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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] |
Text
.. .. - . .
e_-~ E ntergy P o-l x
. Operations 1_._____ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ _ _ _ _ . .
April 30, 1992 2CAN049208 U. S. Nuclear Regulatory Commission Document Control Desi-Mail Station P1-137 Washington, DC 20555 Subj ect: Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NFP-6 Submitting Audition.21 Information Concerning the First Ten Year Inservice Inspection Relief Requests (TAC No. M76001)
Gentlemen:
In letter 2CAN088915, dated August 31, 1989 Entergy Operations submitted relief requests for Arkansas Nuclear One, Unit 2 (ANO-2) for the first 10-year interval. These requests were for relief ftom certain ASME Section XI Inservice Inspection (ISI) requirements because only limited
( examinations could be performed. The NRC subsequently requerted l additional information concerning these relief requests in letter dated Septa.mber 10, 1991 (2CNA099102). In letter dated February 13, 1992 (2 car 029202), Entergy Operations stated that ANO-2 was unable to provide the soecific infarmation requested but committed to submit a best estimate of the percentage of the Code-required coverage. The purpore of this submittal is to provide these best estimates for the coverage.
l The Code required coverage was estimated and placed into four categories.
These categories are 0 to 25%; 26 to 50%; $1 to 75%; and 76 to 100% of the Code required coverage of the weld. Attached is a listing of those welds that fell within the first, second, third, and fourth category.
respectively.
l l
The attachment also provides additional information, including items such as a description of the examination area, examination volume and/or area, the category of the weld, and the method used to perform the examination.
Based on further review, there are several welds in which the Code required coverage was considered to be met. These welds are those identified by 100% in the attached list. It is Entergy Operations' conclusion that NRC relief is no longer necessary and the relief for those welds is herewith withdrawn.
9205050310 92 A30 <
PDR ADOCK 05000368 0 PDR l 1
' U.-S. NRC April 30, 1992
( , Page 2 L This submittal provides - the information necessary for the NRC to complete-its review of the ANO-2 first 10-year interval limited examinatien relief requests. Should you have any questions regarding this issue, please contact me.
Very truly yours, M' cav James [J.Fisicaro ,
Director Licensing JJF/RWC/sjf Attachment ~
cc Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV_
'611 Ryan PlazaLDrivo, _ Suite 400 Arlington, TX 76011-8064
.NRC Senior _ Resident Inspector
-Arkansas: Nuclear One - ANO-1 & 2
' Number 1. Nuclear Plant-Road Russellville, AR 72801 Hr.' Thomas W. Alexion NRR Project Manager, Region '1V/ANO-1 U S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 i
'One White Flint North i
=11555 Rockville P84e Rockv8.11e, Marylana 20852 Ms. Sheri Peterson
'NRRLProject Manager, Region IV/ANO-2 U.-S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 Ont White Flint' North--
11555'Rockv111e Pike Rocks 111e,. Maryland 20852 L
L lt ._
. s OtQQM ESe :fL20-1 ANO-2 UMITED ISI EXAMINAT10N COVERAGE EST1 MATES FOR FIRST INSPECTION INTERVAL EXAMVOLUME AFKVOR AREA ESTIVATED COVERAGE %
ISI NO. h CATATEMNO. REMNtKS COMPONENTIDENTIFICATION METHOD (S) REASON FOR EXAM: NATION UMiTATION RFOs EXAMINED 0 25 N50 51-75 75-100 .
EXAMINATION AREA DESCFtIFTION EXTENT Code oniy requrres 5% of weld ler.gth 01412 BA'B t.1 Weld Metal + %t Base Metal Surveinance Capsule Ho! der / Attented 100% per Reg Guide 1.150 Reactor Pressure Vesset Vof for Bentine Region.
tower Shelf to Middle Shet Weld 5% 2R62R7 Code on8y requires 10% of weed 01409 B A'8 I .1 Weld Metal + %t Base Metal Surveillance Capsule Holder / Flow Skitt / le,gth. Attempted 100% per Reg Reactor PressureVessel Vol Guide 1.150 for Betthne Reg:en.
Lower Shell Longitudinal Weld @ S0
- 10% 2R6/2R7 Code only requires 10% of weid 01413 B A'B1.1 Weld Metal + %t 6ase Metal SurveiItance Capsule Holder / length. Attempted 100% per Reg Reactor Pres 2re Vessel Vol Guide 1.150 for Bettline Region.
Middle Shet Longitudmal Weld @ 90
- 10% 2RM/2R7 Flow skrt is not noted in data as 01401 B-B/B12 Weld Metal + %1 Base Metal 100 % causstg scan Mation. Fut Code Reactor Pressure Vess21 Vot See Remarks coverage achieved. Rehef ret Bottom Head Dome to Peel Segment Torus 5% 2R6 necessary.
01C08 B B/B12 Weld Meta! + % t Base Metal j Flow Baffle Assembiv /
Heactor Pressure Vessel Vol '
%ttorn Head to Lower Shell Weld 5% 2RS 01416 8 B/812 Weld Meta! + M Base Metal '
Nonfes /
Reactor Pressure Vesse' Vol Middle Shell to Upper She# Weld 5% 2R6/2R7 01417 B-B/B12 Weld Wta! + %t Base Metal Nontes /
Reactor Pressure Vessel Vol Upper Shen Longitudinal Weld @ 90
- 10% 2R6CR7 01-018 B B/812 Weld Meta l + %t Base Me.af Nonfes /
Reacto- Pressure Vesse! Vol Upper Shell Longitudinal Weld G 210
- 10% 2RS/2R7 01419 B-B/B1.2 Weld Metat + %t Base Meta!
/
Reactor Pressure vessef V.,i Nonies Upper Sheif I wigitudinal Weld @ 330
- 10% 2R6/2R7 Co+ rWy requ?es 10% of weld 01402 B-B/B12 Weld Meta? + %t Base Metal 100 % length. Code ccverage ached on l,
Reactor Pressure Vesset Vo! See Rema Ks 27% of weld langth. Hehet not Peel Segment to Peel Segment @ 30
Code on8y requires 10% of weid 01403 8-B/B12 Weld Metaf + wt BaseMetal 100*, teng*h. Code coverage achieved on Reactor Pressure Vessel Vol See Remarks 27% of weld length. Re!ief not Peel Segment to Peel Segment @ 90
(3) Distributed uniformly amor g three areas eound vesselcircumference (1) "t'of shett or head (2) it of Main Pipeng Run/2* Branch Run (4) 21 of Pipmg71 of Support AttachmentMember ("t'of support)
m
- s ESP 92220-2 OVJ0r92 AP10-2 URRITED ISI EXAhmNATION COVERAGE ESTIRRATES FOR FWISTINSPECTION sNTERVAL i IS' NO. CAT / ITEM NO. EXAM VOLUhE ANDOR AREA ESTIMATED CoraPAE% ~
l COMPONENTOENTFICATION METHOO(S) REASON FOR EXAMINATIONtNITATION IEMARAS
- EXAMINATION AREA DESCRIPDON EXTENT ' ffOs EXAMINED Os 2fMio 5t-75 75-100 .
l 01-004 B-B/B12 Weld Metal + %t E,ase Metal Code only requires 10% of weld .?
Reactor PressureVersei . Vol Sae Remarks 100 % leng*h. Code coverage actneved on Peel Segment to Peel Segment @ 150
- 10% - 2R6 27% of weld length. ReEef not l
! necessay.
- B-B/B12 Weld Meta! + nt Base Metal Code enfy requires 10% of weld l Reactor PressureVessel Vol ' . See Remarks 100 % 8=ngth. Code coverage achie.ved on Peel Segment to Peel Segment @ 2.0
- 10% 2R6 27% of wead length. Remef not
~
01-006 B-B/B12 - Weld Metal + % t Base Metal Code only requires 10% of weld ;
- Reactor PressureVessel Vol See Remarks tW5 length. Code coverage ochieved on Peel Segment to Peel Segment @ 270
- 10% 2R6 27% of we8d length. Rehet not !
l ._ .
"'C'55'"I-01-007 B-B/B12 WeM Meta! + %i Base Metal Code onfy requees 10% of weld Reactor Pressere Vessel Vol See Remarks 100 % lengtts. Code coverage achieved on Peel Segment to Peel Segment @ 330
- 10% 2R6 27% of weld lengt*t. Relief not necessary ,
01422 BC/Bt4 Weld Metal + %t Base Metal (1) Examination limited for nozzfe bore !
Reactor PressureVesset Vol End of Nozzle Bore / scanmng only. Shell not Emited. l 4
Inlet Nozzle to Shell @ 60 * ?00% 2R6/2R7 i
ic 01423 BO/B1.4 Weld Meta! + %t Base Metal (t) Ceranstaor:Emited for nozzle bore j j Reactor Pressure Vessel Vol End of Nozzle Bore / scanrang orff. Sher not Emited. ;
Inlet bioloe to Sher @ 120- 100% 2RS/2R7 01-025 B0/81.4 Weld Metai + %t Base Metal (1) Exammaton Smited for nozzle twre Reactor PressureVessel Vol End of Nozzle Bore / scanning or+f. Sher notlimited. l J, tolet Nozzle to Sher @ 240
t j 01426 BOlB1.4 Weld Metal + %t BaseMetal (1) Examnation Emited for nozzle bore !
Reactor Pressure Vesset Vol End of Nozzie Bore / scaqrung only. Sher notimited.
i inlet Nozzle to Sher @ 300
!' 01421 B0/81.4 Weld Metal + bt Base Metal (1) TM wald was prevousVrcorrect!y l' Reactor PressureVesset Vol integes! Eviension/End of Nozzle Bore Shet Bore idarQied as01-027 which is not Outlet Nozzle to Shet @ 9* 100 % 2Rti'2R7 Emded. The sher side & nozzle bore scarming coverages are as indicated. f i
01 024 BC/B1.4 Weld Metal + %t Base Metal (1) TI e shet sida and nozzfe bnre Reactor Pressure Vessel Vol integral Extenson/End of Nozzle Bw Shet Bw scanrung coverages are as indica *ed.
Outtet Nozzle to Shell @ 180
- 100% 2RS/2R7 (1) *t'of shellor head (3) Distnbuteduniformly among three areas around v , set orcumference 4 (2) It of Main Piping Rin/2" Branch Run (4) 26 of Piping /21 of Support AttachmentMe r.ber (*t'of support) f
a %
l - ESP 92020-3 : 0%$N ,
- j. ANO-2 UMITED ISI EXAMINATION COVERAGE ESTIMATES FOR FIRSTINSPECTION INTERVAL '
ISI NO- CAT /! TEM NO. EXAMVOLUME AMWOR ANA ' ESTIMATED COWERAGE%
COMPONENT 0ENTFICATKW METHOD (S) REASON FOR EXAMINATIONIDMTATION REMARMS EXAMINATION AREA DESCRIPTION EXTENT RFOs EXAMINED C'27 :4 50- 51J5 75-100 ,
01-L443' B 4 1/81.9 FLs between Threaded Stud Holes
- The limitation prenoush reported was Reactor PressureVessel Vol See Remarks 100 % for a nonremovable obstrucconat the Vesse'F:ange Ligaments 2R1 bottom 2* cf the stud hole. This is l 100% ;
outside the examinate stAsme of the
!!ange ligaments. The flange q ligaments were luny exstraned. ReGet
- st necessary. .rt 02401 B-C/B t.3 + e.-;d is
- 4t Base Metal i Reactor Vesset Closure Head Vol r c.g i,9 i ge Configuration /
f Flange to Peel Segment Torus Weld 100 % ee4. "-'
03402 B-B/B3.1 Weid Metal + % t Base Metal Stay Cylinder Base to Lower Pead Vol Blend Radius /
Steam Generator 2E24A 5% 2R2
. 03003 B-B/B3.1 Weld Metal + 41 Base Metal Peel Segme it to Ped Segment @ 60
l, Steam Generator 2% 10% 2R2 i t
03404 BB,B3.1 Weid Metal + %t Base Meta 8
$i Steam Generator 2E24A Vof Nozzle l / l j- Peel Segment in Peel Segment @ 138
j j 03405 B-B/B3.1 Weld Metal + %t BaseMeta:
S'eam Generator 2E24A Vol Nozzle - / ;
Peel Segment to Peel Segment @ 210
l 05 009 BO/B22 Weld Metal + %t Base Metal (1)
- Pressurizer Vol Heater Penevatier.s J l 12* Surge Nozzle to Bottom Head 100% 2R1 '
I 4
l 05-010 BO!B2_2 Weld Metal + %t t t,e Metal gt)
! Pressurizer Vol Nozzles I /
4* Spray Nozzle to Top Head 100% 2R2 l I" 05420 B0/B22 Mozzle hside Radiused Section I f, Pressurizer Vol Heater Bundles / ',
12" Surge Nozzle inner Radius Section 100 % 2R1 i.05-121 BC/B22 Nozzie Inside Radiused Section i, Pressurizer .
Vol Nozzfes /.
[, 4* Spray Nozzle ir.ner Radius becLon l 100 % l2R2 [
- i j.
(1) *t of shellor head (3) Distributea uniformfy among three aress arour=d vessel crcumference (2) 1t of Main Piping Run/2* Branch Run (4) 21 of Piping?t of Support AttachmentMember ('t'of support)
' ESP 9202G)4 - 0%b '
ANO-2 URAITED ISI EXAAAINATION COVERAGE ESTIARATES FOR FIRSTINSPECTION INTERVAL
. ISI NO. CAT / ITEM NO. EXAM VOLUME APOOR AREA ESUMATED COVERAGE %
COMPONENTIDENDRCADON MED00(S) REASON FOR DAMMDON LMTADON REMNWS EXAMINADON AREA DESCRIPDON EXTENT RFOs EXAMINED 025 26M 51-75 75-100 . ,
_p 05-122 BOlB22 Nozzle inside Radiused Section .
I Presrewizer Vol ' insulation Bracket. IM Luc. Nozz!e /
6* Saiety Nozzle inner Radius Secten @ 0
- 100% 2R4 08-0?4 . Bf/B4.1 Weld Meta! + %t Base Metal I
Reactor Coolant (2CCA-5-30-). VrAsur Insutation Support Brackets /-
Elbow to Safe End Cacumferen'ialWold 100 % 2R1/2R2 L C8015 BJB4.5 Weld Metal + %1 ~ ase Metal 1
Reactor Coolant (2CCA-5-30*) Vol Insulation Suppor. Brackets /. i l Safe End to Pump CircumferentalWeld 100% 2R2
?. 09409 BJB45 Weld Metal + % t Base Metal
- Reactor Coo' ant (2MA4-30*) Vol Insalation Support Brackets /
1 Pump to Safe End LacumferentialWeld 100% 2R2
, 24049 BJP ? 5 Weld Metal + %t BaseMetal A 1%V calibration enabled fut two-l Safety injection (2CCA 23W) Vel See Remarks - 100 % drectionalamal coverage to %
4 Reducer to Tee CircumferentalWeM 100 % achraved from reoucer sde.
f 2R6 Circum ao u e; coverage also attained.
j i
Re6ef not nu.a.f. ;
25-01 B-JU4:5 Weid Metal + %t Base Metal No asial scan p," .M due to
? Shutdown Coohng (2CCA-25-14") Vol Hanger Support Bracl et / hanger support tracket and tee j Tee to Pipe CircumferentialWeld 100% 2R6 con 5guraten.100% crcumferentan c scan vu.wn m ,
4 l i 15-10 BJB4.6 Weld Metal + %t Base Metal (2)
} Reactor Coolant (2CCA-1040') Vol . Cable Wnip Restrarrt / l l
12* Branch Conrection [ 100 % 2R6 '
l 03030 C-NC1.1 Weld Metat + %t Base Metal r3)
Steam Generator 2E24A Vol Insulation Suppmt Reg /
Intermediate Sheti to CcnicalShed 20% 2R2,7R4/2R6 r
03431 C-NC1.1 Weld Metal + %t BaseMetal (3)
Conical SheG to Upper Sheft Vol Insulation Support RingA-Besm /
Steam Generator 2E24A 20%
}H2/2R47R6 i
03 032 C #C1.1 Weld Metal + t Base Metal (3) I
, Steam Generator 2E24A Vol Insulation Support Ring /
t Upper E5eu to Top Head Torus 20% 2R2/2R4/2R6 i i !
03433 C-A/C1.1- Weld Metal + %t Base Meta! (3) !
) Steam Generator 2E24A . Vol insutaten Supports / l l Top Head Torus to Top Head Dome 20% 2R2,7R47RS (1) *t'of shellor head - (3) Distributeduntformty amorsg three areas around vesselcrcumference
- 12) It of Main Piping Run/2" Branch Run (4) 2t of Paping71 of Support AttachmentMember (Tof support) 9
~ , ,
. m (
.. ESP 92023-5 OQWEZ mez uumED IS8 EMARANGADON COFRAGE ESDERATES FOR FRST WISPECDON WTERVAh ISI NO. CAT)tTEM NO." EX#MVOt.UME AN[VOR AREA ' ESTIMATED COVERAGE % i COMPONENT 0ENTIFiCADON METHOO(S) REASON FOR EXAMINATIONLIMITATION REMARMS I EXAMINATION AREA DESCR4' DON EXTENT RFOs EXAMIPED G25 2650 51-75 76100 .
j: 03441 . -
C-C/C1.3 ail-de J Weld Metal Steam Generator 2F.24A Sur Insulation Bradet /
4 Snuuber t.ug @ 270* 100% 2RS 4
04430 .
C-A/C1.1 Weld Metal . %t Base Metal (3) '
, Steam Generator 2E249. .
Vol Insulation Support Rrig / '
lotermediate She8 to C.micalSheE 20% 2R2f2R3;*2R5 >
t 04031 . C-A/C*.1 Weld Metal + nt Base Metal p)
Steam G..erator2E248 Vol Insulation Jupport Rir:g / ,
ConicelShell to Upper Shell 20% 2R1/2R3,2R5 04432 C-A/C1.1 Weld Metal + % t Base Metal (3)
Steam Generator 2E24B Vol insulation support Ring ./ ;
Upper Shell to Top Head Torus 20% 2R2/2R3/2RS i 04433 C-NC1.1 ' Weld Metal + %t Base Metal (3) l Steam Generator 2E24B ' Vol insutation Si pports /
Top Head T(,rus to Top Head Dome 20% 2R1/2R3f2RS 50415 GE/C2.1 Weld Metal . %t Base Metal Ebutdown Cooling (2GCB-5-14*) Vol Pipe Support l / l Pipe to Pipe CircumferentialWeld i 100 % 2R2 o
d 56407 CE/C2.1 WeW Meta! + %t Base Metal Welded plate located outside scan Shutdown Cochng(2GCGB4*) Voi See Remarks 100 % area on pipe side. A 1%V cahbraton t Reducer to Pipe CreumferentialWe'd 100 % 2R6 enabled fut two-d6eedonal axiaf f 4
coverage to be achieved from both i j' sides. Circumferentalcoverage also ,
attarwd Relief notnecessary. j 57409 Cf/C2.1 Weld Metal + % t Base Metal instrunwntaten nozzles & lugs located Shutdwn Cooling (2GCB-10-10") Vo! See Remarks 100 % inside scan area on heat exchanger >
, Reduce-to Heat Exchangar Weid 100 % 2.32 side. A 17.V calibration enabled fut 4 tro,.' G ! axial coverage to be .
i achieved from reducer side. -
Carcumferentialcove age also attained.
ReEef ret necessary. *
~~
t L
f f
i l l (1) *t*of she8 cr head (3) Distributed uniformty among three areas around vessel arcumference (2) 11 of Main Piping Run/2" Branch Run (4) 2t nf Pipimf21 of Support AttachmentMember (*t*of support) - !
t' i
im , . v ( , - . . 3 .i r. ._. -- ,. . _ . . , , . , , .-
ESP 92020<, 04h '
ANO-2 USAITED ISI EXAAAINATION COVERAGE ESTIREATES FOR FIRSTINSPECTION INTERVAL -
, ISI NO. CAT / ITEM NO. - EXAM VOLUME AMVOR MEA - ESTMATED COERAE%
COMPONENTIDENTIFICATION METHOD (S) REASON FOR EXAMINATION LIMITATION fEMARKS EXAMINATION AREA DESCRIPTION EXTENT RFOs EXAMWED 0 25 26-50 51-75 75100 .
i' 58411- Cf/C2.1 Weld Metal. %t Base Metal Two betrumentation nonleslocated Shutdown Cooting (2GCB-11-10*) Vol .. See Remarks 100 % adjacent to weld on heat exchanger Reducer to Heat Exchanger Weld 100% 2R2 side. A 1%V calibration enabled fut l twodirac5onal axial coserage to be [
l achieved from reducer side.
Circumferential coverage also attained !
i, wth 1%V calibnMion. Relief not
, necessary.
59 035 C-F/02.1 Weld Metaf + %t Base Metal .
Instrumentation nozzles & lugs located i
. Shutdown Coohng (2GCB-16-10-) Vol See Remarks 10c% insi&_ scan area on heat ed iw
. Heat Exchanger to Elbow Weld 100 % 2R2/2R4 side. A 1%V rafitwation ensbied fut two-directional exial coverage to be !
- achiaved from elbow side. l j- Crcumferential coverage also attaineri ;
- ReGet not necessary. j
. 60 027 CE/C2.1 Weld Meta! + %t Base Metal Two instrumentation nozzies located Shutdown Cooling (2GCB-17-10~) Vol See Remarks 100% adjacent to weld on heat exchanger I l Heat Exchanger to Elbow Weld 100% 2R2 side A 1 %V calibratior. .eabled fut two-direcbonal axial coverage to be achieved from elbow side. !
I. Crcumferential coverage also attained i 4
with 1%V caubration. ReEef rot I
accessary.
j 58003B CJ/C22 Weld Metal + kt Base Metal [
- Shutdown Coolang CGCB-3-12")- Vol Rigd Support Hanger / j j E! bow Outside Long um Weld 100% ER5 i
- 53421A CJ/C22 Weki Metal + %t Base Metal I
!' Safety injaction (2GCB-3-12*) Vol Welded identfication Tag / [
Elbow Long Seam Weld 100 % .2R2
! 55429B Cf/C22 Weld Metal + % t Base Meta' !
i Safety injection (2GCB-7-14*) Vol identibcate Plate / !
j Reducer Long Seam Weld 100%- 2R5 [
4 >
17-024 C-G/C2.1 Weld Metal + %t Base Metal r Feedwater (2088-1-24-) Vol Nozzle / !
Elbow to Pipe CircumferentialWeld 100 % 2RS 19416 C-G/C2.1 Weld Metaf + %t Base Metat I Feedwater (2DBB 2-24") ! Vol Nozzle /Vafve Configuration / I Elbow to Valve CircumferentialWeld l 100% 2R6 1
f
,. (1) "t'of shell or head (3) Distributed uniformly among three areas around vesset circumference I t
(2) It of Main Pping Run/2* Branch Run (4) 21 of Piping 71 of Support Attachment Member (Tot support) 5
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