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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] |
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December 18, 1992 F 1CAN129202
, U. S. Nuclear Regulatory Commission j Document Control Desk Mail Station P1-137
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f Washington, DC 20555 l
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Subject:
Arkansas Nuclear Ono - Unit 1 l Docket No. 50-313
- License No. DPR-51 90._ Day Response to NRC 5 Safety Evaluation for Second Ten Year
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, IST Program and Relief Requests 3
i Gentlemen:
Entergy Operations has received the NRC Safety. Evaluation dated September-21, 1992, on the Second Ten Year pump and valve Inservice Testing (IST)
. Program for Arkansas Nuclear _One,. Unit.1 (ANO-1). This Safety Evaluation (SE) and the attached- Technical . Evaluation Report: (TER) reviewed the relief requests submitted by : ANO and requested a ninety _ day. response 4
providing additional justification ' for denied _ requests _. and additional information for two -provisionally approved requests. Followup responses 4
are requested within one -year- to describe- the process used in developing
-the ANO-1 IST Program and to address : ~ anomalies in the program. As-requested by the NRC: staff,-- any necessary chang 6s or- actions to resolve those anomalies that are in. agreement - with - the staff's - SE will - be
-completed within one year of the date of this letter,;or by the end of-the next refueling outage, whichever- is -later.
The attachments to this submittal provide - the information requested for the _ ninety-day : response.
Attachment:
'l provides- the_ additional-
~
in formation requested' including the ANO-1 : response to - denied requests.
Attachment:
2; is revised . relief . request No. 10T which' provides the'
. requested ' ~ details 'on alternative testing.
- Attachment _;3 contains a revision to request . No. 30 removing
- the valves for which relief was denied and provides the additiccal irformation requested _ for thef EDG air start system valves.
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U. S. NRC Cecember 18, 1992
{ 1CAN129202 Page 2 4 Should you have any questions concerning this submittal, please contact-
, me.
1 Very truly yours,
- n James . Fisicato j Director, Licensing i
1 JJF/JRH/kic Attachments i cc: Mr. James L. Milhoan l Regional Administrator i U. S. Nuclear Regulatory Commission Region IV.
611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear-Planc Road
) Russellville, AR 72801 Mr. Roby Bevan t- NRR Project Manager, Region IV/ANO-1 U. S. Naclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Thomas W. Alexion NRR Project Manag er, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop L3-H-3 One White Flint North 111555 Rockville Pike Rockville, Maryland 20852 t
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ATTACHMENT 1 REQUEST FOR ADDITIONAL INFORMATION
- 1. Relief Request No. 10 e NRC Reauest Relief Request No. 10 requests relief from the remote position indication verification requirements of Section XI, Paragraph IWV-3300, for the listed solenoid operated valves. The licensee has not proposed alternate testing for these valves.
, The licensee should develop alternate means of determining valve position so the remote position indication can be verified accurate at least once every two years.
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- ANO-1 Resoonse These solenoid valves have enclosed stems and no external means of determining valve position locally. Therefore these valves cannot be - directly observed to verify the accuracy of the remote position indicators associated with them. ANO-1 therefore proposes to verify the accuracy of these remote valve position indicators using other indications as allowed by 0M-10, Section 4.1.
Attachment 2, revised Relief Request No. _ 10, provides additional information on the alternative testing for valve position indication verification.
II. Relief Request No. 28 i
e NRC Recuest Relief Request No. 28 was submitted by letter dated October-20, 1988 (1CAN108809) and has not been revised by subsequent submittals. This request is not affected by any of the positions delineated in -Attachment 1 of GL 89-04 and is, therefore approved by GL 89-04. Relief Request No. 28 requests l relief from the pump testing requirements of the Code for the diesel fuel oil transfer _ pumps. The licensee proposes to operationally test the pumps as part of the Emergency Diesel Generator (EDG). functional test and to perform a full flew test during refueling outages. [The emergency diesel fuel oil transfer pumps are centrifugal pumps.] The licensee's proposal does not provide an adequate means to monitor for hydraulic or mechanical degradation of these pumps.
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- ANO-1 Resoonse The subject pumps are positive displacement type pumps, instead of centrifugal pumps as presumed in the NRC TER. They are of the rotary gear design and operate at a nominal speed of 1200 RPM. The pumps have a rated capacity of 10 gpm. The Emergency Diesel Generators (EDG) which the fuel oil transfer pumps supply consume approximately four (4) gpm of fuel oil when operating at rated electrical output. The pumps therefore have a 250% capacity by design. The pumps discharge to day tanks located inside the EDG skid rails. These tanks are vented to atmosphere.
Each pump is automatically started and stopped by level switches on its respective day tank. Activation of the low level switch causes the pump to start while activation of the high level switch causes the pump to stop. The capacity of the day tank between these two level switches is 60 gallons.
During EDG operation the pump operates for approximately ten minutes to fill the day tank once the low level switch is
- activated and is idle for approximately 15 minutes while the day tank level is depleted. This cycle is repeated for the duration of EDG operation. The_ pump will operate for two or three such 10 minute periods during a typical EDG surveillance.
The total pump run time per EDG surveillance may then be conservatively estimated as being .30 minutes. The base frequency for EDG surveillances is once per month. By estimating a total of 18 surycillances per year, the total run time per year for each pump is 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> for routine surveillances. Accounting for refueling outage testing, inclement weather starts, auto starts, other surveillances and storage tank recirculation would conservatively yield a total annual run time of less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or a usage factor of approximately 1/2%.
Due to the limited pump run time and pump design, normal wear of - this pump would only result in gradually reduced capacity over time due to rubbing wear of the gear teeth faces. This type of wear does not typically introduce incipient failure modes beyond those present on a new pump. Because of the excess capacity present in the design, loss of. capacity due to normal wear is not_ considered to be a safety concern. However, because it is desirable to be aware of significant capacity reduction due to this type of wear, ANO-1 will continue to perform the capacity test referred to in Relief Request 28 on a refueling outage basis or following significant maintenance.
The operability limit of that surveillance is the design value of the pump capacity, 10 gpm. Therefore, the test is quite stringent in terms of acceptance criteria in that design capacity is 250% of required capacit j. In 18 years of operation, both pumps have maintained design capacity without requiring corrective maintenance or-replacement related to a.
loss of capacity.
In addition to the operational test of the pump performed as part of the EDG functional test, ANO-1 commits to perform vibration data collection and analysis on these pumps on-at least a quarterly basis. This additional test is considered adequate to further detect abnormal year, rubbit.g , bearing deterioration, gear tooth breakage and other conditions potentially affecting the operational readiness of these pumps.
In summary, due to the above decribed factors, including pump design, excess capacity, usage t e.co r and the lack of the required instrumentation to allow Code e auirements to be met, ANO-1 proposes to test the pump as follows.
- 1) On at least a quarterly basis pump capacity will be verified to no greater than that required for full load operation of the EDG.
- 2) On at least a quarterly basis vibration data collection and analysis will be performed in accordance with OM-6 requirements.
- 3) On a refueling outage basis and after significant maintenance a capacity test will be performed by measuring the time required to fill the day tank between two indicated tank levels. The number of gallons added to the tank is then divided .by the time in minutes required to add that volume in order to determino a pump flow rate.
III. Relici u. quest No. 30
- NRC Reauest The evaluation of Relief Request No. 30 has been broken up into two parts for clarity. The first part requests relief from the stroke time measurements of Section~XI, Paragraph IWV-3413, for the emergency diesel generator (EDG) air start valves, 'SV-5218, SV-5233, SV-5237, SV-5239, CV-5218, CV-5233, CV-5237, and CV-5239. The licensee-has proposed to stroke time test these valves indirectly by measuring the starting times of the diesel generators.
Based on the determination that compliance with the Code requirements is impractical and burdensome to the licensee, and considering the proposed alternate 1 testing, relief should be
-granted w1th the following provisions. The licensee should determine if the EDG can start in the required time with only one air start train available. If so, some method to-independently verify _the operational readiness of both sets of valves _ should- be developed and implemented within one year or -
by the next refueling outage, whichever is longer.
_ _ _ _ _ _ _ - -_-_-___b
The second part requested relief form the stroke time measurement requirements of Section XI, Paragraph IWV-3413 for the EDG service water cooling valves, CV-3806 and CV-3807. The licensee has proposed to verify the stroke time indirectly by the starting time of the diesel generator.
Based on the determination that the licensee has not adequately demonstrated that compliance with the Code requirements is impractical or a hardship, and that the proposed testing does not provide reasonable assurance of operational readiness, relit' should not be granted as requested.
- ANO-1 Resoonse With regards to the first part of the NRC request, Relief Request No. 30 has been revised (Attachment 3) to provide adaltional information concerning the SDG air start valves.
These valves do not have position indicating lights or other means of directly monitoring the time required for a change in valve position. Exercising of the valves is accomplished during EDG surveillances at a frequency which meets or exceeds Code requirements. The base frequency for EDG testing is once per month. Surveillance procedures are written such that every other month the EDG is started both locally and remotely. At this time local verification is performed to insure that the EDG starts from each of the two air start trains. This approach is consistent with that requested by the staff to assure verification of the operational readiness of the EDG air start valves.
In response to the second part, Service Water System valves, CV-3806 and CV-3807 have been removed from the attached relief request and testing will be performed within the ASME Code requirement.
- . 1 ATTACllMENT 2 REI,lEF REQUEST NO.10 S.5 stem / Valves: Reactor Coolay1 Svstem Vent Valves SV-1071, SV-1072, SV-1073, SV-1074, SV 1077, SV-1079, SV 1081, SV 1082, SV 1083, SV 1084, SV-1091, SV-1092, SV 1093, SV 1094 Beactor Buildinc flVAC Isglation i Valves SV-7457, SV-7459, SV-7467, SV 7469, SV-7454, SV-7456, SV-7510, SV-7512, SV-7479 Emercency Feedwater Flow Contiol Valves CV-2645, CV-2646, CV-2647, CV 2648 Sampic System Isolation Valves SV 1440, SV 1443, SV-1818, SV 1840 Main Steam to EFW Pumo Turbine Supply Valvg SV-2613 Function: Egaetor Coolant System Vent Vahrs SV-1077, SV 1079 - Pressurizer High Point Vents These solenoid operated valves are used to vent non-condensable gases from the pressurizer during startup operations and may be used whenevar reactor coolant system conditions are such that non-condensable gases may have accumulated in the pressurizer.
SV 1081, SV-1082, SV-1083, SV-1084 - RCS Loop A liigh Point Vents These solenoid operated valves are used to vent non-condensable gases from the "A" reactor coolant loop during startup and may be used whenever reactor coolant system conditions are such that non-condensable gases may have accumulated in the "A" reactor coolant loop.
SV-1091. SV-1092, SV-1093, SV-1094. RCS Loop B High Point Vents These solenoid operated valves are used to vent non-condensable gases from the "B" reactor coolant loop dunng startup and may be used whenever reactor coolant system conditions are such that non-condensable gases may have accumulated in the "B" reactor coolant loop.
SV-1071, SV-1072, SV-1073, SV 1074- Reactor Vessel High Point Vents These solenoid operated valves are used to vent non-condensable gases from the reactor vessel head during startup whencycr reactor coolant system conditions are such that non-condensable gases may have accumulated in the reactor vessel head.
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NITACllMENT 2 REl.lEF REQUEST NO.10 Reactor Buildina HVAC isolation Valves SV-7457, SV-7459, SV 7467, SV-7469 - Hydrogen Sampler Isolation Valves These solenoid operated valves serve as isolation valves for the redundant hydrogen sample systems. They are also the first valve outside the reactor building in this piping spiem and are credited with a containment isolation function.
SV-7454, SV-7456, SV-7479. RCS Leak Detectc.t isolation Valves These valves provide isolation of the monitors used for normal operation RCS leak detection. These valves are credited with a containment isolation function.
SV-7510, SV-7512 - Post Accident Sampling System (PASS) Isolation Valves These valves provide isolation of the PASS. These valves are credited with a containment isolation function.
E_m_qreency Feedwater_Elow Control Valves CV-2645, CV-2646, CV-2647, CV-2648 These modulating DC solenoid valves control the flow of EFW to the steam generators following an actuation of the Emergency Feedwater System.
Samole Sistem Isqlation Valves S
SV-1440, SV-1443 These normally closed valves provide a containmcnt isolation function for the Post Accident Sample System sample supply and return lines to and from the reactor building sump.
SV-1818, SV-1840 These normally closed valves provide a containment isolation for reactor coolant system sampling lines exiting the reactor building.
Main Steam Valve SV-2613 - Main Steam to Emerger.cy Feedwater Pump Turbine This valve is used in the startup sequence of the steam driven emergency feedwater -
pump. This valve provides a steam flow path to roll the turbine to an initial specci of -
900 RPM prior to opening of the main steam supply valve.
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ATTACilS1ENT 2 ,
REl.lEF REQUEST NO.10 Code Class: Reactor Coolant system Valves - Class 1 Reactor Buildine HVAC Valves - Class 2 EFW Flow Control Valves - Class 3 Sample Isolation Valves - Class 2 Main Steam Valve - Class 3 Code Category: Reactor Coolant System Valves - Category B j Reactor Buildine HVAC Valves -Category A EFW Flow Control Valves - Category B Samole Isolation Vahrs - Category A Main Steam Valve Category B Code Requirement: IWV-3300 VALVE PMITION INDIC-\ TOR VERIFICATION
" Valves with remote position mdicators shall be obscried at least once every 2 years to verify that valve operatio' is accurately indicated."
Relief Requested: The enclosed stem and lack of other loca. _ Ucation devices prohibits direct visual verification of valve position. ANO-1 therefore proposes to verify the accuracy of these remote valve position indicators using other indications as allowed by OM-10, Section 4.1.
Basis for Relief: These solenoid valves br c encbsed stems and no external means of determining valve position locclly. Tiierefore C.m ulves cannot be directly observed to verify the accuracy of the remote position indicators associated with them.
Alternative Testing: Valve position verification shall be performed on the subject valves by compliance with OM-10, Section 4.1, Valve Position Verification; specifically,"Where local obsen'ation is not possible, other indications shall be used for verification of valve opeiation." These 4 verifications employ system parameter indications and testing results to provide assurance that valve position is accurately indicated.
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- ATTACllMENT 3 i
RELIEF REQUEST NO. 30 i
System: Emergency Diesel Generator Air Start l
l Valves: CV-5218, CV 5233, CV-5237, CV,5239, SV-5218, SV-5233, SV 5237 AND SV 5239 Fenetion: These valves comprise the means by which starting air is admitted to the Emergency 2
Diesel Ucnerators (EDG's) air start motors. An electrical signal from the EDG start circuitry causes one of the two solenoid valves associated with a particular EDG to -
l change position such that pressurized air is admitted to the pinion engagement l mechanism of the first of two air start motors arranged in series. As the pinion is
. engaged, a port is opened to allow air flow to the pinion engagement of the second air
! start motor. Air flow then continues to the associated control valve to cause it to open to -
i admit air to the vaned air start motors in order to crank the EDG. When the EDG starts,
, speed sensors cause the start signal to be removed at which time the solenoid valve repositions to isolate starting air to and depret surize the piping to the air start motors pinion engagement mechanism and the air supply control valve. This action allows the
- air supply control valve to close ind the pinion to disengage from the EDG ring gear,
, One solenoid valve and one control vahc comprise one train of air start capability. An alternator switches the start signal such that the two trains operate in an alternating '
l fashion each time the start signal is generated.
Code Class: Non-Code components includ:d based on the safety function performed.
- Code Category
- Category B Code Requirement: IWV-3413 POWER OPERATED VALVES (b) The stroke time of all power operated valves shall be measured ta the nearest second, for stroke times of 10 seconds or less, or 10% of the specified limiting stroke for full-
- stroke times longer than 10 see w henever such a valve is full-stroke tested.
Relief Requested: ANO-1 requests relief from the stroke timing requirement for these power operated vahes.-
Basis for Relief: These valves do not have position indicating lights or other means of directly -
monitoring the time required for a change ir. valve position Exercising of the valves is accomplished during EDG surveillances at a frequency which meets or exceeds Code requirements. The proper operation of the soleno..i valve and its associated air control valve can be monitored by virtue of proper starting operation of the EDG. The normal '
- time required from the receipt of a start signal for the EDG to start and achieve rated
- speed and voltage is 9 to 13 seconds based on surveillance test results. The required time per the ANO-1 Technical Specifications is less than 15 seconds. Therefore, by virtue of proper EDG starting operation, the air start solenoid and air control valves are verified to be operating properly. l i
- ' Alternative Testing
- ANO-l will monitor proper operation of the air start solenoid and air control l valves by verification of EDG operability dt. ting the EDG surveillance. The base frequency for - ;
EDG testing is once per month. Surveillance procedures are written such that every 1
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A'ITACllMENT 3 REl.lEF REQUEST NO. 30 other month the EDG is started both locally and remotely. At this time local verification is performed to insure that the EDO starts from each of the two air start trains. The time required to start and achieve rated speed and voltage on each train is monitored and recorded. If the requirca time is greater than 15 seconds for either train, the EDG is declared inoperable and corrective actions taken. Significant degradation or failure of any one valve would thatefore be identified by failure of the respectisc EDG to satisfy its t urveillance requirements.
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