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Category:CORRESPONDENCE-LETTERS
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20210K1621999-07-0707 July 1999 Informs That Licensee in Process of Preparing Scope of Service Delineation for Environ Assessment to Be Performed for New Airport Located Near Russellville,Ar,To Identify Anticipated Environ Impacts from Various Agencies 1CAN079902, Documents ANO-1 Position Discussed on 990705,with Members of NRC Staff & Formally Requests Enforcement Discretion from Requirements of TS 3.7.2.C to Allow Continued Power of Operation1999-07-0606 July 1999 Documents ANO-1 Position Discussed on 990705,with Members of NRC Staff & Formally Requests Enforcement Discretion from Requirements of TS 3.7.2.C to Allow Continued Power of Operation ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 0CAN069906, Forwards Corrected Pages to 1997 & 1998 Annual Radiological Environ Operating Repts, Issued 980430 (0CAN049804) & 990506 (0CAN059902).Ltr Number & Page Number Are at Top of of Corrected Pages to Replace Originally Pages1999-06-30030 June 1999 Forwards Corrected Pages to 1997 & 1998 Annual Radiological Environ Operating Repts, Issued 980430 (0CAN049804) & 990506 (0CAN059902).Ltr Number & Page Number Are at Top of of Corrected Pages to Replace Originally Pages 1CAN069905, Forwards non-proprietary Version of Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs1999-06-17017 June 1999 Forwards non-proprietary Version of Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs 0CAN069903, Submits Rept of Each Change to or Error Discovered in Acceptable Evaluation Model or in Application of Such Model for ECCS That Affects Peak Cladding Temp,Iaw 10CFR50.46(a) (3)(ii)1999-06-10010 June 1999 Submits Rept of Each Change to or Error Discovered in Acceptable Evaluation Model or in Application of Such Model for ECCS That Affects Peak Cladding Temp,Iaw 10CFR50.46(a) (3)(ii) 2CAN069901, Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 20001999-06-0202 June 1999 Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 2000 1CAN069901, Submits 10CFR50.46 Rept Re Inconsistent Input in SBLOCA Analysis.Rept Submitted in Accordance with Recommendations Stated in Notice1999-06-0202 June 1999 Submits 10CFR50.46 Rept Re Inconsistent Input in SBLOCA Analysis.Rept Submitted in Accordance with Recommendations Stated in Notice 0CAN059906, Forwards Response to NRC 990402 RAI Re GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-05-28028 May 1999 Forwards Response to NRC 990402 RAI Re GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs ML20207E4341999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft 1CAN059904, Informs NRC That Wl Franklin No Longer Has Need to Maintain Operating License on Ano,Unit 1.Requests License for Wl Franklin Be Withdrawn1999-05-20020 May 1999 Informs NRC That Wl Franklin No Longer Has Need to Maintain Operating License on Ano,Unit 1.Requests License for Wl Franklin Be Withdrawn 2CAN059906, Informs That ANO-2 UFSAR Will Be Revised to Include Comprehensive Discussions of Each Category of Containment Penetration Overcurrent Protective Devices,Per NRC Review of 980806 TS Change Request Re Relocation of TS Table 3.8-11999-05-18018 May 1999 Informs That ANO-2 UFSAR Will Be Revised to Include Comprehensive Discussions of Each Category of Containment Penetration Overcurrent Protective Devices,Per NRC Review of 980806 TS Change Request Re Relocation of TS Table 3.8-1 1CAN059902, Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program1999-05-17017 May 1999 Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program 2CAN059905, Expresses Appreciation for Staff & Mgt Team Efforts in Aggressively Pursuing Risk Informed ISI Initiative1999-05-14014 May 1999 Expresses Appreciation for Staff & Mgt Team Efforts in Aggressively Pursuing Risk Informed ISI Initiative ML20206P7681999-05-10010 May 1999 Forwards Applications for Renewal of Operating License (Form 398) for MW Little & F Uptagrafft.Without Encl 2CAN059903, Forwards Rev to Footnote Submitted to Provide Clarity to Aforementioned Guidance1999-05-10010 May 1999 Forwards Rev to Footnote Submitted to Provide Clarity to Aforementioned Guidance ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206H7121999-05-0606 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept, for Ano.All Radionuclides Detected by Radiological Environ Monitoring Program During 1998 Were Significantly Below Regulatory Limits 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEAR2CAN099009, Requests Interim Relief from Inservice Testing Re Performing Partial Stroke Test for Check Valve 2SI-16A.Valve Currently Required to Be Tested by 9009251990-09-21021 September 1990 Requests Interim Relief from Inservice Testing Re Performing Partial Stroke Test for Check Valve 2SI-16A.Valve Currently Required to Be Tested by 900925 0CAN099002, Discusses Validation of Nonlicensed Operator Staffing,In Response to Insp Repts 50-313/90-01 & 50-368/90-01.Concludes That Current Level of Three Nonlicensed Operators Per Shift, Adequate to Meet Demands of Operations Under EOP1990-09-14014 September 1990 Discusses Validation of Nonlicensed Operator Staffing,In Response to Insp Repts 50-313/90-01 & 50-368/90-01.Concludes That Current Level of Three Nonlicensed Operators Per Shift, Adequate to Meet Demands of Operations Under EOP 0CAN099007, Forwards Operator Licensing Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-14014 September 1990 Forwards Operator Licensing Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 2CAN099004, Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis1990-09-0707 September 1990 Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis 0CAN099001, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/90-19 & 50-368/90-19.Corrective Actions:Surveillance Procedures Reverified & Revised1990-09-0707 September 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/90-19 & 50-368/90-19.Corrective Actions:Surveillance Procedures Reverified & Revised 1CAN099003, Requests one-time Rev to Natl Exam Schedule for Operator License & Requalification Exams at Facility to Allow Testing in Aug,Rather than Feb of 19911990-09-0606 September 1990 Requests one-time Rev to Natl Exam Schedule for Operator License & Requalification Exams at Facility to Allow Testing in Aug,Rather than Feb of 1991 0CAN089009, Informs of Relocation to New Generation Support Bldg Just Outside Protected Area Southeast of Administration Bldg1990-08-31031 August 1990 Informs of Relocation to New Generation Support Bldg Just Outside Protected Area Southeast of Administration Bldg 0CAN089006, Forwards Semiannual Radiological Effluent Release Rept for First & Second Quarters 1990 & Changes to ODCM & Process Control Manual1990-08-30030 August 1990 Forwards Semiannual Radiological Effluent Release Rept for First & Second Quarters 1990 & Changes to ODCM & Process Control Manual 0CAN089008, Forwards Facility fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.73(d)1990-08-29029 August 1990 Forwards Facility fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.73(d) 0CAN089005, Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 9010011990-08-27027 August 1990 Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 901001 1CAN089011, Requests Relief from ASME Code Section XI Requirements Re Exercise & Stroke Time Testing for Low Pressure Injection Valves CV-1432 & CV-1433.Valves Located in Bypass Lines Around Decay Heat Coolers1990-08-16016 August 1990 Requests Relief from ASME Code Section XI Requirements Re Exercise & Stroke Time Testing for Low Pressure Injection Valves CV-1432 & CV-1433.Valves Located in Bypass Lines Around Decay Heat Coolers 2CAN089009, Requests Addl Time to Respond to NRC 900607 Request for Info Re Second 10-yr Interval of Inservice Insp Program. Response Will Be Submitted No Later than 9010311990-08-13013 August 1990 Requests Addl Time to Respond to NRC 900607 Request for Info Re Second 10-yr Interval of Inservice Insp Program. Response Will Be Submitted No Later than 901031 0CAN089002, Responds to Recommendations from Insp Repts 50-313/90-04 & 50-368/90-04 on 900202 That Reporting Format for Semiannual Radioactive Effluent Release Repts Be Revised to Comply W/ Reg Guide 1.21,Rev 11990-08-0808 August 1990 Responds to Recommendations from Insp Repts 50-313/90-04 & 50-368/90-04 on 900202 That Reporting Format for Semiannual Radioactive Effluent Release Repts Be Revised to Comply W/ Reg Guide 1.21,Rev 1 05000313/LER-1989-041, Revises Commitment Completion Date for LER 89-041-00 Re Proper Method of Calibr of Startup Feedwater Control Valves CV-2623 & 2673 to 900915.Delay Due to Time Needed to Review & Implement New Calibr Guidance Criteria1990-08-0202 August 1990 Revises Commitment Completion Date for LER 89-041-00 Re Proper Method of Calibr of Startup Feedwater Control Valves CV-2623 & 2673 to 900915.Delay Due to Time Needed to Review & Implement New Calibr Guidance Criteria 2CAN089006, Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info1990-08-0202 August 1990 Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info ML20081E0891990-07-31031 July 1990 Advises That Since Guidance Contained in Reg Guide 1.97 Not Addressed in Submittals Re Generic Ltr 82-33,further Clarification of Position Re Compliance W/Generic Ltr Appropriate,Per .Ltr Will Be Submitted by 901215 0CAN079014, Amends Commitment Date for Mods to Svc Water Pump Design,Per Insp Repts 50-313/89-30 & 50-368/89-30.Project Scoping Rept Expected to Be Completed by 9009301990-07-31031 July 1990 Amends Commitment Date for Mods to Svc Water Pump Design,Per Insp Repts 50-313/89-30 & 50-368/89-30.Project Scoping Rept Expected to Be Completed by 900930 0CAN079024, Forwards Revised Response to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Specific Communication Meetings Will Be Conducted W/Staff Re Decontamination Practices & Procedures1990-07-31031 July 1990 Forwards Revised Response to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Specific Communication Meetings Will Be Conducted W/Staff Re Decontamination Practices & Procedures 0CAN079020, Forwards Update to Status of Remaining Open Items on Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Encl Withheld (Ref 10CFR2.790)1990-07-31031 July 1990 Forwards Update to Status of Remaining Open Items on Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Encl Withheld (Ref 10CFR2.790) 0CAN079018, Certifies That Info Contained in Rev 12 to QA Manual Operations Freighted to NRC on 900723 & Accurately Represents Changes Made Since Previous Submittal,Per 10CFR50.54(a)(3)1990-07-24024 July 1990 Certifies That Info Contained in Rev 12 to QA Manual Operations Freighted to NRC on 900723 & Accurately Represents Changes Made Since Previous Submittal,Per 10CFR50.54(a)(3) 0CAN079021, Forwards Rev 12 to QA Manual Operations1990-07-23023 July 1990 Forwards Rev 12 to QA Manual Operations 0CAN079019, Forwards Rev 12 to QA Manual Operations.W/O Encl1990-07-23023 July 1990 Forwards Rev 12 to QA Manual Operations.W/O Encl 0CAN079011, Suppls Response to Violations Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Re Isolation Valve CS-26. Corrective Actions:Special Work Plan Developed & Valve Cs-26 Local Leak Rate Tested on 9002161990-07-20020 July 1990 Suppls Response to Violations Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Re Isolation Valve CS-26. Corrective Actions:Special Work Plan Developed & Valve Cs-26 Local Leak Rate Tested on 900216 2CAN079008, Forwards Response to NRC Questions on CEN-386-P Re Extended Burnup Rept & Statistical Treatment of Elastic Strain in Fuel Cladding at end-of-life & Measured Axial Fuel Rod pellet-to-pellet Gaps1990-07-17017 July 1990 Forwards Response to NRC Questions on CEN-386-P Re Extended Burnup Rept & Statistical Treatment of Elastic Strain in Fuel Cladding at end-of-life & Measured Axial Fuel Rod pellet-to-pellet Gaps 0CAN079006, Provides Update to Util Providing Results of Comparison of Station Blackout Rule Submittals to NUMARC Guidance1990-07-17017 July 1990 Provides Update to Util Providing Results of Comparison of Station Blackout Rule Submittals to NUMARC Guidance 2CAN079001, Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip1990-07-0505 July 1990 Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip ML20043H5161990-06-19019 June 1990 Informs of Changes of Responsibility for Plant Emergency Plan,Effective 900605 ML20043H3121990-06-18018 June 1990 Forwards Responses to Remaining NRC Questions Re Seismically Qualified,Partially Protected,Condensate Storage Tank (Qcst).Analyses in Calculations Demonstrate That Qcst Tank Foundation & Drilled Piers Adequate W/O Mod ML20043F3321990-06-15015 June 1990 Submits Addl Info on Tech Spec Change Request for Seismic Instrumentation,Per 890809 Request.Licensee Concurs W/Nrc Recommendation Re Editorial Change ML20043G0661990-06-13013 June 1990 Responds to Deviations Noted in Insp Repts 50-313/90-11 & 50-368/90-11.Corrective Actions:Further Evaluations Conducted to Develop Optimum List of post-accident Instruments Requiring Identification on Control Panels ML20043H3471990-06-11011 June 1990 Forwards Rev 19 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043G3801990-06-11011 June 1990 Responds to Violations Noted in Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Decision Made to Staff Unit 1 Exit Location Point W/Health Physics Technician 24 H Per Day ML20043F5121990-06-0808 June 1990 Forwards List of Directors & Officers of Entergy Operations, Inc.Operation of All Plants Transferred to Entergy on 900606 ML20043F4341990-06-0707 June 1990 Informs of Receipt of Necessary Approvals to Transfer Operating Responsibilities of Plant to Entergy Operations, Per Amends 128 & 102 to Licenses DPR-51 & NPF-6, Respectively.Extension of Amend Request Unnecessary ML20043E6561990-06-0707 June 1990 Requests That Listed Distribution Be Made on All Future NRC Correspondence.Correspondence to Ns Carns Should Be Addressed to Russellville ML20043E4991990-06-0505 June 1990 Provides Supplemental Response to Violations Noted in Insp Repts 50-313/89-02 & 50-368/89-02.Corrective Actions:Listed Program Enhancements Being Implemented to LER Process to Provide Timely Determinations of Condition Rept ML20043E3851990-06-0404 June 1990 Concurs w/900516 Ltr Re Implementation of SPDS Complete for Both Units & Requirements of NUREG-0737,Suppl 1 Met ML20043E3771990-06-0404 June 1990 Forwards Response to Concerns Re Control Room Habitability Survey.Addl Mods Identified Will Enhance Overall Reliability of Control Room Sys & Changes Designed to Increase Performance,Effectiveness & Response of Habitability Sys ML20043C0821990-05-25025 May 1990 Withdraws 900410 Request to Amend Tech Spec Table 3.3-1 Re Applicable Operational Modes for Certain Reactor Protective Instrumentation Operability Requirements ML20043B6531990-05-22022 May 1990 Forwards Rev to Industrial Security Plan to Eliminate Need to Protect Certain Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21) ML20043B7091990-05-21021 May 1990 Forwards Revised Maelu Certificate of Insurance for Nuclear Onsite Property Insurance Coverage for 1990,changing Policy Number from X89166 to X90143R ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A5991990-05-15015 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Repts for Feb & Mar 1990 for Arkansas Nuclear One,Unit 1 ML20042H0551990-05-0909 May 1990 Forwards Civil Penalty in Amount of $50,000 for Violations Noted in Insp Repts 50-313/86-23 & 50-368/86-24 Re Environ Qualification of Electrical Equipment Important to Safety. Comprehensive Corrective Actions Undertaken ML20043B0841990-05-0909 May 1990 Corrects 900309 Ltr Re Completion of Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Design Change Package Addressing Perimeter & Interior Lighting Scheduled to Be Onsite Late Summer 1991 ML20043A8361990-05-0707 May 1990 Responds to Violations Noted in Insp Repts 50-313/90-05 & 50-368/90-05.Corrective Actions:Personnel Involved Received Counselling Re Incident & Operations Personnel Being Trained on Significance of Surveillance Requirements ML20042F4371990-05-0404 May 1990 Requests 90-day Extension to Provide Addl Time for Reviews of Amends 128 & 102 to Licenses DPR-51 & NPF-6,respectively, Re Ownership Transfer ML20042G4771990-05-0404 May 1990 Forwards Summary of Util Exercise Critique Board Evaluation of Radiological Emergency Preparedness Exercise REX-90,per Insp Repts 50-313/90-08 & 50-368/90-08 ML20042F3351990-05-0303 May 1990 Forwards Nonproprietary Suppl 1 to CEN-386-NP & Proprietary Suppl 1 to CEN-386-P, Responses to Questions on C-E Rept CEN-386-P, 'Verification of Acceptability of 1-Pin Burnup Limit....' Proprietary Rept Withheld (Ref 10CFR2.790) ML20042F2701990-04-30030 April 1990 Provides Exam Schedules for Reactor Coolant Pumps a & B in Revised Inservice Insp Program Plan.Insps Scheduled for Refueling Outages 1R10 & 1R12 for Pump a Exams & Refueling Outages 1R10,1R12 & 1R14 for Pump B Exams 1990-09-07
[Table view] |
Text
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARXANSAS 72203 (501) 377-4000 February 29, 1988 OCAN028806 U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 ATTN: Mr. Robert D. Martin, Administrator
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 1.E. Bulletin 85-03: Motor-0perated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings
Dear Mr. Martin:
Arkansas Power and light provided verification that motor-operated valve testing has been completed in accordance with Action Item "f" of IE Bulletin 85-03 by letter dated January 15, 1988 (0CAN018805). To complete our response to Action Item "f", we are submitting a written report describing our approach to each of the Action Items from the Bulletin and a summary of data for each motor-operated valve that has been compiled in response to the Bullet.in.
This report completes our response to I.E. Bulletin 85-03 for Arkansas Nuclear One, Units 1 and 2.
Very truly yours, Dan R. Howard Manager, Licensing DRH:GW:mb cc: U.S. Regulatory Commission Document Control Desk Washington, D.C. 20555 8803000213 000229 3 DR ADOCK 050 hh
- . - . - - . . . . . . . k,
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) SS COUNTY OF PULASKI )
1, Dan R. Howard, being duly sworn, subscribe to and say that I am Manager, Licensing for Arkansas Power & Light Company; that I have full authority to execute this oath; that I have read the document numbered SCAN 028806 and know the contents thereof; and that to the best of my knowledge, information and belief the statements in it are true.
[
Dan R. Howard SUBSCRIBED AND SWORN T0 before me, a Notary Public in and for the County and State above named, this M ay of w _
1988.
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Notary Public Hy Commission Expires:
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IE BULLETIN 85 MOTOR-OPERATED VALVE COMMUN MODE FAILURES OURING PLANT TRANSIENTS DUE TO IMPROPER SWITCH SETTINGS e
WRITTEN REPORT 1 REQUESTED UNDER ITEM F, IEB 85-03 FOR ARKANSAS POWER.AND LIGHT COMPANY ARKANSAS NUCLEAR ONE
- UNITS - 1 AND 2 f
4 FEBRUARY, 1988 L ...
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. RESPONSE TO IE BULLETIN 85-03 ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 IE Bulletin 85-03 (9CNA118511) requested Arkansas Power and Light to implement a program to ensure that switch settings on high pressure safety injection and auxiliary feedwater system safety-related motor-operated valves (MOV's) are selected, set, and maintained correctly to accommodate the maximum differential pressures expected on these valves during both normal and abnormal events within the design basis. Provided below is the response for Arkansas Nuclear One, Units 1 and 2.
Action Item "a" "Review ard document the design basis for the operation of each valve. This documentation should include the maximum differential pressure expected during both opening and closing the valve for both normal and abnormal events to the extent that these valve operations and events are included in the existing, approved design basis, (i.e., the design basis documented in pertinent licensee submittals such as FSAR analyses and fully-approved operating and emergency procedures, etc.). When determining the maximum differential pressure, those single equipment failures and inadvertent equipment operations (such as inadvertent valve closures or openings) that are within the plant design basis should be assumed."
Response
Arkansas Power and Light has conducted the requested reviews for both Units 1 and 2 with these results documented in the attached "MOV Data Summary" Tables. These results were initially transmitted to the NRC by letter dated May 14, 1986 (OCAN058503),
as required by IE Bulletin 85-03.
Action Item "b" "Using the results from item "a" above, establish the correct switch settings. This shall include a program to review and revise, as necessary, the methods for selecting and setting all switches (i.e., torque bypass, position limit, overload) for each valve operation (opening and closing).
If the licensee determines that a valve is inoperable, the licensee shall also make an appropriate justification for continued operation in accordance with the applicable technical specification."
Response
Arkansas Power and Light has implemented a program to review and revise, as necessary, the methods for selecting and implementing o
. Response (cont.)
switch settings. These activities for the 85-03 Bulletin MOV's >
and the additional MOV's that were tested, were performed under a special work plan that was utilized for MOV testing and other MOP related inspections. MOVATS (Motor Operated Valve Analysis and Testing System) was utilized to accurately set switches based on the desired thrust values and switch trip points, as described in our letter to the NRC dated October 1, 1986 (9CAN198692).
In accordance with IE Bulletin 85-03, existing switch settings were reviewed for operability with regard to the design differential pressures imposed by IE Bulletin 85-03 and these results are shown in the attached "MOV Data Summary" Tables in the "As Found Valve Operability" column. This review of "As Found Operability" concentrates on the individual actuator travel in both directions by examining the torque switch bypass, undervoltage requirerents, the as-found torque switch trip (TST) and the minimum setting limits derived from the valve and actuator calculations. The end results of this review was the designation of each MOV as either "operable", "inoperable" or if it could not be determined, "indeterminate". For those designated "indeterminate", each MOV was not considered inoperable based on the high probability that it would have performed its function due to the conservatism in the calculations. These operability classifications deal only with the operability of the MOV (As Found) in the direction given and are not comparable to "operability" as defined by the Technical Specifications.
Operability evaluations of the MOV in accordance with the applicable Technical Specifications were performed at the time of the diagnostic testing (H0 VATS) to determine the reportability of l any inoperable MOV's. These evaluations were performed considering the safety function of the MOV, the requirements of the system containing the MOV, and previous operating and testing performance. As a result of these evaluations, no reportable items per 10CFR50.72 and 10CFR50.73 were found during the Unit 1 and 2 MOV testing.
, Action Item "c" "Individual valve settings shall be changed, as appropriate, to those established in item "b", above. Whether the valve setting is changed or not, the valve will be demonstrated to be operable by testing the valve at the maximum differential pressure determined in item "a" above with the exception that testing motor-operated valves under conditions simulating a break in the line containing the valve is not required. Otherwise, justification should be provided for any cases where testing with u-
, Action Item "c" (cont.)
the maximum differentialspressure cannot practicably be performed.
This justification should include the alternative to maximum differential pressure testing which will be used to verify the correct settings.
Note: This bulletin is not intended to establish a requirement for valve testing for the condition simulating a break in the line containing the valve. However, to the extent that such valve operation is relied upon in the design basis, a break in the line containing the valve should be considered in the analyses prescribed in items "a" and "b" above. The resulting switch settings for pipe break conditions should be verified, to the extent practical, by the same methods that would be used to verify ,
other settings (if any) that are not tested at the maximum A
differential pressure.
Each valve shall.be stroke. tested, to the extent practical, to T verify that 'the settdngs defined in item "b" above have been properly implemented even if testing with differential pressure cannot be performed".
Response
(
Each MOV tested in accordance with I.E. Bulletin 85-03 was tested to verify that the settings defined in Action Item "b" were properly implemented and the MOV functions properly at these settings. The "Test Method Description / Justification" column in the attached "MOV Data Summary" Tables describe what testing was performed on each MOV.
Differential pressure (DP) testing was performed on selected valves representing valve groups that encompass all the I.E.
Bulletin 85-03 valves. Differential pressure testing was performed on 17 MOV's in ANO Unit 1 and 16 MOV's in Unit 2. Most of the MOV's were DP tested close to their design DP from the results of Action Item "a". In cases where the maximum DP could not be obtained, the valve stem thrust recorded at the test pressure was extrapolated up to the design DP. The method used to extrapolate valve stem thrust was a simple ratio of the design to test pressures multiplied by the test thrust. This extrapolation y method was described in our response to additional questions in '
our letter dated October 6, 1987 -(1CAN108703).
n 1
Though the DP testing performed was considered sufficient in most ,
respects, not all valve types were tested. Explanations are provided in the attached "MOV Data Suinmary" Tables for valves that \
could not be DP tested.
f :
I
, Response (cont.) ac ,
Evaluation of the results of DP testing provided confidence that the' calculations utilized to predict the performance of the M0V's are conservative and can be used to set torque switches on other-MOV's at ANO using MOVATS equipment and procedures.
t
[/ Action Item "d"
,4 "Prepareor_rOiseprocedurestoensurethatcorrectswitch-settings are determined and maintained throughout the life of the plant. Ensure that applicable industry recommendations are
, considered in the preparation of these procedures.
) >#" ')
This item is intended to be completely consistent with action item g' ' ' 3.2, "Post-Maintenance Testing (All Other Safety-Related Components)," of Generic Letter 83-28, "Required Actions Based on i
Generic Implications of Salem ATWS Events." These procedures I,
should include provisions to monitor valve performance to ensure
, the switch settings are correct. This is particularly important
- if the torque or torque bypass switch setting har been
(' significantly raised above that required."
, i Resp 4nyse Procedures are in place to ensure that correct switch settings are maintained. We are prescatly evaluating the enhancement of our
- program with a new administrative procedure to be used in
,, setpoints selection. Our procedures are based on the outcome from our testing program and the development of industry experience
/. based on applicable industry recommendations,.
Action Item "e" u
"Within 180 days of the date of this b'lletin, submit a written report to the NRC that: (1) reports the results of item "a" and (2) contains the program to accomplish items "b" through "d" above including a schedule for completion of these items. The schedule
, shall msure that these items are completed as soon as practical and within-two years from the date of this bulletin".
Response
Arkansas Power and Light responded to this item on May 14, 1986
, with a written report (OCAN058603) sent to Region IV submitting the results of Action Item "a" and a description of our program
- for Items "b" through "d".
l l
l 1
1 I
,s
. Action Item "f" Provide a written report on completion of the above program. This report should provide (1) a verification of completion of the requested program, (2) a summary of the findings as to valve operability prior to any adjustments as a result of this bulletin, and (3) a summary of data in accordance with Table 2, Suggested Data Summary Format. The NRC staff intends to use this data to assist in the resolution of Generic Issue II.E.6.1. This report shall be submitted to the NRC within 60 days of completion of the program. Table 2 should be expanded, if appropriate, to include c summary of all data required to evaluate the response to this bulletin.
Response
This' written report with the attached "MOV Data Summary" Tables along with our initial response to this Action Item in our letter dated January 15, 1988 (0CAN018805), completes Arkansas Power and Light's response to I.E. Bulletin 85-03.
1 5-1- . .
h 1
, ' ATTACHMENTS MOV Data Summary' Table for ANO -Unit 1, High Pressure Safety Injection System -.2 pages MOV Data Summary Table for ANO - Unit 1, Emergency Feedwater System - 4 pages.
MOV Data Summary Table for ANO - Unit 2, High Pressure Safety Injection System - 4 pages.
H0V. Data Summary Table for ANO - Unit 2, Emergency Feedwater System - 4 pages.
General notes on Tables;
- Three valves were changed-out as a result of the MOV testing and are identified by an (*) on the tables. The valve information shown in the table describes data on the new valve that was Installed, however, "As-Found Operability" is based on the valve that was removed.
- 2CV-0707 was removed from our original IEB 85-03 list, reference OCAN058603, since the MOV is being exercised manes 11y with power removed to the actuator.
MOV DATA
SUMMARY
ARKANSAS NUCLEAR ONE - 17.li 1 HIGH PRESSURE SAFETY INJECTION SYSTEM SWITCH SETTINGS VALUE VALVE OPERATOR VALVE DESIGN TEST DP PRIOR TO FIMAL SWITCH AS FOUND TEST METHOD DESCE!PTION/
FUNCTION BASIS DP ADJUSIMLNT SLTTINGS VALVE JUSTIFICATION (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model, Motor Open Open Open/Close Open/Close Open-Type, Model, RPM, Lutput Close Close Close Sizt, Rating Speed (RPM)
CV-1219 Limitorque HPI Valve to 2758 psi 2928 psi 1.5/2.0 1.5/1.5 Operable DP Tested within 10% of Design V21an, Globe SMB-00 Loop A 2937 psi 2928 psi Inoperable Basis DP and MOVATs Tested.
B9-3748-13MS 1700 RPM 2.5", 1500 lb. 44 RPM CV-1220 Limitorque HPI Valve to 2758 psi 2948 psi 1/2 l'1.375 Operable DP Tested within 10% of Design V21an, Globe SMB-00 Loop A 2937 psi 2948 psi Indeterminate Basis DP and MOVATs Tested.
89-3748-13MS 1700 RPM 2.5", 1500 lb. 44 RPM CV-1227 Limitorque HPI Valve to 2758 psi 2928 psi 1/1 1/1.5 Operable DP Tested within 10% of Design Valan, Globe SMB-00 Loop B 2937 psi 2928 psi Operable Basis DP and MOVATs Tested.
89-374B-13MS 1700 RPM 2.5", 1500 lb. 44 RPM CV-1228 timitorque HPI Valve to 2758 psi 2930 psi 1.5/1 1/2 Operable DP Tested within 10% of Design V21an, Globe SMB-00 Loop B 2937 psi 2930 psi Inoperable Basis DP and MOVATs Tested.
89-374-03MS 1100 RPM
- 2. 5", 1%0 lb. 44 RPM
' CV- 13',0 Limitorque HPI Pump Recirc. 2944 psi See 2/3.5 4/3.5 Inoperable MOV identical to CV-1301 which Vogt. Gate SMB-000 Isolation Valve 2944 psi CV-1301 Operable was selected for DP testing.
2", 1500 lb. 1725 RPM MOVATs tested also.
39 RPM
- CV-1301 Limitorque HPI Pump Recirc. 2944 psi 2973 psi 1.5/4 5/4.25 Inoperable DP Tested within 10% of Design Vogt Gate SMB-000 Isolation Valve 2944 psi 2973 psi Operable Basis DP and MOVATs Tested.
2", 1500 lb. 1725 RPM 39 RPM CV-1405 Limitorque Containment 63 psi Not DP 3/3 2/1.25 Operable MOVATs Tested, OP Testing not Crane- Alloyco, SMB-00 Isolation Valve, 63 psi Tested Operable feasible due to requiring water Gate, N9126-SP 1700 RPM P34A Suction level in containment. Hydro 14", 150 lb. 23.6 RPM Reactor Building Alternative not considered prac-Sump Recirc. tical in lieu of MOVATs Testing.
1
MOV DATA SUMMALY ARKANSAS NUCLEAR ONE - C*IT 1 HIGH PRESSURE SAFETY INJECTION SYSTEM SWITCH SETTING 5 VALVE VALVE OPERATOR VALVE DESIGN TEST DP PRIOC TO FINAL SWITCH AS FOUND TEST METHDD DESCRIPTIDM/
FUNCTION BASIS DP ADJUSTMENT SETTINGS VALVE JUSTIFICATIDM (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model, Motor Open Open Open/Close Open/Close Open Type Model, RPM, Output Close Close Close Stte, Rating Speed (RPM)
CV-1406 Limitorque Containment 63 psi Not OP 2.25/2.25 1.5/1 Operable M0 VATS Tested DP Testing not Crane-Alloyco, SMB-09 Isolation Valve, 63 psi Tested Operable feasible due to requiring water Cata N9126-SP 1700 RPM P348 Suction level in containment. Hydro 14", 150 lb. 23.6 RPM Reactor Cuilding Altarnative not considered prac-Sump Recirc. tical in lieu of MOVATs Testing.
CV-1407 Limi torque Borated Water 81 psi Not DP 2.25/1.75 <2/1.5 Operable MOVATS Tested, DP Testing not Crane-Alloyco, SMB-2 Storage Tank 81 psi Tested Operable feasible due to draining Safety Gata, N9126-SP 3400 RPM Isolation Valve Injectica Pumps Suction lines.
14", 150 lb. 125 RPM for P34A Suction Hydro Alternative not considered practical in lieu of MOVATs Testing.
CV-1409 timitorque Borated Water 81 psi Not DP 1.5/2 1.25/1 Operable MOVATs Tested, DP Testing not Crane-Alloyco, SMB-2 Storage Tank 81 psi Tested Operable feasible due to draining Safety Gita, N9126-SP 3485 RIM Isolation Valve Injection Pumps Suction lines.
14", 150 lb. 125 RPM for P34B Suction Hydro Alternative not considered practical in lieu of MOVATs Testing.
CV-1414 Rotork Reactor Building 63 psi Not DP Damaged 5/1.75 Operable ADVATs Tested DP Testing not Anchar Darling, 16NA21 Sump Isolation 63 psi Tested Torque Switch Operable feasible due to requiring water Gate 1800 RPM Valve for P34A :evel in containment. Hydro 14-150 FW 30 RPM Suction Alternative not considared prac-14", 15n Ib. tical in lieu of MOVATs Testing.
CV-1415 Rotork Reactor Building 63 psi Not DP 4.5/ Max. 1.75/2 Operable MOVATs Tested, DP Testing not Anchor Darling,16RAZ1 Sump Isolation 63 psi Test?d Operable feasible due to requiring water Gata 1800 RPM Valve for P348 level in containment. Hydro 14-150 FW 30 RPM Suction Alternative not considered prac-14", 150 lb. tical in lieu of MOVATs Testing.
2
MOV DATA
SUMMARY
ARKANSAS NUCLEAR ONE - UNIT 1 ,.
EMERGENCY FEEDWATER SYSTEM SWIICH SE181NGS VALVE VALVE OPERATOR VALVE DESIGN TEST DP PRIOR TO FINAL SWITCH AS FOUND TEST METHOD DESCRIPTION /
FUNCTION BASIS DP ADJUSTMENT SETTINGS VALVE JUST1FICATION (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model Motor Open Open Open/Close Open/Close Open Type, Model, RPM, Output Close Close Close Siza, Rating Speed (RPM) a CV-2613 Limitorque Inlet Steam 1100 psi 395 psi' 1.5/1.5 2/2 Operable M0 VATS Tested and DP Tested Anchor Darling, SMB-000 Isolation valve 1100 psi 95 psi Inoperable- at maximum attainable DP due G:,ta 1900 RPM for P7A From SGA to interaction between the 4-900-FW 36.5 RPM trip and throttle valve, 4", 900 lb.
CV-2617 Limitorque Inlet Steam 1100 psi 900 psi 3/3 3.75/3.5 Operable MOVATs' Tested and DP Tested Vilan, Gate SMB-000 Isolation Valve 1100 psi 900 psi Operable at maximum attainable DP due B12 254S-02TS 1700 RPM for P7A From SGB to interaction between the 4", 600 lb. 35.0 RPM trip and throttle valve.
CV-2620 Limitorque P7A Isolation 1824 psi See 2/3 2.5/1.75 Indeterminate MOV Identical to CV-2626 and Anchor Darling, SMB-00 Valve for SG8 1824 psi CV-2626 Inoperable 2670 which were selected for Gata 1900 RPM DP Testing. MOVATS Tested 4-900-FW 28.1 RPM also.
4", 900 lb.
CV-2626 timitorque P78 Isolation 1519 psi 1502 psi 2.25/2.25 1.5/1 . Operable DP Tested within 10% of Design Anchor Darling, SMB-00 Valve for SGB 1519 psi 1502 psi Operable Basis DP and MOVATs Tested.
Gata 1800 RPM 4-900-FW 25.2 RPM 4", 900 lb.
CV-2627 Limitorque P7A Isolation 1824 ps' See 2/2.5 2/1 Indeterminate MOV Identical to CV-2626 and Anchor Darling, SMB-00 Valve for SGA 1824 psi CV-2670 Inoperable 2670 which were selected for DP Gate 1900 RPM Testing. MOVATs Tested also.
4-900-FW 18.7 RPM 4", 900 lb.
CV-2663 Limitorque Inlet Steam 1100 psi 845 psi 1/2 2.75/2.5 Operable MOVATs Tested and DP Tested at Anchor Darling, SMB-000 Isolation valve 1100 psi 845 psi Inoperable maximum attainable DP due to Gate 1900 RPM for P7A from SGB interaction between the trip 4-900-Fw 36.5 RPM and throttle valve.
4", 900 lb.
CV-2667 timitorque Inlet Steam 1100 psi 900 psi 1.5/2.5 2.75/2.5 Indeterminate MOVATs Tested and DP Tested at Borg-Warner, SMS-000 Isolation Valve 1100 psi 900 psi Operable maximum attainable DP due to Gate. 1700 RPM for P7A From SGA interaction between the trip 4", 600 lb. 46.6 RPM and throttle valve.
1
MOV DATA SUHAARY ARKANSAS NUCLEAR ONE - UNIT 1 EMERGENCY FEEDWATER SYSTEM SWilCH SE111NGS VALVE VALVE OPERATOR VALVE DESIGN TEST DP PRIOR TO FINAL SWITCH AS FOUND TEST METHOD DESCRIPT10k/
FUNCTION BASIS DP ADJUS1 MENT SETTINGS VALVE JUSTIFICATIDM (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model Motor Open Open Open/Close Open/Close Open Type, Model, RPM, Output Close Close Close Siza, Rating Speed (RPM)
CV-2670 Limitorque P78 Isolation 1519 psi 1502 psi 2.25/2 2/1.25' Operable DP Tested within IDE of Design -
Anchor Darling, SMB-00 Valve for SGA 1519 psi 1502 psi Operable Basis OP and MOVATs Tested.
Gata 1800 RPM 4-900-FW 25.2 RPM 4", 900 lb.
CV-2800 Limitorque Condensate 100 psi See 2/2 2.25/1.5 Operable MOV Identical to CV-2802 which -
4 Valan, Gate SMB-00 Storage Tank 112 psi CV-2802 Operable was selected for DP Testing.
B15-0648-2TS 1750 RPM Isolation Valve MOVATs Tested also.
8", 150 lb. 60 RPM for P78 Suction CV-2802 Limitorque Condensate 100 psi 17 psi 2/2 3/3 Operable MOVATs Tested and DP Tested to Valan, Gate SMB-00 Storage Tank 112 psi 17 psi Operable maximum hydrostatic head from B15-0648-2TS 1750 RPM Isolation Valve the Condensate Storage Tank.
8", 150 lb. 60 RPM for P7A Suction CV-2803 timitorque Service Water 103 psi See 3/3 3.5/3.5 Operable MOV Identical to CV-3851 which Valan, Gate SMB-000 Loop I Isolation 103 psi CV-3851 Operable was selected for OP Testing.
814-0648-2TS 1750 RPM Valve MOVATs Tested also.
6", 150 lb. 37.5 RPM CV-2806 Limitorque Service Water 103 psi See 2.5/2.5 3.25/1 Inoperable MOV Identical to CV-3851 which valan, Gate SMB-000 Loop II Isolation 103 psi CV-3851 Operable was selected for DP Testing.
B14-0648-215 1750 RPM Valve MOVATs Tested also.
6", 150 lb. 37.5 RPM CV-2869 Limitorque Test Isolation 1519 psi 1490 psi 1.5/1.5 2/1.75 , Inoperable DP Tested within 10% of Design Anchor Darling, SMB-00 Valve for P78 1519 psi 1490 pst Inoperable Basis DP and MOVATs Tested.
Gate 1800 RPM Discharge 4-900-FW 25.2 RPM 4", 900 lb.
CV-2870 Limitorque Test Isolation 1802 psi See 1.5/1.5 2/1 Indeterminate MOV Identical to CV-2869 which Anchor Darling, SMB-00 Valve for P7A 1802 psi CV-2869 Inoperable was selected for DP Test.
Gate 1900 RPM Discharge MOVATs Tested also.
4-900-FW 18.8 RPM 4", 900 lb.
2
MOV DATA
SUMMARY
ARKANSAS NUCLEAR ONE - UNIT 1 EMERGENCY FEEDWATER SYSTEM SW11CH SLTilNGS VALVE OPERATOR VALVE DESIGN TEST DP PRIOR TO FINAL SWITCH AS FOUND TEST METHOD DESCRIPTION /
VALVE FUNCTION BASIS DP ADJUSTMENT SETTINGS VALVE JUSTIFICATION (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model, Motor Open Open Open/Close Open/Close Open Type, Model, RPM, Output Close Close Close Str2, Rating Speed (RPM)
CV-3640 Limitorque Service Water 103 psi See 4/4 2/<2 Inoperable MOV Identical to CV-3641 and Fisher. SMB-000 Crossover 103 psi CV-3641 Operable 3645 which were selected for Butt;rfly 1700 RPM Throttle Valve DP Testing. MOVATs Tested C123 0.5 RPM also.
18", 150 lb.
CV-3641 Limitorque Service Water 103 psi 48 psi 4/1.5 1.5/<2 Inoperable MOVATs Tested and DP Tested at Fisher, SMB-000 Loop II Throttle 103 psi 49 pst Inoperable maximum attainable DP due to Butterfly 1700 RPM Valve potential hammering affects 9123 0.5 RPM caused at Design DP in a 18", 150 lb. partially volded system.
CV-3642 Limitorque Service Water 103 psi See 3.5/2.5 <2/2 Inoperable MOV Identical to CV-3641 and Fisher, SMB-000 Crossover Throttle 103 psi CV-3641 Inoperable 3645 which were selected for Butterfly 1700 RPM Valve DP Testing. MOVATs Tested 9123 0.5 RPM also.
Is", 150 lb.
CV-3644 timitorque Service Water 103 psi See 2.75/3 2/2 Inoperable . MOV Identical to CV-3641 and Fisher, SMB-000 Crossover Throttle 103 psi CV-3645 Inoperable 3645 which were selected for Butterfly 1700 RPM Valve, Throttle DP Testing. MOVATs Tested 9123 0.5 RPM Valve From P4A to also.
IS", 150 lb. Auxiliary Cooling CV-3645 Limitorque Service Water 103 psi 58 psi 4/2.5 2/<2 Operable MOVATs Tested and DP Tested at Fisher, SMB-000 Loop I Throttle 103 psi 68 psi Inoperable maximum attainable DP due to Butterfly 1700 RPM Valve potential hammering affects 9123 0.5 RPM caused at Design DP in a 18", 150 lb. partially voided system.
CV-3646 Limitorque Service Water 103 psi See 3/3 2/2 Innperable MOV Identical to CV-3641 and Fisher, SMB-000 Crossover 103 psi CV-3645 Inoperable 3645 which were selected for Butterfly 1700 RPM Throttle Valve DP Testing. MOVATs Tested 9123 0.5 RPM also.
18", 150 lb.
3
MOV DATA SQ MARY.
ARKANSAS NUCLEAR ONE - UNIT 1 EMERGENCY FEEDWATER SYSTEM SWilCH SE1 TINGS VALVE VALVE OPERATOR VALVE DESIGN TEST DP PRIOR TO FINAL SWITCH AS FOUND . TEST METHOD DESCRIPTION /
FUNCTION BASIS DP ADJUSTMENT SETTINGS VALVE JUSTIFICATION (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model, Motor Open Open Open/Close Open/Close Open Type, Model, RPM, Output Close Close Close Siz2, Rating Speed (RPM)
'CV-3850 Limitorque Service Water 103 psi 92 psi <1/1 1.5/1.25- Indeterminate DP Tested within 10% of Design Westinghouse. SMI-00 Loop I Isolation 103 psi 92 psi- Operable Basis DP'and MOVATs Tested.'
Gate 3400 RPM Valve 6-150 # Gate 148 RPM 6", 150 lb.
CV-T'31 Limitorque Service Water 103 psi 90 psi 2/2.5 <3/2.5 Operable DP Tested within 10%'of Design V21an, Gate SMB-000 Loop 11 Isolation 103 psi 90 psi -Operable Basis DP and MOVATs Tested.
814-0648-2T 1750 RPM Valve G", 150 lb. 37.5 RPM
-4
MOV DATA
SUMMARY
ARKANSAS MUCLEAR ONE - UNIT 2 HIGH PRESSURE SAFETY INJECTION SYSTEM SWIICH SLIIINGS VALVE VALVE OPERATOR VALVE DESIGN TEST DP PRIOR 10 FINAL SWITCH AS FOUND TEST METHOD DESCRIPTION /
F UNCil0N BASIS DP ADJUSIMENT SETTINGS VALVE JUSTIFICAT10M (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model Motor Open Open Open/Close Open/Close Open Type, Model, RPM, Output Close Close Close 5122. Rating Speed (RPM) 2CV-5015-1 Limitorque HPSI Header, 1510 psl See 1/2 >2/1 Operable MOV Identical to 2CV-5035-1 Ttrget Rock, SMB-00 1RCP-A 1510 pst 2CV-5035 Operable which was selected for DP Globe, 6150 1700 RPM Testing. MOVATs Tested also.
2", 1500 lb. 39.0 RPM 2CV-5016-2 Limitorque HPSI Header, 1510 psi See 2/1.5 2/1.75 Operable MOV Identical to 2CV-5035-1 Ttrget Rock, SMB-00 2RCP-A 1510 psi 2CV-5035 Operable which was selected for DP Globe, 6150 1700 RPM Testing. MOVATs Tested also.
2", 1500 lb. 39.0 RPM 2CV-5035-1 Limitorque HPSI Header, 1510 psi 1470 psi 2/2 1.75/1.5 Operable DP Tested within 10% of Design Ttrget Rock. SMB-00 1RCP-8 1510 psi 1470 psi Ogerable Basis DP ana MOVATs Test'ed.
Globe 6150 1700 RPM 2", 1500 lb. 39.0 RPM 2CV-5036-2 Limitorque HPSI Header, 1510 psi 1459 psi 1.25/2 1.25/1.5 Operable DP Tested within 10% of Design Tcrget Rock, SMB-00 2RCP-8 1510 psi 1459 psi Indeterminate Basis DP and MOVATs Tested.
Globe, 6150 1700 RPM 2", 1500 lb. 39.0 RPM 2CV-5055-1 Limitorque HPSI Header, 1510 psi See 1.5/1.75 2.25/1.25 Operable MOV Identical to 2CV-5035-1 Terget Rock, SMB-00 1RCP-C 1510 psi 2CV-5035 Operable which was selected for DP Globe, 6150 1700 RPM Testing. MOVATs Tested also.
2", 1500 lb. 39.0 RPM 2CV-5056-2 Limitorque HPSI Header, 1510 psi See 2/1.75 <2/>l Operable MOV Identical to 2CV-5036-2 Ttrget Rock, SMB-00 2RCP-C 1510 psi 2CV-5036 Operable which was selected for DP Globe, 6150 1700 RPM Testing. MOVATs Tested also.
2", 1500 lb. 39.0 RPM 2CV-5075-1 Limitorque HPSI Header, 1510 psi See 2/2 >2/<2 Operable MOV Identical to 2CV-5036-2 Target Rock, SMB-00 1RCP-D 1510 psi 2CV-5036 Operable which was selected for DP Globe, 6150 1700 RPM Testing. MOVATs Tested also.
2", 1500 lb. 39.0 RPM 2CV-5076-2 Limitorque HPSI Header, 1510 psi See 1/2 2/<1.5 Operable MOV Identical to 2CV-5036-2 Target Rock, SMB-00 2RCP-0 1510 psi 2CV-5036 Operable which was selected for DP Globe, 6150 1700 RPM Testing. M0 VATS Tested also.
2", 1500 lb. 39.0 RPM 1
r MOV DATA
SUMMARY
ARKANSAS NUCLEAR ONE - UNIT 2 HIGH PRESSURE SAFETY INJECTION SYSTEM i SWIICH SETTINGS VALVE VALVE OPERATOR VALVE OESIGN TEST DP PRIOR TO FINAL SWITCH AS FOUND TEST METHOD DESCRIPTION /
FUNCTION BASIS DP ADJUSTMfMT SETTINGS VALVE JUSTIFICATIOM (TORQUE SWiiCH) (TORQUE SWITCH) OPERABILITY Component 10 Manufacturer Manufacturer, Model, Motor Open Open Open/Close Open/Close Open Type Model, RPM, Output Close Close Close
$123, Rating Speed (RPM) 2CV-5101-1 EIM Train A HPSI 1510 pst 1470 psi 4/4 3/2.6 Operable DP Tested within IDE of Design Copes-Vulcan, fB-00 Injection 1510 psi 1470 psi Indeterminate Basis DP and MOVATs Tested.
Globe. 1800 RPM Isolation DWG. E-175798 18.0 RPM 2", 1500 lb.
2CV-5102-2 EIM Train 8 HPSI 1510 pst 1251 psi 4/3 4/2.5 Operable MOVATs Tested and DP Tested at Copes-Vulcan, EB-00 Injection 1510 psi 1251 psi Indeterminate- maximum attainable DP due to Globe, 1800 RPM isolation conditions at time of test. MOV DWG. E-175798 18.0 RPM Identical to 2CV-5101-1.
2", 1500 lb.
2CV-5103-1 Limitorque Train A HPSI 350 psi Not DP 2/2 2/2 Operable MOVATs Tested. Not able to Weston SMB-000 Isolation 350 psi Tested Indeterminate establish DP around MOV without Hyfraulics, 1700 RPM making a system modification Gata, 75470 27.0 RPM due to a bypass around MOV.
4", 1500 lb.
2CV-5104-2 Limitorque Train B HPSI 350 psi Not DP 2/2 2/2 Inoperable MOVATs Tested. Not able to Weston SMB-000 Isolation 350 psi Tested Indeterminate establish DP around MOV without Hyfraulics, 1700 RPM making a system modification Cata, 75470 21.0 RPM due to a bypass around MOV.
4", 1500 lb.
2CV-5126-1 Limitorque HPSI 2P-89A 1510 psi Not DP 2.5/2.5 2.5/1.75 Operable MOVATs Tested. DP Testing would Borc-Warner, SMB-000 Recirculation 1510 psi Tested Operable require placing the HPSI pump Gata, 70440-1 1700 RPM in a degraded condition beyond 2", 1500 lb. 39.0 RPM normal system surveillance requirements.
2CV-5127-1 Limitorque HPSI 2P-89C 1510 psi Not DP 2/2.5 2/1 pperable MOVATs Tested. DP Testing would Borg-Warner, SMB-000 Recirculation 1510 psi Tested 'werable require placing the HPSI pump Gate, 70440-1 1700 RPM in a degraded condition beyond 2", 1500 lb. 39.0 RPM normal system survelliance -
j requirements.
l I
i i
l 2
MOV DATA Slp9tARY ARKANSAS NUCLEAR ONE - UNIT 2 HIGH PRESSURE SAFETY INJECTION SYSTEM ,
SWilCH SL111NGS VALVE OPERATOR VALVE DESIGN' ' TEST DP PRIOR TO FINAL SWITCH AS FOUNO TEST METH00 DESCRIPTION /-
VALVE FUNCTION BASIS DP ADJUSTMENT SETTINGS VALVE JUSTIFICATION (TORQUE SWITCH) (TORQUE SWITCH) OPERA 81LITY Component ID, Manufacturer Manufacturer, Model, Motor Open Open Open/Close -Open/Close Open Type, Model, RPM, Output .Close- Close Close Size, Rating Speed (RPM) 2CV-5128-1 Limitorque HPSI 2P-898 1510 psi Not DP '1/2 1.5/1 Indeterminate MOVATs Tested. DP Testing would Borg-Warner SM-000 Recirculation 1510 psi' Tested Operable require placing the HPSI pump Gata, 70440-1 1700 RPM in a degraded condition beyond, 2", 1500 lb. 39.0 RPM normal system surveillance requirements.
HPSI Pumps 1510 psi Not DP 1.5/1.5 2/1 Operable MOVATs Tested. DP Testing would 2CV-5628-2 timitorque Anchor Darling, SM-00 Recirculation 1510 psi Tested Operable require placing the HPSI pump Cate 3400 RPM isolation Valve in a degraded condition beyond 2556-3 25.0 RPM normal system surveillance 4", 900 lb. < requirements.
2CV-5630-1 Rotork Refueling Water 36 psi Mot DP 1/ MIN 1.5/ MIN Operable MOVATs Tested. DP Testing would Crane-Alloyco, 40A Tank Outlet to 36 psi Tested Operable require draining portions of the Gata 1800 RPM Train A system which would affect "! PSI M9126-EMD-SP 45.0 RPM pump suction. Hydro alternative 20", 150 lb.
not considered practical in lieu of MOVATs Testing.
2CV-5631-2 Rotork Refueling Water 36 osi Not DP 2/2 1.75/ MIN Operable MOVATs Tested. DP Testing would Crane-Alloyco. 40A Tank Outlet to 36 psi Tested. Operable require draining portions of the Gata 1800 RPM Train 8 system which would affect HPSI-N9126-De-SP 45.0 RPM pump suction. Hydro alternative 20*, 150 lb. not considered practical in lieu of MOVATs Testing.
2CV-5647-1 Rotork Containment Sump 65 psi Not CP 5/2 4.75/1.5 Operable MOVATs Tested.- 'DP Testing is not Crane-Alloyco, 70NA1 Recirculation to 65 psi Tested Operable feasible due to a water level in Gate 3600 RPM Train A containment would be required to.
N9126-EMD-SP 89.0 RPM establish DP.- Hydro alternative 24", 150 lb. not considered practical in lieu of POVATs Testing.
2CV-5648-2 Rotork Containment Sump 65 psi Not DP 5/3 4.25/0.75 Operable MOVATs Tested. DP Testing is not Crane-Alloyco, 70NA1 Recirculation to 65 psi Tested Operable feasible due to a water level in.
Gata 3600 RPM Train 8 containment would be required to N9126-EMD-SP 89.0 RPM establish DP. Hydro alternative-24", 150 lb. not considered practical in lieu of MOVATs Testing.
3
4 . .
MOV DATA SUleqARY ARKANSAS NUCLEAR ONE - UNIT 2 HIQi PRESSURE SAFETY INJECTION SYSTEM 5WilCH SLTTINGS DE51GN TEST DP PRIOR TO- FINAL SWITCH AS FOUND TEST METH00 DESCRIPTION /
VALVE VALVE OPERATOR VALVE BASIS DP ADJUSTMENT SETTINGS VALVE JUSTIFICATION fDNCTION (10RQUE SWITCH) (TORQUE LWITCH) OPERABILITY Component 10 Manufactuier Open Open Open Open/Close Open/Close Manufacturer, Model. Motor Close Type, Model, RPM, Output Close Close Sin, Rating Speed (RPM)
Containment Sump 65 psi Not DP 1.5/1 5.25/4 Operable M0 VATS Tested. DP Testing is not 2CV-5649-1 Rotork Crane-Alloyco, 70NA2 Recirculation to 65 psi Tested Operable feasible due to a water level in containment would be required to Gata 3600 RPM Train A Hydro alternative 90.0 RPM establish DP.
M9126-EMD-SP not considered practical in lieu 24", 150 lb.
of MOVATs Testing.
Containment Sump Not OP MAX / MIN 4.5/3 Operable MOVATs Tested. DP Testing is not-2tv-5650-2 Rotork 65 psi Crane-Alloyco, 70NA2 Recirculation to 65 psi Tested Inoperable feasible due to a water level .in containment wnuld be required to Gata 3600 RPM Train 8 establish DP. Hydro alternative N9126-EMD-5P 90.0 RPM not considered pr.sctical in 11eu 24*, 150 lb.
of MOVATs Testing.
4
MOV DATA
SUMMARY
ARKANSAS NUCLEAR ONE - CIT 2 EMERGENCY FEEDWATER SYSTEM SWilCH SE1 TINGS VALVE VALVE OPERATOR VALVE DESIGN TEST DP PRIOR TO FINAL SWITCH AS FOUND -TEST METHOD DESCRIPTION /
FUNCTION BASIS DP ADJUSTMENT SETTINGS VALVE JUSTIFICATION (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model, Motor Open Open Open/Close Open/Close Open Type Model, RPM, Output Close Close Close
$1ra, Rating Speed (RPM) 2CV-0340-2 Limitorque EFW Turbine Steam 1195 pst 360 psi 1.5/1.5 3/3 Operable MOVATs Tested and DP Tested Anchor Darling, SMB-00 Admission Valve 1195 psi 360 pst Inoperable to maximum attainable DP due Gata 1900 RPM to interactions between the 2550-3 25.00 RPM Trip and Throttle Valve.
4", 600 lb.
2CV-0711-2 Limitorque EFW 2P-7A Service 152 psi 99.4 psi 2.5/2.5 4/4 operable MOV Identical to 2CV-0716-1 Anchor Darling, SMB-000 Water System 152 psi 99.4 psi Inoperable which was selected for DP Gata 1900 RPM Isolation Testing. MOVATs Tested also.
2551-3 25.0 RPM C", 150 lb.
2CV-0716-1 Limitorque EFW 2P-78 Service 152 psi 99.4 psi 2/2.5 3.5/1.5 Ope-able MOVATs Tested and DP Tested Anchor Darling, SMB-000 Water System 152 psi 99.4 pst Inoperable to maximum DP attainable due Gata 1700 RPM Isolation to Service Water System 2551-3 25.0 RPM Condition during shutdown.
6", 150 lb.
2CV-0789-1 Limitorque EFW 2P-78 Supply 188 psi Not DP 2/2 <2/1 Operable MOVATs Tested. DP Testing would Anchor Darling, SMB-00 Cross Connect 188 psi Tested Operable require violating NPSH of EFW Gate 1700 RPM pump to establish DP. HYDRO 2552-3 24.0 RPM alternative not considered 8", 150 lb. practical in lieu of MOVATs Testing.
2CV-0795-2 Limitorque EFW 2P-7A Supply 188 psi Not DP 1.5/1.5 1.75/1.5 Operable MOVATs Tested. DP Testing would Anchor Darling, SMB-00 Cross Connect 188 psi Tested Inoperable require violating NPSH of EFW Gata 1900 RPM pump to establish DP. HYDRO 2552-3 25.0 RPM alternative not considered 8", 150 lb. practical in lieu of MOVATs Testing.
2CV-1000-1 Limitorque Main Steam to 1195 psi 1027 psi 2/2 1.5/1.25 Operable MOVATs Tested and DP Tested Anchor Darling SMB-00 EFW Pump Isolation 1195 psi 1027 psi Operable to maximum attainable DP due Gata 1700 RPM Valve to interactions between the 2S57-3 29.0 RPM Trip and Throttle Valve.
4", 600 lb.
I
a MOV DATA SupMARY ARKANSAS NUCLEAR ONE - L".ili 2 EMERGENCY FEEDWATER SYSTEM
$WIICH SLillNGS .
' VALVE DESIGN TEST DP PRIOR 10 FINAL SWITCH AS FOUND TEST METHOD DESCRIPTION /
VALVE VALVE OPERATOR FUNCTION BASIS DP ADJUSTMENT SETTINGS VALVE JUSTIFICATION (TORQUE SWITCH) (TORQUE SWITCH) OPERABILITY Component ID, Manufacturer Manufacturer, Model, Motor Open Open Open/Close Open/Close Open Type Model, RPM, Output Close Close .Close Sin, Rating Speed (RPM)
EIW 2P-78 1565 pst 1400 psi 1/2 4/3 Operable DP Tested within 10% of Design 2CV-1025-1 Limitorque Copes-Vulcan, SM-000 Discharge to 1565 pst 1400 psi Operable Bases DP and MOVATs Tested.~
Globe 1700 RPM Steam Generator A E-169461 17.0 RPM 4",-900 lb.
EFW 2P-7A 1565 psi 1400 pst 2.75/2.5 2.25/2.25 Operable DP Tested within 10% of Design 2CV-1026-2 Limitorque Anchor Darling, $2 -00 Discharge to 1400 psi 1400 psi Operable Bases DP and MOVATs Tested.
Cate 1900 RPM Steam Generator A 2554-3 26.0 RPM 4", 900 lb.
2CV-1036-2 timitorque EFW 2P-78 1565 psi 1e00 psi 1/1 2/2 Operable DP Tested within 10% of Design Anchor Darling, SMB-00 Discharge to 1565 psi 1400 psi Inoperable Bases DP and MOVATs Tested.
Gata 1700 RPM Steam Generator B W8321823 60.0 RPM 4", 900 lb.
2CV-1037-1 Limitorque EFW 2P-7A 1565 psi 1400 psi 1.5/1.5 2.5/2 Operable DP Tested within 10% of Design Anchor Darling, SMB-00 Discharge to 1565 psi 1400 psi Operable Based DP and MOVATs Tested.
Gate 1900 RPM Steam Generator A W8321824 67.0 RPM 4", 900 lb.
2CV-1038-2 Limitorque EFW 2P-78 1565 psi 1400 psi 1.5/1.5 2/2 Operable DP Tested within 10% of Design Anchor Darling, SN -00 Discharge to 1565 psi 1400 psi Operable Bases DP and MOVATs Tested.
Gata 1700 RPM Steam Generator A W8321823 60.0 RPM 4", 900 lb.
2CV-1039-1 Limitorque EFW 2P-7A 1565 psi 1400 psi 2.5/1.5 2.75/2.25 Operable DP Tested within 10% of Design Anchor Darling, SMB-00 Discharge to 1565 psi 1400 psi Operable Bases DP and MuvATs Tested.
Gata 1900 RPM Steam Generator B W8321824 67.0 RPM 4", 900 lb.
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. a MOV DATA
SUMMARY
ARKANSAS NUCLEAR ONE - UNIT 2 EMERGENCY FEEDWATER SYSTEM 5WIICH SETTINGS VALVE VALVE OPERATOR VALVE DESIGN TEST DP PRIOR TO FINAL SWITCH AS FOUND TTST METHOD DESCRIPTION /
FUNCTION BASIS DP ADJUSTMENT SETTINGS VALVE JUSTIFICATION (TORQUE SWITCH) (TORQUE SWITCH) OPERA 8ILITY Component ID, Manufacturer Manufacturer, Model, Motor 6 pen Open Open/Close Open/Close Open Type Model, RPM, Output Close Close Close Siz2, Rating Speed (RPM) 2CV-1050-2 Limitorque Main Steam to EFW 1195 pst 1040 psi 1.5/1.5 1.75/1.5 Operable DP Tested within 10% of Design Anchor Darling 5M8-00 Pump Isolation 1195 psi 1040 psi Operable Bases DP and MOVATs Tested.
Gata 1700 RPM Valve 2557-3 29.D RPM 4", 600 lb.
2CV-1075-1 Limitorque EFW 2P-78 1565 psi 1400 psi 2/1 3/3 Operable DP Tested within 10% of Design Copes-Vulcan, SMB-000 Discharge to 1565 psi 1400 psi Inoperable Bases DP and MOVATs Tested.
Globe 1700 RPM Steam Generator B E-169461 17.0 RPM 4", 900 lb.
2CV-1076-2 Limitorque EFW 2P-7A 1565 psi 1400 psi 2.5/2 2.25/2.25 Operable DP Tested within 10% of Design Anchor Dar11ng, SMB-00 Discharge to 1400 psi 1400 pst Operable Bases DP and MOVATs Tested.
Gate 1900 RPM Steam Generator B 2554-3 26.0 RPM 4", 900 lb.
2CV-1418-1 Limitorque Service Water '%2 psi Not DP 1.5/2 2/2 Operable MOVATs Tested. DP Testing would Clow Corp., SMB-000 Pumps Cross 152 psi Tested Operable involve placing the system in a Butterfly 1700 RPM Connect condition that would impact 20" Tricentric 50.0 RPM Reactor Shutdown Cooling Require-20", 150 lb. ments. Thus MOVATs Testing was utilized in lieu of DP Testing.
2CV-1419-1 Limitorque Service Water 152 psi Not DP 2/1.5 2.25/1.75 Operable MOVATs Tested. DP Testing would Clow Corp., SMB-000 Pumps Cross 152 psi Tested inoperable involve placing the system in a Butterfly 1700 RPM Connect condition that would impact 20" Tricentric 50.0 RPM Reactor Shutdown Cooling Require-20", 150 lb. ments. Thus MOVATs Testing was uttilzed in lieu of DP Testing.
2CV-1421-2 Limitorque Service Water 152 psi Not DP 1.5/1.5 2/2.25 Indeterminate MOVATs Tested. OP Testing would Clow Corp., SMB-000 Pumps Cross 152 pst Tested Inoperable involve placing the system in a Butterfly 1700 RPP Connect condition that would impact 20* Tricentric 50.0 RPM Reactor Shutdown Cooling Require-20', 150 lb. ments. Thus MOVATs Testing was utilized in lieu of DP Testing.
3
MOV DATA StNMARY ARKANSAS MUCLEAR ONE - UNIT 2 EMERGENCY FEEDWATER SYSTEM SWITCH SElilNGS DESIGN TEST DP PRIOR TO FINAL SWITCH AS FOUND TEST METHOD DESCRIPTION /
VALVE VALVE OPERATOR VALVE 8 ASIS DP 1.DJUSTMENT SETTINGS VALVE JUSTIFICATION FUNCTION (TORQUE SWITCH) (TORQUE SWiiCH) OPERA 8ILITY Component ID. Manufacturer Open Open Open/Close Open/Close Open Manufacturer. Model. Motor Close Type. Model. RPM, Output Close Close Siza Rating Speed (RPM)
Service Water 152 psi Not DP 1.5/1.5 2/2 Indeterminate MOVATs Testing. DP Testing would 2CV-1422-2 Limitorque Inoperable involve placing the systee in a Clow Corp., Spe-000 Pumps Cross 152 psi Tested condition that would impact 8utterfly 1700 RPM Connect Reactor Shutdown Cooling Require-27," Tricentric 50.0 RPM ments.- Thus MOVATs Testing was 20", 150 lb. utilized in lieu of DP Testing.
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