment to the indemnity agreement is deleted in its entirety and the following substituted therefor:
Item 3 - License number or numbers SNM-1321 (From 12:01 a.m. , NovembgY 8 1972 g u 197,; to 12:00 midnight, 6 _,
- - - e inclusive) - -
DPR-51 (From 12:01 a.m., MAY 211974 )
.~. .
Item 5 of the Attachment to the indemnity agreement is amended by adding the following:
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NuclearEnergyLiabilityPolicy(FacilityForm)No.-MF-74 issued-by Mutual Atomic Energy Liability Underwriters.
FOR THE UNITED STATES AT0iJIC ENERGY COMMISSION' f^
s derome Saltzman, Dep y Chief Office of. Antitrus Indemnity Directorate of Licensing
{: *- s :
Accepted May 23 ,1974
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By
-- ." / ., . ,n ARKANSAS PO',iER AND LIGHT COMPAfiY
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