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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 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) 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 0CAN079015, Discusses Clarification to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Surveillance Sampling Being Performed Monthly & Analyzed Prior to Loading/Releasing Each Load to Russellville Municipal Sewage Sys1990-07-26026 July 1990 Discusses Clarification to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Surveillance Sampling Being Performed Monthly & Analyzed Prior to Loading/Releasing Each Load to Russellville Municipal Sewage Sys 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 0CAN079017, Discusses Amend 8 to Plant Updated Sar.Certifies That Info Amend Represents Changes Made,Per 10CFR50.591990-07-23023 July 1990 Discusses Amend 8 to Plant Updated Sar.Certifies That Info Amend Represents Changes Made,Per 10CFR50.59 0CAN079010, Amends 880616 Response to Violations Noted in Insp Repts 50-313/88-11 & 50-368/88-11 Re Integrated Leak Rate Test. Procedure Rev Postponed & Will Be Incorporated Into Single Rev to Be Completed by 9103011990-07-20020 July 1990 Amends 880616 Response to Violations Noted in Insp Repts 50-313/88-11 & 50-368/88-11 Re Integrated Leak Rate Test. Procedure Rev Postponed & Will Be Incorporated Into Single Rev to Be Completed by 910301 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 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 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 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 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 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 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 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 1990-09-07
[Table view] |
Text
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P. O. Box 551 -i Littie Rock AR 72203 -- '
Tel 501377 4000 )
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December 11,'1989- 1 L'
9CAN128999 p 1 b Di S. Nuclear Regulatory- Commission ,
. Document Control Desk 2 g
Mail' Station P1-137-
' Washington, D. C. 20555 ,
Units 1 and 2
SUBJECT:
Arkansas Nuclear One Docket Nos. 50-313/50-368 J License Nos. DPR-51 and NPF-6 .I Correction to Response to Inspection Report !
50-313/89-42: 50-368/89-42 Gentlemen:
L .Our. letter-of December'4, 1989 (OCAN128901),- contained our response to the subject. inspection report. An inconsistency was discovered on page four of the attachment under question 4. This letter provides clarification of the inconsistency. The last paragraph states, " Identified enhancements to the -
' welding program-as discussed above are expected to be completed by May 1,
.1990." - This sentence should have read, "The review of the welding program as discussed above is expected to be completed by May 1, 1990." The attached response include the subject clarification, which is noted by a side bar.
'If you have any questions, please-call Mr..J. Fisicaro at (501) 964-3228.
Very truly your.,--
E. C. Ewing
. General Manager, Technical Support and Assessment ECE/JDJ/sgw l attachment 1:
1- cc: Regional Administrator l
Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 I
l WI P 'I 8912'200183 891211-PDR ADOCK 05000313
% MM - . _ . _ _ .
e 3- -'Atttchment ' l
. -U S. NRC ;
Page 1--
December 11, 1989' l 4 -i
-Notice of Violation 1
A. Control of Welding Activities 1
Criterion IX.of Appendix B to 10 CFR 50 and the licensee's approved
. quality assurance-plan require that special processes, such as
. welding, be controlled and accomplished by qualified personnel using l qualified' procedures. In the following examples, this did not occur.
- 1. .The travel speed specified on Drawing 2CCB-14-2 for Weld FW18Cl-is 3-10 inches per minute.
Contrary to the above, the welding speeds in use were 2 and 11/2 inches per minute. .
l 2. The Welding Procedure Specification (WPS) for Weld FWIC1 did not i j address the use of demineralized water to quench the weld. ;
Contrary to the above, demineralized water was sprayed on'the weld to expedite cooling below 350* F, the maximum interpass temperature ,
in the WPS. l
- 3. Flare-bevel Welds FW9, FW10, FW15, and FW16 identified on Drawing 2CCC-6-H-2 were specified to be 2 inches of weld 4-inch centers.
Contrary to the above, these welds were accepted although they were made continuously (for 6 inches without break).
This is a Severity Level IV violation. (Supplement II)(313/8942-01; 368/8942-01).
I Response to the Violation
- 1. The reason for the violation: ;
With regard to examples l'and 2, the cause of the violation was the failure of management to clearly communicate expectations regarding
! adherence to the quality requirements built into the program to the weld craftsmen and weld craftsmen supervision.
In example 1, the welder was not aware that the travel speed specification was in the WPS. (As stated in paragraph 3 b of the-Inspection Report, the WPS, not the drawing, is the document containing the travel speed specifications.)
- Concerning example 2, the use of demineralized water as a quenching spray on austenitic stainless steel was an historical construction practice not covered by procedure. The welder was following what he considered to be an accepted practice instead of strictly adhering to l the WPS.
l l'
l~ _. -
a
, Attachment :
U. S. NRC
'Page 2 December-11, 1989 With regard to example 3, the cause of.the violation was inattention to detail by the welder. After completing the welding on a nearly '
identical hanger 2CCC-12-H1 which specified a continuous weld, hs failed to. note the difference in the drawings and welded hanger 2CCC-6-H2 similarly.
- 2. The corrective steps that have been taken:
To ensure that weld craftsmen and weld craftsmen supervision were aware of management's expectations for the conduct of welding activities, training was conducted on October 20, 21, and-22, 1989, which emphasized that the requirements of the WPS must be followed and that circumstances prohibiting WPS- compliance require that work is stopped and the supervisor '
is notified for resolution. Also, supervisors began reviewing each weld package and the WPS with the craftsman before_the job is started. -
These actions were previously addressed in our letter of Octobor 26,
'1989 (9CAN198917).
L Additional training which discussed weld procedure specifications and compliance with these requirements was conducted during the week of November 27, 1989, for plant modifications weld craftsmen and maintenance weld craftsmen.
The " Control of Plant Modification Welding" and " Conduct'of Maintenance Welding" procedures have been changed to state that a copy of the WPS l shall be in the work package at- the work location and that the supervisor l will review the weld packages and the WPS with the craftsEen at the l start of_each shift. The procedures now clearly state that welding 1 specifications will be followed, activities not addressed in procedures L or specifications will not be done, and circumstances prohibiting
' compliance with the specifications require stopping work and notifying the cognizant supervisor for resolution.
Also, to address the additional weakness identified in the inspection report regarding Quality Control (QC) surveillance of welding activities, l QC has implemented a special welding surveillance checklist which has been incorporated into -QCO-6, " Welding Inspection",' along with monitoring frequency guidance. Routine, random surveillance of in process welding activities is being performed and documented.
Concerning the adequacy of the weld noted in example 1, the supporting procedure qualification records for the WPS were reviewed by Engineering.
As a result, the WPS travel speed was determined to be overly restrictive, and the WPS was revised accordingly to require 1-10 inches per minute.
As this change to the WPS was non-essential pursuant to the applicable ASME code, the quality of the weld was not affected by the use of a slower travel speed and the weld was determined to be acceptable.
I
." U. S. NRC I Page 3 December 11, 1989 To establish the adequacy of the weld noted in example 2, Engineering determined that the use of demineralized water to control interpass temperature on P8 austenitic stainless steel is an appropriate use of a quenching spray. A memorandum was issued by Engineering which established interim requirements for use of domineralized water as a l quenching spray until the weld specifications are revised. (The weld l specifications will.be revised by February 28, 1990.) However, prior
-to this determination occurring, the weld was cut out and rewelded without the.use of quenching spray and the now weld was determined to be acceptable.
-The continuous flare-bevel welds in example 3 were determined to be acceptable in accordance with AP&L specification APL-M-2410, Section 4'11,'" Support Assemblies of Greater Strength than Required". The hanger as-built drawing was revised to indicate the continuous weld.
, In each of the examples given, the quality of the welds was not affected.
l AP&L has no indication that procedural non-compliance has resulted in
( unsafe welding practices. l l- l L 3. The corrective steps that will be taken to avoid recurrence: l 1 i l Training on compliance with procedures and specifications will be conducted:for new welders coming on site in the future. This on going training, the training and the procedure changes which have already i been completed, and the implementation of the QC welding surveillance-u checklist will prevent a recurrence of this violation.
-A review of AP&L/ANO ASME and AWS Welding Procedure Specifications for accuracy and adequacy was initiated. The 52 AWS D1.1 qualified joint l
-and pre qualified joint WPSs have been reviewed and no changes were l requi red.' Of the 57 ASME Section IX qualified WPSs, 14 of the most l- commonly used WPSs have been reviewed and revised as necessary. The l' remaining ASME Section IX qualified Welding Procedure Specifications
!> will be reviewed and revised as necessary by February 28, 1990. Any L inadequacies in the remaining WPSs will not affect welding activities as the weld craftsmen and supervisors review the WPS prior to starting
- work and they are aware that any difficulties must be resolved before the work can be done. The AP&L/ANO Specification M-2415, " Nuclear Welding Standards", will be revised to address the use of demineralized water for controlling interpass temperature on austenttic stainless _
steels by February 28, 1990.
A review of the welding program at ANO has been initiated for possible enhancements, such as consolidation of the separate controls for the maintenance and modifications groups into uniform, comprehensive procedures and policies. Such procedures and policies would encompass training and qualification requirements for all welders on site. This review is expected to be completed by May 1, 1990.
i
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.i* . .
" -U.'S. NRC J Page 4 l s December _11, 1989 j
- 4. The date of full-compliance:
Compliance was achieved by October 22, 1989, with the completion J of the training of the weld craftsmen on compliance with procedures and I specifications.
, As discussed above, the following procedures changes will be completed by February 28, 1990:
- necessary based on reviews. ;
l
- AP&L/ANO Specification M-2415 to address the use of quenching spray.
-The review of the welding program as discussed above is expected to be p completed by May 1, 1990. ]
i Notice of Violation- l I
B. Document Control J l
Criterion VI of Appendix 8 to 10 CFR 50 and the licensee's approved '
quality assurance plan require that measures shall assure that document changes are distributed to and used at the location where the prescribed .
activity is performed. l l
Contrary to the above, out-of-date revisions of Procedures 1092.011
" Implementing and Control Welding," and 1033.003, " Welding Filler I Materia 1L Control" were in use at the storeroom during the issue of welding materials. This resulted in procedurally required records not being maintained.
This is a Severity level IV violation. (Supplement II) (313/8942-02; 368/8942-02) l Response to the Violation
- 1. The reason for the violation:
The correct revision of Procedure 1092.011 was not in the storeroom because Materials Management was not included on the Master Procedure Distribution List (MPDL) for 1092.011. The MPDL is used by Document Control to distribute new procedure revisions. The need for this procedure in the storeroom was apparently overlooked when distribution of the procedure was determined.
The correct revision of procedure 1033.003 was not in the rod storeroom I because the Stores Supervisor failed to forward a copy to the rod storeroom.
1 1
s 4 t
,('. . .. :
Attachment:
. 6m ' ' .'
o UU $.'NRC.
Page 5' December 11,:1989 ,
- 12. -The corrective steps that have been taken:
Copies of the latest revisions of procedures 1092.011 and 1033.003 were placed in thel rod storeroom on October 20, 1989.
Materials Management and the rod storeroom have been added to the NPDL for procedure 1092.011,'and the rod storeroom was added to the MPDL for procedure 1033.003. Revisions to these procedures will now be issued directly to the rod storeroom by Document Control, and written confirmation ,
of receipt of each revision is required by Document Control procedures.
The Stores Supervisor has a controlled set of procedures required by Materials Management. There are no other work locations in Materials 1
Management (except the rod storeroom) which require distribution of l document changes.-
I 1 The approval form for procedure revisions has recently been revised to l . ensure that ifsa procedure revision affects departments other than.
the department responsible for the procedure, the revision is also approved by a section leader in the other affected departments. This will help ensure that procedures are distributed to the appropriate departments.
- 3. Corrective steps that will'be taken to prevent recurrence:
Actions taken to place the procedures on the MPDL for the rod storeroom !
will prevent recurrence of this event, ,
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L A review will be conducted of the 1033 procedure series (Materials :
l' Management procedures) to identify referenced procedures which are the l 1
responsibility of other departments. -
These identified procedures will l be reviewed to determine if Materials Management should be on the ,
distribution list for each procedure. This review will be completed l by January 15, 1990.
p 4. The date of full compliance:
t Full compliance was achieved October 20, 1989, when the current revisions were placed in the storeroom, l'
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