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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
- 1 cntergy operanons,inc. t
. -:-:- ENTERGY iaasn 333 Rtr:scl%h A4 72301 Tel 501858-SCC 0 l July 15,1996 i l i l OCAN079601
, U. S. Nuclear Regulatory Commission l
. Document Control Desk l
Mail Station P1-137 !
Washington, DC 20555 l
Subject:
Arkansas Nuclear One - Units 1 and 2 !
Docket Nos. 50-313 and 50-368 ;
License Nos. DPR-51 and NPF-6 ,
Response to Generic Letter 95-07 l Request for AdditionalInformation '
l (TAC Nos. M93427 and M93428)
Gentlemen:
1 Entergy Operations provided responses to Generic Letter 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," in submittals dated i f
October 16,1995 (0CAN109509), and February 13,1996 (OCAN029605). By letter dated June 14,1996, the NRC requested additional information regarding our responses to the i generic letter.
1 L
The requested information is attached in accordance with your request. Should you have any I questions, please contact me.
Very truly yours, Nd Dwight C. Mims
! Director, Nuclear Safety ;
L i
DCM/dwb II l Attachment 9607230004 960715 i DR ADOCK 050003 3 l .-- - . . . - .-.
l U. S. NRC July 15,1996 OCAN079601 Page 2 cc: Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, St ite 400 1 Arlington, TX 76011-8064 I NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2
)
U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 4
1 i
- ,. ~
Attachment to 0CAN079601 Page1of4 ATTACHMENT 1 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LE' ITER 95-07 NRC Question 1 The licensee's IST program states that valves CV-1400, CV-1401, LPI/DH Loop Isolation Valves, are normally closed with a safety function to open. The licensee's submittal in response to GL 95-07 states that operating procedures have been revised to add a caution stating that the valves should remain open above 200 degrees F, because they are potentially susceptible to thermal binding. Has the licensee changed the normal position of these valves from normally closed to normally open during power operation, when reactor coolant system (RCS) average temperature is above 200 degrees F7 Please provide clarifying information regarding this procedure change. In addition, if these valves are flexible wedge, double disk or split .vedge gate valves, they may be potentially susceptible to pressure locking during a design basis event. Please addre.s this issue.
Question 1 Response During power operations, LPI/IM loop isoiation valves CV-1400 and CV-1401, are normally closed with 1 afety function to open. The normal closed position of the valves during power operation has not been changed. Since system fluid temperature can exceed 200 *F during decay heat removal operation, it is possible that the valve temperature could exceed 200 F when securing a decay heat removal loop from operation. As a precaution against thermal binding, procedure 1104.004, " Decay Heat Removal Operating Procedure," was revised to caution against thermal binding and note that if the valve body temperature of CV-1400 or CV-1401 was above 200 F at the time of securing the loop from decay heat removal operation, then the remainder of the realignment of the train could take place while waiting on the valve to coo! below 200 F. The valve will be closed once the valve body temperature drops below 200 F. The procedure also has provisions for closing the valve if the valve temperature is above 200 F depending on plant conditions. Should that occur, design engineering is required to be contacted fa contingency actions (i.e., cycle intervals) to maintain the valves operable. The intent of this procedure change is to assure that opening and closing operations are conducted at relatively the same conditions.
The LPI/DH loop isolation "alves CV-1400 and CV-1401 were also evaluated for susceptibility to pressure locivg. A maximum design basis RCS pressure of 2525 psig was assumed to be trapped in tne bonnets of the valves. Conservative values for packing loads, friction factors, and oegraded voltage were combined with torque and weak link capability obtained from the motor operated valve program and used as inputs into the Entergy Operations' pressure locking analysis method. The total required thrust to open the valve under these conditions was determined to be less than the valve's weak link l rating and the operator capability. The valves were thus determined to have sufficient l margin to operi under design basis conditions.
i
Attachment to 0CAN079601
. Page 2 of 4 NRC Question 2 In Table 2, the licensee's submittal states that valve CV-1000, Pressurizer ERV Isolation Valve, may be susceptible to boiler effect pressure locking. In addition, the NRC staff believes that this valve may be potentially susceptible to hydraulic pressure locking during a steam generator tube rupture. vent. The staff believes that further information is needed regarding the technical basis for the acceptability of this valve. For the purposes of closure of GL 95-07, has the licensee completed analytical calculations to demonstrate the capability of this valve to open under both boiler effect and hydraulic pressure locked conditions? If so, please provide these calculations for our review.
As part of its justification that pressure locking is not a concern for this valve, the licensee's submittal states that operability of this valve is not required as part of the ANO-1 licensing basis, because the valve has no active credited safety function. Also, the licensee's submittal states that the valve is part of a redundant RCS vent path as described in ANO-1 Technical Specification (TS) 3.1.1.7. TS 3.1.1.7 states that, with one RCS vent path inoperable, the inoperable vent path must be restored to operable status within 30 days Further, TS 3.1.1.7 states that, with two or more vent paths inoperable, at least two vent ; ohs must be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In that this valve may be requacu to move from the closed to open position to create an RCS vent path as described in TS 3.1.1.7, please describe why this valve has no active credited safety function.
Question 2 Response The Pressurizer Electromatic Relief Valve (ERV) Isolation Valve, CV-1000, is not required to stroke during a steam generator tube rupture event since ANO does not credit the use of the ERV to depressurize during this scenario. As part of ANO's pressure locking and thermal binding review, CV-1000 was evaluated for susceptibility to both hydraulic and boiler effect pressure locking. Results of this screening indicated that the valve was potentially susceptible to hydraulic pressure locking as well as boiler effect lockirg. The valve was evaluated with the Entergy Operations' pressure locking analysis method and was determined to have adequate margin to open against hydraulic pressure from the RCS (Reference Appendix 1, which contains portions of ANO Engineering Report 93-R-0010-01, Appendices III and IV regarding CV-1000). Because of the range of temyeratures to which the valve is exposed during operation, an analytical approach to demonstrate operability .. iring potential boiler effect locking situations was not considered feasible. In lieu of analysis, procedure modifications requiring CV-1000 to be open during I heatup were implemented to eliminate the potential for boiler effect pressure locking. l 1
Recommended actions identified in the attached excerpts from ANO Engineering Report 93-R-0010-01 have been included in the ANO corrective action program. Each ' . n .
l identifiul has either been completed or scheduled for action.
Attachment to OCAN079601 Page 3 of 4 Valve CV-1000, Pressurizer ERV Isolation Valve, has no active credited safety function.
Technical Specification 3.1.1.7 requires one reactor coolant system vent path from the pressurizer steam space to be operable when RCS temperature is above 280 F except that such path may be inoperable for up to 30 days. The vent path normally used to meet this requirement is through valves SV-1079 and SV-1077. This vent path was designed specifically for the purpose of venting noncondensible gases and/or steam from the RCS that could inhibit natural circulation core cooling. Though the path through CV-1000 was not designed for this purpose, it can be used to satisfy the technical specification requirement in the event that the path designed for this purpose is unavailable. There are no safety analyses that credit operation of either path. If neither path were available, all safety analyses would remain valid. Therefore, valve CV-1000, pressurizer ERV isolation valve, has no active credited safety function.
l l
NRC Question 3 In Table 2, the licensee's submittal states that valves 2CV-4698-1, Pressurizer Vent, and 2CV-4740-2, Low Temperature Over Pressure Isolation, are not susceptible to pressure locking or thermal binding. The NRC staff believes that these valves may be potentially susceptible to pressure locking or tharmal binding during a design basis event. Please provide a detailed description of your evaluation of the susceptibility of these valves to pressure locking or thermal binding.
Question 3 Response i
Valves 2CV-4698-1, pressurizer vent, and 2CV-4740-2, low temperature overpressure 4 isolation, were evaluated for susceptibility to pressure locking and thermal binding (Reference Appendix 2, which contains portions of ANO Engineering Report 93-R-0010-01, Appendix III regarding valves 2CV-4698-1 and 2CV-4740-2). Based on this evaluation, thz valves were determined not to be susceptible to pressure locking and thermal binding.
NRC Question 4 Through review of operational experience feedback, the staffis aware ofinstances where licensees have completed design or procedural modifications to preclude pressure locking or thermal binding which may have had an adverse impact on plant safety due to incomplete or incorrect evaluation of the potential effects of these modifications. Please describe evaluations and training for plant personnel that have been conducted for each design or procedural modification completed to address potential pressure locking or thermal binding concerns.
Attachment to OCAN079601' i
. Page 4 of 4 j Question 4 Response !
l The modifications to susceptible valves, including those already modified and those l planned, involve providing a vent path from the bonnet area. Existing modifications !
i instilled pressure relief valves and vented the bonnets to appropriate drains to prevent pressure locking. Future modifications may involve venting the bonnet area back to system piping. These modifications may result in one side of the double disk performing the isolation function for the valve.
)
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ANO is aware of concerns regarding pressure locking modifications to valves (e.g., valves may become unidirectional when a hole is drilled in the disk). To ensure that the modifications did not, or will not, have an adverse impact on plant safety, evaluations are performed for each of the changes in accordance with our rigorous design process. Post I
modification inspection and/or testing is another means used, where appropriate, to confirm the acceptability of the change.
Design changes, including valve modifications, are evaluated to determine whether or not the change should be included in the training for plant personnel. Training (required reading /information packages, etc.) on the procedure changes regarding valves modified to preclude pressure locking or thermal binding have been provided to licensed operators.
Consistent with established ANO procedures, future modifications will also be reviewed for appropriateness for training.
a ( .- . APPENDIX 1 i ANO-93-R@l0-01
.- APPENDIXIII Page 55 of121 Valve ID: CV-1000 PZR ERV Isolation Valve y
System: RCS Valve Size: 2.500
% JDisk Type: GATE (FW)
Evaluation Thermal Binding This valve is potentially susceptible to thermal binding, since the RCS temperature is greater than 200 'F during normal plant operation. NUREG-1275 lists an example where a PORV block valve failed due to stem / disk separation. The valve had been closed while the RCS was hot. The plant subsequently cooled down for a valve replacement. The valve failed to open because of thermal binding at the lower temperature. If CV-1000 is closed to isolate leakage from the ERV while the RCS is at normal operating temperature, and the plant is then subsequently cooled down with the valve in the closed position, the valve may fail to open at the lower temperature. Ifit does open, it is possible that internal parts may have been overstressed during the stroke. Damage to the disk ears or other valve parts may occur and not be noticed. To eliminate thermal bindmg as a concern, when CV-1000 has been isolated at normal operating temperatures, plant cooldown procedures should require cycling CV-1000 approximately every 100 'F during the cooldown. As an alternative to cycling, the valve could be opened at the start of the cooldown and left open. This valve is considered susceptible to thermal binding. This valve has been closed during portions of plant cooldowns in the past. It is important to assure that the valve has not been unknowingly overstressed by stroking it cold, following such a cooldown, with the valve in the closed position. Maintenance records should be reviewed, or a visual inspection performed for evidence that the valve has not sustained damage from such a scenario. Since the valve is currently open, it is considered operable l with respect to thermal binding, however to assure that it remains operable in the future, the recommended procedure changes should be implemented.
Hydraulic I4cking
. The valve is potentially susceptible to hydraulic locking, since steam could become
! trapped in the bonnet of the valve from flex wedge / seat leakage. For conservatism in
!' analyzing the potential for hydraulic locking, the maximum trapped bonnet pressure is assumed to be equal to the maximum RCS pressure (2525 psig.)(ref. 5). The upstream pressure is also conservatively assumed to be 2525 psig. at the time of opening. An
- evaluation using the Entergy " Hub" analysis method was done for this valve. The " Hub" l analysis predicts that the maximum required opening thrust occurs when bonnet pressure 55
i APPENulX 1 ANO-93-R 0010-01 ,
APPENDIXIII l Page 56 of121 l is at a maximum and the high side pressure equals the bonnet pressure. Maximum opening thrust under these conditions also occurs when the lower pressure side is zero. The valve was therefore evaluated against these conservative conditions, and demonstrated to be capable of performing its safety functmn.. The valve is also set to open against a delta-P ;
of not less than 2525 psig under the ANO GL 89-10 program and is capable of opening under these conditions. Since this valve is capable ef opening under these design basis conditions, it is not considered susceptible to hydraulic pressure locking.
Environmental Boiler EKect This valve is susceptible to environmental boiler effect. The valve is directly on the pressudzer. Heat from plant heatup will be transmitted to the bonnet of this valve. The 5 r.lve is in steam service, however because of the vertical valve orientation, condensate could be trapped in the bonnet. If the plant is heated up with the valve in the closed position, pressure could build up in the bonnet and possibly lock or over stress the valve.
Procedural guidance should be established to require that CV-1000 remain open following steam bubble formation. The valve can be opened and closed while the plant is at normal operating temperature without declaring it inoperable.
1 Proximity Boiler EKect ,
_ j This valve is susceptible to proximity boiler effect. The valve is directly on top of the pressurizer. Because of the valve orientation, condensate could be trapped in the bonnet.
If the plant is heated up with the valve in the closed position, pressure could build up in the bonnet and possibly lock or over stress the valve. Procedural guidance should be established to require that CV-1000 remain open following steam bubble formation. The valve can be opened and closed while the plant is at normal operating temperature without declaring it inoperable.
Recommendations and
Conclusions:
This valve is considered " Susceptible-Operable" at this time. Should the valve be closed hot and subsequently cooled down, the valve could bind, thus rendering it " Inoperable" The plant should also not be heated up with the valve in the closed position. Procedures should be revised, as described above, to preclude the potential for thermal binding and pressure locking. It should be noted that " Operability" of the valve is not required as part of the ANO-1 licensing basis, since the valve has no active credited safety function. The valve is however, part of a required RCS vent path as described in Technical Specification section 3.1.1.7.
56
(
.. app kf k ANO.93-R.001041
.. tressoix111 -
Page 57 of121
References:
- 1. 91-E-0091-01 R2
- 2. 91-E-0091-02 R0
- 3. NES 13 R1
- 4. ISO 16-RC-6 Sht.1 Rev. 7
- 5. CALC V-1031-00 Rev. 2 ;
- 6. CALC V-CV-1000-10 Rev. 2
- 7. OP 1102.002 RSS- Plant Startup :
- 8. OP 1103.005 R26- Pressurizer Operations
- 9. OP 1102.010 R44- Plant Shutdown and Cooldown
- 10. OP 1015.035 Rl- Valve Operations
- 11. OP 1015.002 R17- Decay Heat Removal and LTOP System Operation 1
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t 57
' ANO-93-R-0010-01 APPENDIX 1 APPENDIX IV PRE SURE LOCKING ANALYSIS FCR CV-1000 VARIABLES REFERENCES a = Mean Seat Remus = 1/2
- Mean Seat Diameter = 2.25/ 2 = 1.125 inches V-CV-100010f2 b = Disc Post Radius = 1/2
- Post Diameter = 1.625 / 2 = 0.813 hches 9Mt-1022 01/0 0 = Seat Angie = 5 Degrees 9Mt 1022-01/0 q = Pressure Trepped in Bonnet = 2525 pst V-103100/2 q
g = High Side Preneure = 2525 peig q = Low Side Pressure = 0 peQ p = ConfRcient of Fr6cuan Between Disc and Seat Ring = 0.4 EPRI TEST DATA TCF = Torque Correction Factor for VOTES Data = 0 N/A See Notes MUT = Measured UrW T1 rust at last State Test = 8406b JO-920106
- USinac = Open Calinaccuracy Assocseted with Unsesting Value = 0.04 *See Notes Below MAOT = Marn.:.am Allowebio Open Thrust Weeir Member = 22680 b ( ACT.TT LIMIT ) V-CV-1000-10/2 MPT = Motor Pullout Torque Capetullty for Open Direchon MPT = Start Torque
- Temp. Factor MES 01 DGF = AC voltage % squared or DC %. % voltage and Tempeture Factor Reference : 92-E-000S41/6 MPT 10* 77* 0.4
- 0.823 = 162.23 ft-lb Latest Setpomt ChW SF = Valve Stem Factor, used for Converson of Actuator Torque to Thrust
. COF = Coeffcient of Friction Assumed for r'*W of SF = 0.17 JO-920106 SF = 0.01309 ft b por b, usang COF above. Latest Setpoent Ced=harg MPOT = Motor Pullout Thrust r =r ha*y = MPT
- SF b MES-01 MPOT= 12.393 lb THE FOLLOWING VALUES ARE PER ROARKS FORMULAS FOR STRESS AND STRAIN, TABLE 2 C2= 1/4 [ 1-((b/s)*2 * (1+2*In(alb))] C = 0.034623 C3= b/(4a)[((b/a)a2 + 1)
- In(a/b) + (b/a)'2 1)] C =0.003014 3
NOTE: In the following equatens, y = .3 = Poisson's Rate for the disc metenal C8= 1/2(1 + v + (1 v)(ble)*2) C" 8
C, = tva[((1 +v)/2
- In(awt)) + ((1-v)/4 * (1 - (b/a)*2))] C = 0.212993 r 32 r 34 r 32 r 32' r 3 r 34' r ,2 e r
Lyg =
- in E- g . l.. 3. be d e 3 1 . I
n'os 4 a, ,a, r,,
o
- - r s
'O is set = to b, or poet radius L g= 0.000217 L = 0.032491 Page 30 of 62
i l '. --
APPENDIX 1 ANO-93-R-0010-01 i APPENDIX IV PRESSURE LOCKING ANALYS13 FOR CV-1000 l .-
l CALCULATION OF LOADS DUE TO BONNET PRESSURE:
0 bbon
- C8)] = Unit Sheer Force at Disc Hub Q h= 551.385 ItAn -
Q g =Qh * (b/ a)- q a
+2a * (e*2 - r 2) = Unit Force et Mean Seat Demeter Q = 280.0911 tan l CALCULATION OF LOADS DUE TO HIGH48DE PRESSURE:
i Q =q g
- C8)] = Unit Sheer Force at Disc Hub Q = 551.385 ItAn l
l Q =q g * (tv a)- q +2s * (a*2 - r*2) = Unit Force at Mean Seat Diameter l
l Qg = -280.091 ItAn CALCULATION OF LOADS DUE TO LOW 41DE PRESSURE:
O =q g
- C8)] = Unit Sheer Force at Disc Hub '
Q = 0 RAn j j Q =q h * (td e)- q a
+2a * (a 2 r*2) = Unit Force et Mean Seat Diameter Q = 0 ItAn CALCULATION OF LOADS DUE TO DIFFERENTIAL PRESSURE:
q =q q = 2525 pod 3p W = (Q -Q )+( q
- ba2y(2*pi*b) = 1577.797 ItAn O = -W
SEAT RING FORCE CALCULATIONS:
j Q g=Q .Q g = 0ItAn F
g =Q
Q =Q l
-Q +Q = 1420.312 RAn f
I F =Q
- a = -10039.62 t# l F = -1*( F g +F )= 10039.6 t#
4 k
4
- Page 31 of 62 i ;
APPENDIX 1 ANO-93-R-0010-01 APPENDIX IV
, PRESSURE LOCKING ANALYSD FOR CV-1000 REQUIRED THRUST CALCULATIONS FOR PRESSURE LOCKED CONDITION:
Total Required Thrust = Unseatir.g Force + Pressure Load - Stem Ejection Force T
Mat = Adjusted Static Unseating = MUT * (1 + Ina), where Ina = SRSS of inaccuracies of VOTES open.
Ina = (.09
- 7CF)2 +(ggjn,c)2 = M (.09
- 0 )^2+ 0.04 ^2 = 0.04 T )= 8805 lbf Mat = MUT * (1 + 0.04 Total Pressure Load = Fp = F g
- Valve Factor, VF VF = + (cos 0 + sin 0 )= 0.388 Fp = 38951bf SEF = Stem Ejection Force Due to Bonnet Pressure = q g9
- Stem Area SEF = 2525 *0.994 = 2510 lbf Total Minimum Required Unwedging Force = T t + Fp - SEF = 10190 lbf MARGIN FACTOR CALCULATIONS:
Weak Link Margin Factor = (MAOT - Min. Req'd Unwedging ) + Min. Req'd Unwedging = 123 %
Capability Margin Factor = (MPOT - Min Req'd Unwedging) + Min. Req'd Unwedging = 22%
NOTES:
Converted unstg torque (89.7) to thrust using static CST SF (.0108) due to poor open cat.
Torque error = (.025^2 + .02^2 + (2/89.7)^2) ^.5 = .04 TCF set to 0; thrust data not used.
Page 32 of 62
. . . - - . . . _ _ . ~ . - - - . - ~_ - - - - - . - -
, ANO-93-R-0010 01 ,
APPENDIXIII
. Page 26 of121 i Valve ID: 2CV-4698-1 PZR Emergency Core Cooling Vent Valve System: RCS Valve Size: 3.000 ;
i Viv/ Disk Type: GATE (FW) ,
Evaluation i
Thermal Binding .
This valve is not susceptible to thermal binding. During normal operation, the valve is .
closed. There is steam in the LTOP piping only up to 2CV-4740-2. This valve is several feet downstream. The valve will not be subject to significant thermal gradients from the ,
RCS. The maximum accident temperature in the containment building is 288 'F. .
l Temperatures above 200 F occur for approximately 17 minutes during a Design Basis LOCA. Information obtained from the valve manufacturer indicates that thermal binding of this valve should not cccur under these circumstances. ,
Hydraulic Locking This valve is potentially susceptible to hydraulic locking. If 2CV-4740-2 leaks, 2CV-4698-1 may trap full pressurizer pressure in its bonnet through flex wedge leakage. The -
initial RCS pressure trapped in the valve bonnet could be as high as 2585.3 psig, (Set pressure of the Pressurizer Safety Valves + 1% Tolerance and 3% accumulation). In a feed and bleed scenario, the RCS pressure is assumed to be 2585.3 psig for conservatism.
Some backpressure may exist in the Quench Tank due to leakage through the valve, however downstream pressure is assumed to be 0 psig for conservatism. Any backpressure developed will actually assist 2CV-4698-1 to open. An evaluation using the Entergy " Hub" analysis method was done for this valve. The " Hub" analysis predicts that the maximum required opening thrust occurs when bonnet pressure is at a maximum and the high side pressure equals the bonnet pressure. Maximum opening thrust under these conditions also occurs when the lower pressure side is zero. The valve was therefore evaluated against these conservative conditions, and demonstrated to be capable of performing its safety function.. The valve is also set to open against a delta-P of not less than 2585.3 psig under the ANO GL 89-10 program and is capable of opening under these -
conditions. Since this valve is capable of opening under these design ba sis conditions, it is not considered susceptible to hydraulic pressure locking.
26
APPENDIX Z
. ANO-93-R-0010-01 APPENDIXIII Page 27 of121 1 Environmental Boiler Effect i This valve is not susceptible to environmental boiler effect as its process fluid is steam and its operator is oriented vertically upward (Ref. 4).
l Proximity Boiler Effect This valve is not susceptible to proximity boiler effect as its process fluid is steam and the operator is oriented upward (Ref. 4).
Recommendations and
Conclusions:
This valve is considered not susceptible to failure from any PI/fB effects.
References:
- 1. 91-E-009l-01 R2
- 2. 91-E-0091-02 R0
- 3. NES 13 R1
- 4. 2BCA-14-1/15
- 5. M2230,SH2,H3/25 ;
- 6. V-2031-00/1
- 7. V-2CV-4698-10 R1 l
27 l
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" M HIX 2 Ano.93 a4oio4i APPENDIX M Page 28 of121 Valve ID: 2CV-4740-2 " RCS PZR LTOP ReliefIsolation Valve i
System: RCS Valve Size: 4.000 Viv/ Disk Type: GATE (FW) l Evaluation l Thermal Binding During startup, this valve is closed when the RCS temperature exceeds 275 'F. It is opened during cooldown when the RCS temperature is less than 275 'F to enable the LTOP system. Since there is steam in the LTOP piping prior to closing the valve on startup, it is potentially subject to stem elongation binding upon closing. There is no actual flow of steam while the valve is open for LTOP protection because of the closed pressure reliefvalve and ECCS Vent Valve 2CV-4698-1 downstream.' Therefore, the valve body temperature itself should not decrease due to steam flow stoppage when the disk is closed. Because of the continued RCS heatup, the valve body temperature will actually continue to increase. This heating will expand the valve body, disk and stem.
Since " Feed and Bleed Cooling" can be credited for core cooling after loss of all FW (though beyond the ANO-2 licensing basis), this valve could be required to open to reduce pressure in the RCS and allow safety injection. The slight possibility exists that the differential expansion of the valve body, disk and stem could cause thermal binding during -
an attempt to open the valve at high temperature. This however, is considered an extremely unlikely event' based on the following: 1.) The valve was designed for high temperature applications and is rated for the parameters postulated , 2.) Information obtained from the valve manufacturer confirms that if the heatup is gradual, the valve should have no problem with thermal binding. The valve has successfully opened many times for normal LTOP operation, and does not present a thermal binding concern for this function. The valve is considered "Not Susceptible" to thermal binding.
Hydraulic Locking This valve is potentially susceptible to hydraulic locking, as it may trap full pressurizer pressure in its bonnet through flex wedge leakage. The initial RCS pressure trapped in the valve bonnet could be as high as 2585.3 psig, (Set pressure of the Pressurizer Safety Valves + 1% Tolerance and 3% accumulation). In a feed and bleed scenario, the RCS pressore will be equal to or greater than HPSI shutoff head pressure of 1450 psig.
Upstream pressure is assumed to be 2585.3 psig for conservatism. Some backpressure may exist due to leakage through the valve, however downstream pressure is assumed to 2s
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be 0 psig for conservatism. Any backpressure developed will actually assist 2CV-4740-2 to open. An evaluation using the Entergy " Hub" analysis method was done for this valve.
The " Hub" analysis predicts that the maximum required opening thrust occurs when bonnet pressure is at a maximum and the high side pressure equals the bonnet pressure.
Maximum opening thrust under these conditions also occurs when the lower pressure side is zero. The valve was therefore evaluated against these conservative conditions, and
!. demonstrated to be capable of performing its safety function.. The valve is also set to
( open against a delta-P of not less than 2585.3 psig under the ANO GL 89-10 program and l is capable of opening under these conditions. Since this valve is capable of opening under
! these design basis conditions, it is not considered susceptible to hydraulic pressure locking.
Environmental Boiler EKect
! This valve is not suscepWe to environmental boiler effect. Its process fluid is steam and l its operator is oriented whically upward (Ref. 4). j Proximity Boiler Effect This valve is not susceptible to proximity boiler effect. Its process fluid is steam and the operator is oriented upward (Ref. 4).
Recommendations and
Conclusions:
This valve is considered "Not Susceptible" to pressure locking or thermal binding phenomena. It should be noted that " Operability" of the valve is not required as part of i the ANO-2 licensing basis, since the valve has no active safety function.
References:
, 1. 91-E-0091-01 R2 l 2. 91-E-0091-02 R0
! 3. NES 13 R1 I l 4. 2BCA-14-1/15
! 5. M2230,SH2,G3/25 i
[ 6. V-2041-00/1 i 7. V-2CV-4740-10 R1 4
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