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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] |
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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 August 24, 1979 -
1-089-13 Di re ct or of Nu clea r React or Reg ula tion ATTN: Mr. R obe rt W. Reid, Chief Ope rating React ors B ra nch #4 U. S. Nu clea r Reg ula t o ry C ommis s i o n Wa shingt on, D. C. 20555 S ub j e ct : A rka ns a s Nu cle a r One-Unit 1 Docket No. 50-313 Li ce ns e N o. DPR-51 Deg rad e d Grid Voltage (File: 1510)
Gentlemen:
The f ollowi ng is p r ovid e d t o:
- 1) C om p l e t e ou r re s p o ns e t o ou r Ju ne 20, 1979, letter
- 2) Re s p o nd to your le t te r Augus t 16, 1979
- 3) Respond to our telecon of August 21, 1979.
Pa rt 1. Response t o June 20, 1979, lette r Item 7.
F o r e a ch Se ction of IEEE 279, d e sc ribe h ow the p r op os ed u nd e r-voltage p rotection modifica tion c om p lie s with the c rit e ria .
R e s p o ns e :
The f ol l owi ng briefly d e sc ribe s h ow ou r Mills t one Modifi-cations as p rop osed to you in ou r Augus t 23, 1978, le t te r c onf o rm to the requi reme nt s of each Se etion of IEEE 279.
- a. Ge ne ral Functional Requirements - The devices and equip-ment used a re qualified f or Class lE application and the pe rf ormance of the devices is highly reliable. The system is d e sig ned s o that the p r ot e c t iv e action is a u t o-matically initiated as the system re a ch e s p re se nt levels.
79083oogyqb, MEMBEA MiOOLE SOUTH UTIUTIEs SYSTEM
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1-089-13
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Mr. Rob e rt W. Reid August 24, 1979
- b. Single Fa ilu re C rit e ri on - The two load g roups a re pro-
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vided with red u nd a nt protective actuation c ont rol systems. Also, wi ri ng f or ea ch of the two c ont rol gystems is routed in sepa rate Class 1E raceways.
- c. Quality of C omp one nt s and Modules The devices used for the two p rotection sys tems a re qualified f or Class lE application.
- d. Equipment Q u ali f i ca t i ons The available type test data f or Class 1E c omp one nt s qualifications c onf i rms the req ui red sa tis f a ct o ry pe rf o rma nce of the p r ote ction equipment unde r the e nv i r o nme nt al conditions stated in Se ction 3. 7 & 3.9 of the IEEE-279-1971.
- e. Channel Int eg ri t y The p rot e c t ive systems p rop osed have been desig ned f or f ail safe ope rati on. The devices and ci rcuit ry used a re Class lE and the re f ore shall rema i n ope ra ti onal unde r ext reme e nvi r onme nt al , e ne rgy supply a nd accident conditions.
- f. Channel Independence The equipme nt , devices, a nd race-ways for one Class 1E system a re i nd e p e nd e nt and physically sepa ra ted f r om the othe r sys tem . The circuits for the two Class 1E protective systems a re also routed in sepa ra te raceways.
- g. C ont rol a nd P r ote ct i on Sys tem Int e ra ct i ons All the equipment is c ons id e red pa rt of the protection system which is d e sig ned t o me e t the requi reme nt s of IEEE 279 with the exception of the RCP sta rting bypass initiation which is a non-Class lE system. F or mo re detail, please re f e r t o a nswe r t o Question 6.
- h. Is ola ti on Devices Is ola tion devi ces a re not used as the systems a re c om p le t e l y Class lE.
- i. Single Ra nd om Fa il u re a nd Multiple Fa il u re s Re sult ing f r om a C redible Single Event - The re a re no single f ailure points as the systems a re c om p le t el y Class lE, s e p a ra t e ,
and red u nd a nt .
- j. De riva t i on of System Inputs - The u nd e rv ol t ag e relays p r o-posed at the 480'/ ESF buses will mea s u re the system de-g rad ed c ondi t 1 ons di re ctl y and initiate the p r ote ct iv e action at the system level within its repective load group.
2033 018
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Mr. Rob e rt W. Reid August 24 1979
- k. Capability f or Se nc or Ch e ck s Ihe 92% unde r v oltage
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relays have been p r ovid ed with f u nct i onal test switches. Pe riodic t e s t i ng will e nsu re the se ns o rs '
op e ra ti onal capability.
- 1. Capability f or Test and C a lib ra t i o n The system has the capability f or testing. Calibration of devices is discussed unde r item 9. c.
- m. Cha nnel Bypass or Rem oval f r om Ope ra tion As explained in the reply t e Ques tion 3, of ou r let te r of July 12, 1979, systems have the capability t o be tested in se rvice without initiating a p rot e ct ive action at the system level a nd also continue t o mo c + the single f ailu re c rite rion .
- n. Ope ra ting By; Pass The p r ot e c t iv e action of the two systems can ue bypassed manually d u ri ng s ta rting of the RCP m o t o rs . The ope rating bypasses a re Class lE.
- o. Indication of By-passes The by-passes will be ala rmed in the C o n t r ol R o om ,
- p. Access t o Mea ns f o r By Passing Manuui bypass of p r o-tective action is p rovid e d th rough test switches. The access to the test swi t ch e s will be u nde r the admin-is t ra t ive c ont rol of the Shift S up e rvis o r . The RCP bypass will u nde r admi nis t ra tive c ont rol of the Shift S upe rvis or.
- q. Multiple Set Points The p r ot e ct iv e devices a re set at one set point only.
- r. C om p le t i on of Protective Action Once It Is Initiated Once the protective action has been initiated the offsite s ou rce is a ut oma t ical ly disc onne ct ed and the on-site source (Diesel) is made available within a sh o rt time.
The p r ot e c t iv e action will go t o c om p l e t i o n once initiated.
- s. Manual Initiation - Manual c ont r ol is provided on each of the two b reake rs f or c onnecting or disc onnecting the off-site a nd on-site s ou rce s to the a uxilia ry p owe r sys t ems.
Ma nual initia tion .requi res ope ra tion of a minimum numbe r of switches.
- t. Access to Set Point Ad j us tme nt Calib ration and Test P oint s Access to Set Point Adjustment, Calib ra tion a nd Te s t Points is c ont r ol le d Adminis t ra tively u nde r the Shift Sup e rvis o r a nd is limited to qualified pe rs onnel .
2033 019
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1-089-13
- M r. R ob e rt W. Re id August 24, 1979
- u. Identification of Protective Action - The b re ake rs for the of f-site and on-site s ou rces have close a nd t rip indica-tions in the c ont r ol r o om to identify the protective actions.
- v. Inf o rma ti on Re ad Out - Sufficient monit o ring has been p r ov id e d in the c ont r ol r o om which will enable the op e ra +. o r t o kn ow the de te rio ra ting c ondi t i ons of the s y s t eens .
- w. System Repair - Pe riodic t e s t i ng of the system will en-su re the detection of the malfunction of c omp one nt s or m od ule s . Plug in type of c om p o ne nt s a re used wh e re possible s o that the faulty units can be replaced, re-p a i red or adj us ted exp edi ti ous l y . Al s o the system pro-tective action is designed such that the f ailu re of one u nde r v ol t age relay will not disable protective action.
- x. Identification - The equipment and wi ri ng of the cwo p r o-tective systems have been id e ntif ied as red a nd g ree n channels.
Item 9c.
The ANO-1 a nal y s is assumed that p r ot e c t iv e action would be executed at ( o r ab ove) the cal cula t ed valve of 92% (Mot or-base) v ol t ag e . Indicate: (c) a l l owa n ce (above 92%) used to a c c omm od a t e d rif t s . Describe the basis f or de te rmining these all owa nce s. De s c ribe the bases f o r d e t e rmi ning the n om i n a l setpoint which provides maximum protection consis-t e nt wi th minimum spu riris shedding f r om the pe rf e rred p owe r s ou rce (i.e., ele ct ric g rid) .
Re s p o ns e :
The 4 6 0 u nd e rv ol t age relays a re s olid state relays set to t rip at a specific v olt age . The physical ina ccu ra cie s of the relay a re within the e rror ba nd of calibrated test equipme nt and a re the re f ore indisce rnible . Upon installation of the relay, it will be calibrated us i ng ins t rume nt s that a re cali-b ra t ed t ra cea b le to the National Bu re a u of S t a nd a rd s .
To date, no inf o rma tion exis t s on possible d rif t of the relay.
Upon installation, the . relay will be calib ra t ed at the f i rs t refueling outage f ol l owi ng ins t alla ti on. Allowa nce f or d rif t will be made at that time if applicable. D rif t is expected to be mi nim al if a ny .
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1-089-13 Mr. Robe rt W. Re id August 24, 1979 Pa rt 2 NRC August 16, 1979, Letter
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Item 2 P r ovid e the 480 volt a nd 416 0 v ol t AC ele ct rical schematics sh owing the p rop osed d eg rad ed v olt age p rotection system (b oth levels of p r ote ct i on) .
Response
The req u e s t ed sch ema tics a re s h ow n on d rawi ng E-99 sheet 1 Rev. 8-1 which was attached to ou r lette r July 12, 1979, as pa rt of our response t o I t em 6.
Item 3 The p r op os ed u n d e rv ol t a g e relays will have test plug capability.
Describe the test plugs, their function, a nd their ef f ect on the relay. How is the test p e rf o rme d a nd s pe ci f i cal ly what is the function which is tested? Provide a schematic which ill us t ra te s the f u nct i on of the test plug on the relay.
Re s p ons e :
At tached is ins t ruction ma nual G.E H-1768A s h owi ng the connect-ing plugs. A description of the test plug is sh own by the attached publication gel- 2 53 7 2. When the connecting plug is re m ov e d and a test plug is inse rted in its place, all relay points a re accessed, both the relay side a nd the s ou rce side, since each side is brought to a se pa ra te t e rmi nal on the test plug.
Since this relay is an u nd e rv ol t ag e relay with contact cl osu re output set to close at a specific set point, the relay contact cl osu re can be ve rified at the set point wi th out execution of the desired final action.
Item 4 a) We i n t e rp r e t your response to say that a calib ra t i on f ol l owe d by a functional test will be c ond u c t e d p ri o r to i ni t i al ope ra ti on of this system and d u ring each re f u eli ng outage the rea f te r. While we believe this test int e rv al is appro-priate f o r calib ration pu rp oses, op e rab ili ty sh ould be ve rified by pe rf o rming a functional test more of ten, e.g.,
monthly o r qua rte rly. Propose a suitable test i nt e rval for functional testing.
2033 02I
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1-089-13
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Mr. R ob e r t W. Reid August 24, 1979 b) We specifically requested a description cf the test pro-g ram which would ve rif y ( once prior to initial op e ra t i on of the protection system) that no unacceptable voltage would be applied to ESF equipment when the g rid is at the defined "mi nim um- n o rmal" level. Describe the test
- - og ram ,
c) We a re ' once rned about the ad equ a cy of the v ol t ag e applied to ESF equipment during the s ta rt ing of la rge non-Class lE m ot o rs , su ch as react or c oola nt pump mot ors. This is a maj or conce rn. You" analysis indicates that the l owe s t acceptable v ol t ag e is 92% f o r a n eigh t-s e c ond d u ra ti on.
Du ring the s ta rting of la rge motors, you have stated that the v ol t age falls bel ow 92% and stays for longe r tha n eigh t seconds. P r ov id e the valves of these lowe r v oltages a nd d u ra t i on for the s ta rting of each la rge n on-l E mot o r (u nde r a p p rop ria t e plant and g rid c onditi ons) . Explain why voltage levels b e l ow you r minimum v ol t a g e acceptance c rite rion should be c ons id e red acceptable. Please note that the voltages when s ta rting la rge mot o rs must be d e t e rmi ne d to be accept-able ( on a n ap p rop ria te basis) be f ore one c onside rs the accept-ability of a de s ig n f e a tu re that would bypass the deg rad ed voltate protection during such sta rtings .
Re s p o ns e :
a) We again p r op ose our re s p o ns e to this item in ou r le t te r of July 12, 1979, as ap p r op ria te . This is based on Te ch ni cal Specification requi reme nt s for othe r safety systems. ANO-1 Technical Specifications re qu i re Functional Testing of on-sata p owe r s ou rces and ECCS once per 18 months. We c not conside r the p rop os ed Millstone M od i f i c a t i o ns t o be of g reate r saf ety im p o rt a nc e than the a b ov e systems and believe testing f requencies consistent with these above systems is a p p r op ria t e .
A testing f reque ncy of once per 18 months is consistent -
with the requi rem e nt s of NRC Position 3 t ra nsmit ted to us by Mr. D. K. Davis' le t te r of June 3, 1977.
b) After i ns t al la t i on, the system will be dem ons t rated ope-ra b le by a functional test as de s c rib e d in ou r le t te r of July 12, 1979, response t o Item 4a.
c) Y ou r inte rp retation of the 92% bus voltage c rit e ria is not c o rre ct in that it is not mi nim um al l owa b le in all cases.
Ap p e nd ix 1 page 5 of ou r lette r of August 23, 1978, identi-s fies 90% c omp one nt v ol t ag e (92% bus v ol t ag e ) as limiting f or continu ous ope ra ti on but notes that "Sa f e t y- re la t ed
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2035 022
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1-089-13 Mr. Robe rt W. Re id August 24, 1979 mot o rs we re designed to p rovid e full load torque d u ri ng m om e nt a ry dip t o 75% of rated v ol t ag e wh e n othe r mot o rs' a c ce le ra te on the system. On that same page it states that "Du ri ng la rge mot or s + a rting , v ol t ag e s at the 4160V ESF busses we re ma rgina }[, not unacceptable. The voltage dips on the safety rela ted busses do not exceed 75% of ra + ? d voltage d u ri ng s ta rting of React or Coola nt Pumps.
Th e re f o re, the v ol t ag e dips due t o RCPs s ta rting a re within accepta nce c ri t e ria .
H oweve r, in a situa tion wh e re safety systems would be re-quired to op e ra t e (e.g., the potential f or an accident e xi s t s) , the RCPs would be ru n ni ng . In addition, IE or f or s ome t ime af te r the a ccide nt . We, the re f o re , p rop os e deletion of the a u t oma t i c by-pass of the u nd e rv ol t ag e relays as the RCPs will not be used d u ri ng the time f rame safety equipme nt is requ i re d .
The mag ni tude of the v ol t ag e dip due t o RCP s t a rt i ng is with-in the acceptance c rite ria for the safety equipment. H oweve r, the length of the v ol t age dip may exceed 8 se c onds , the re f o re ,
as RCPs must be s ta rt ed d u ri ng normal plant s ta rt up and may be resta rted at s om e belated time f ol l owi ng a n a c cid e nt , we p r o-pose installation of a manual by pass of the u nd e rv ol t age relays f or RCP s ta rting t o av oid spu rious t rips. This by pass will be class lE, Adminis t ra tively c ont r olled , and will a l a rm in the C o nt r ol R o om wh e n a ctua ted .
Item 5 Submittal V-2 A a nd V-3 A s h ow s mot or base v ol t ag e on 4160V bus highe r tha n designed maximum 110% a nd that on 480V bus as ma rgi nal . Fu rthe r, if t ra ns f o rme r se c ond a ry v ol t ag e gain (due t o highe r applied v oltage (22kv) on l owe r ra t e d (21.5kv) p rima ry wi ndi nf s ) is added to the bus v ol t ag e s , the result will be unacceptably highe r v olt ages on both 4160 and 480V equipment.
The submittal fu rthe r i nd i ca t e s that you r assumed no load con-dition includes 25% of the t ra ns f o rme r capacity as running load on 4 80V bus a nd 1.885 MVA o n 416 0V bus. You a re requested to justify 1.0 PU tap u nde r the a b ove mentioned concerns. Also p r ovid e the a nal y s is that gives acceptable v ol t ag e s on Class 1E equipment f or maximum g rid voltage and a realistic no load c ondi t i on (su ch as 5% or less of the t ra ns f o rme r capacity as 480V running load).
Re s p o ns e :
As noted, cases V-2A a nd V-3 A d o sh ow bus v ol t ag e s slightly a b ov e 1.1 P.U. However, the bus v ol t age s do not take int o c ons id e ra tion the v ol t ag e d r op s f o rm the bus to the actual c omp one nt s . Wh e n these voltage d rop s a re taken into c ons id e ra-
,
ton, the ove r excita tion is mi nimal .
2033 023
1-089-13 Mr. Rob e rt W. Re id 8 August 24, 1979 In addition, the a b ov e 2 cases we re p r ov id e d in re s p ons e to a specific question cnd a re not re p re s e nt a t iv e of as v ol t- ,
ages safety equipment would eve r expe rience. These cases assume essentially no load on the busses. Du ring the modes of which safety systems a re required (e.g. M od e s 1, 2, 3, &
4), the re must be sig nif ica nt othe r pla nt loads on the busses f or the plant t o be in that M od e . O nl y in the case of a loss of of-fsite p owe r (in Modes 1, 2, 3 a nd 4) would the re be no non-safety loads running and in this case, safety loads would be p owe red f r om the Diesel Ge ne ra t o rs .
The re f ore , we conclude that the safety systems will not expe rie nce a ny ove r ex cita ti ons.
Rega rdi ng you r re f e re c ne t o t ra ns f o rme r to t ra ns f o rme r s e c onda ry gain due t o applied v ol t ag e of 22kv on t ra ns-f o rme r winding of 21.5 kv. This gain was taken int o a c-c ou nt in the c om p u t a t i o n a nd a p pe a rs as a tap 0.9'73 on the top right c o rne r of the case.
Item 6 Our review of the bypass ci rcui t for the s ta rting of la rge m ot o rs has de t e rmined that this single bypass is a single f ailu re point for ope ration of ESF equipme nt. This is a major concern. Each la rge mot or has a single time delay device. (This t ime r d oe s have two output c ont ra ct s wh i ch ope ra t e in a s e p a ra t e schemes to bypass the d eg raded v olt-age protection in both divisions of ele ct ric p owe r) .
H oweve r, the postulated f ailu re of the time r me chanism itself f o r a ny su ch mot or can result in the loss of v ol t ag e protection in both ele ct rical divisions. This single f ailu re p o t e nt ial must be delineated, possibly by using two time r me chanisms pe r mot or.
See ou r c omme nt ea rlie r rega rdi ng Item 4c.
Response: .
As discussed in ou r re s p o ns e t o It em 4 c ab ove , we p rop ose deletion of the aut oma tic b ypas s. The p rop os e d manual bypass will be Class lE a nd re d u nda nt .
Item 8 Your re s p o ns e dated July 12, 1979, indicated that load ahedding of essential loads was p rop osed only when the s ta tion auxilia ries a re supplied p owe r f r om s ta rt up t ra ns-f o rme r N o . 2 (ST 2). No load shedding would be applied to s ta rt up t ra ns f o rme r N o. 1 (ST 1) u nde r the same c ond i t i ons .
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2033 024
1-089-13 Mr. Rob e rt W. Reid 9 August 24, 1979 Y ou r Augus t 23, 1978 analysis and all our subsequent c om -
mu ni ca ti ons have indicated that wh e n ope ra ting on ST-1 d u ri ng
" a b n o rm a l " c ond i t i ons , shedding of non essential loads was essential t o maintain accep table v ol t ag e . Expla'r this ch a ng e .
Sh ow why load shedding is not needed f o r S T-1.
Re s p o ns e :
D u ring c onve rs a t i ons with the staff in May, 1979, it was ag reed that the initial g rid c ond i t i ons assumed in our submittal of Augus t 23, 1978, we re ov e rl y res t rict ive a nd c onse rva t ive . We p rop osed new c o nd i t i ons that we re more realistic wh i ch would result in a nal ys es m o re c ons i s t e nt with NRC re qui reme nt s . These new a s s ump t i ons we re ag re ed t o by the Staff and we re t ra nsmi t ted t o you by ou r le t te r of May 21, 1979, along with new analyses.
Due to the ov e r c ons e rva t ism in the August 23, 1978, sub-mittal, it was ne ce s sa ry to shed loads on ST-1 t o a s su re adequate v ol t age . H owev e r, u nde r the m o re re al i s t i c (yet still v e ry c ons e rva t ive) a s sump t i ons of our May 21, 1979, le t te r, a nal y s e s indicate that load sh ed di ng up on fast t ra ns f e r to ST1 is no longe r ne ce s s a ry . Load shedding upon fast t ra ns f e r to ST 2 is s t il l ne c e s s a ry .
Item 9 As you have indicated, your re s p o ns e is not c om p l e t e . You have c ommi t t ed to p r ov id i ng inf orma tion on the set points of the u nde rv ol t age rel ay s . P r ovid e the inf o rma t i on or a schedule for providing the i nf o rma tion.
Ou r c once rn he re is a p r ope r s tack up of the t ole ra nce s in the system including the i na c cu ra cie s of ins t rumentation in ad j us t i n; the set points t o assu re that the v ol t ag e applied t o ESF equipment is not unacceptable. In you r dis cussion display su ch t ole ra nces a nd e rror ba nds a nd their stack up t o as su re that the v olt age applied to the ESF equipment is -
n ot unacceptable.
Anothe r conce rn is that, after c ons id e ring the buildup of ina c cu ra cie s , etc., the nominal setpoint sh ould not be so h ig h as to cause the safety buses t o be s pu ri ously di s c on-nected f r om the p re f e rred p owe r s ou rce .
Re s p o ns e :
See ou r re s p o ns e t o it em 4a in Pa rt 1 of this le t te r.
Pa rt 3 Telecon on August 21, 1979
,
Item 1 - RCP Bypass 2033 025
1-089-13 Mr. Rob e rt W. Reid August 24, 1979
Response
See ou r re s p o ns e t o It ems 4 c a nd 6 of Pa rt 2 above. -
Item 2 - C omp le t e d a nswe rs t o NRC's le t te r of June 20, 1979, letter.
Response
See Pa rt 1 above.
Item 3 P r ovid e a listing of equipme nt that c om p r i s e the 4160V and 480V running load as s h ow n on Table 2 to AP&L's lette r of May 21, 1979.
Re s p ons e :
Table 1, a t t a ch e d , is a listing ef all running loads assumed in the ab ove analysis.
Ve ry t ruly y o u rs ,
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. David G. Trimble Ma nage r, Li ce ns i ng DCT/JTE/ew At ta chme nt 2033 026 1
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INSTRUCTIONS GEH-1768A Su r t a s t o t s GEH.1768 UNDERVOLTAGE RELAYS ex-w y
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b Fig. I The Type I AVHE Relay Disassembled O
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UNDERVOLTAGE RELAYS TYPEIAV o] g INTRODUCTION These relavs a r e of the induction-disk con- '
struction. The disk is actuated by a potential oper- to
- ating coil on a laminated U magnet. The disk shaft i carries the moving contact w hic h completes the ,, \
trip or alarm circuitwhen it touches the stationary g contact or contacts. The disk shaft is restrained by a spiralspring to givethe proper contact closing se _M voltage and its motion is retarded by permanent \\\
magnets acting on the disk to give the correct time b delay. as
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There is a seal-le unit mounted to the left of y\\
the shaft as shown in F-g.1. This unit has its coil .o 82 pg in series and its contacts in parallel with the main e contacts suchthat whenthe main contacts close, the seal-in unit picks up and seals in. When the scal-in sn (\\M
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unit picks up, it raises a target into view which 3M3O latches up and remains exposed until released by 5
~e k pressing a button beneath the lower-left corner of \ \WD the cover, y\ (W N
- The r eIa ys a r e all mounted in single unit \ YDM-MDC- 5h double-end cases. The case has studs for external , s \ NN Q MI connections at both ends. The electrical connec- y N N
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2 internal connections. The operating coil is con- ,
nected in parallel withboth the upper and the lower inner molded blocks while the trip circuit is con-nected in series with th es e blocks. In this way, Fig. 2 Time-voltage Curves For Relay Types insertion of either the upper or lower conmeting LAY 54E And IAV5 plug will energizethe operating coil but t he t rip circuit will not be completed until the second con- .
necting p1ug is inserted. For relays which have The Type IAV54F relay is similar to tne Type contacts closed when the relay is de energized but IAV54E relay e7 cept that it has a longer opera ing optn under normal operating conditions, the double time. The timecharacteristicsare shown in Fig.3.
eted ha The Type IAV54H relay is also similar to the to p before the trip circu t co Type IAV54F relay except that it has much longer minirnizing the possibility of
- n c o r r ? c t tripping operating time than either the e IAV54E or the when returning the relay to service after tests and Type IAV54F relays. The time e racteristics are inspection. shown in Fig. 4.
APPLIC ATION The Type IAV55C relay is similar to the Type TAV54E relay except that it has two circuit closing '
These relays are protective devices designed contacts.
to close trip or alarm circuitswheneverthe voltage The Type IAV55F relay is similar to the Type applied to their operating coils reaches some pre- IAV54F rela 7 except that it has two circuit closinK determined value. The f anctions are described in contacts.
greater detail in the following paragraphs, The Type IAV55H relay is similar to the Type O F ~R ATIN G C H AR ACTERISTIC S IAV54H relay except that it has two circuit closing
The Type IAV54E relay has a single circult-closing contact which closes when the voltage is reduced to some predetermined value. Thus, the The Type IAV55J relay is similar to the Type contacts are closed at zero volta. This relay is a IAV55H relay except that it is provided with two time undervoltage relay with inverse time charac- separate seal-in units; one for each set of nor-teristics which are shown in Fig. 2. mally closed contacts.
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2033 029 .
Type IAV Undervoltage Relays GEH-1768 g RECEIVING, HANDLING AND STORAGE These relays, when not included as a part of a packing the relay in order that none of the parts control panel will beshipped in cartons designed to are injured or the adjustments disturbed.
protect t h em against damage. Immediately upon receipt of a relay, examine it for any damage sus-tained in transit. If 1nj u ry or damage resulting If the rela s are not to be installed 'mrnedi-from rough handlingis evident, file a damage claim ately,they shoufdbe storedin their originalcartons at once with the t r a n s p o r t a t i o n company and in a plae e that is free from moisture
- dust and mp not e nearestGeneral Electric Appa- metallic c h i p s. Foreign matter colle ted or the
- outside of the case mayfind its way inside when the cover is removedand causetrouble inthe operation ncasonable c a r e should be exercised in un- of the re'ay.
DESCRIPTION CASE This cradle is held firmly in the case with a latch at the top and the bottom and by a guide pin at the The case is suitable for eit her surface or back of the case. The cases and cradles are so semVlush panel m ounting and an assortment of constructed that the relay cannot be inserted in the hardware is provided for eit h er mounting. The case upside d ow n. The connecting plue, besides cover attaches to the ca s e and also carries the making the electrical connections between the re-reset mechanismwhen onels required. Each cover spective blocks of the readle and case, also locks screw has provision for a sealing wire. the latch in placa "'h'. cover which is fastened to the case by thumbscrews, holds the connecting plug The case has studs or screw connections at in place.
both ends or at t h e bottom only for the external connections. Th e electrical connections between To draw out the relay unit the cover is first the relay unitsand thecase studs are made through removed, and t h e plug drawn out. Shorting bars spring backed contact fingers mountedin stationary are providedin the case to shortthe current trans-molded inner and outer blocks between which nests former circuits. T h e latches are then released, a removable connecting plug which completes the and the r ela y unit can be easily drawn out. To
) circuits. The outer blocks, attached to the case replace the relay unit,the reverse order is followed.
have the studs for t he external connections, and the inner blocks have the terminals for the internal A separatetesting plugcan beinserted in place connections. e of the connecting plug to test the relay la place on the panel either from its ow n source of current The r clay mechanism is mounted in a steel and voltage, or from other sources. Or, the relay framework called the cradle and is a complete unit unit can bedrawn outand replacedby another which with all lead > being terminated at the inner block, has been tested in the laboratory.
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INSTALLATION LOCATION ADJUSTMENTS The locationshould be cleanand dry, free from TARGET AND SEAL [-IN UNIT dust and excessive vibration, and well lighted to facilitatt inspection and testing. For trip coils operating on currents ranging from 0.2 up to 2 amperes at the minimum control
) MOUNTING voltage, set the target and seal-in tap plug in the 0.2 ampere tap.
The relay s hould be mounted on a vertical surface. The outline and panel drilling dimes sions The tap plug is t h e screw holding the right-are shown in Flg. I1. hand stationary c on t a e t of the seal-in unit. To change the tap setting, first remove the connecting CO N N ECT!O NS plugs. Th> 7 take a screw from the left-hand sta-tionary e ont a e t and place it in the desired t ap.
The internalconnection diagrims are shown in Next, remove the screw from t h e other tap, and Figs. 5 a nd 6. Typical external connections are place it in the left-hand contact. This procedure is shown in Fig. 7. necessary toprevent tne right-hand stationary con-tact from getting out of adjustment. Screws should One of the mounting studs or screws should be not be in both taps at the same time, as d c pickup ptimanently grounded by a conductor not less than will have a higher tap value, whereas a".: pickup g No.12 B &S gage copper wire or its equivalent. will be increased, u 90 no w m 2033 030
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INSTRUCTIONS GEI-25372B Surtestots gel.25372A
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TEST PLUGS FOR DRAWOUT RELAYS AND METERS Types X L A12 A and X L A13 A e o
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203.5 031 POWER SYSTEMS MANAGEMENT DEPARTMENT GEN ER AL h ELECTRIC
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PHILADELPHlA, PA.
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GE!-25372 Test Plugs for Drawout Relays and Meters
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TEST PLUGS g FOR DRAWOUT RELAYS AND METERS TYPE XLA .
APPLIC ATIO N not disturb the current transformer shorting ar-rangement. The diagonally staggered binding posts The Type XLA test plugs are used to test are numbered. Numbers one to ten, corresponding drawout relays and meters. The XLA12A enables to the relay stud connections, appes_r up-right when power to be applied to the relay from either a using this plug in the bottom of a relay, while g separate source or the source that feeds the equip- number eleven to twenty appear up-side down, ment. The XLA13A can only be used when a Because of its design, the XLA13 test plug cannot separate source of power is available. be inserted into the bottom of a relay with numbers one to ten up-side down. Thus, the contacts of the inserted plug will always be toward the relay.
XLA12A TESTING The XLAl2A test plug consists of a black H ne esung can be accomplished by re-and red Textolite* molding with twenty electrically m ng the rday caer and suWWng eh M separate contact fingers connected to ten con- plug for the connecting plug.
centric bmding posts. The ten contact fingers on XLA12A the black side are connected to the inside binding posts with the black thumb nuts and engage the Several pieces cf hardware are supplied with relay internal connections. The contact fingers this test plug (See Fig. ',). The U-shaped link is on the red side are connected to tb ouier binding used to make through connections, relay stud to posts with the red thumb nuts and et . age the equip- case terminals. The long, open end link is used to ment case stud connections. See Fig.1. The con-centric binding posts are numbered on the nameplate' short circuit any current transformers and any e and the correspondmg contact fingers are numbered on each side of the test plug. When using the test normally closed contacts. This 1.nk must be in-serted in the proper place under the red thumb nuts before the test plug is inserted in the unit.
plug in the bottom of the relay, numbers one to ten, corresponding to the relay studs, appear upright, Two sizes of corregated end links are provided so while numbers eleven to twenty are upside down. standard test clips can be used. These links are It is impossible, du.e to its construction, to insert also provided with a hole so that a secure bolted the plug into the bottom of a relay with numbers connection may be obtained.
one to ten up-side down. By the same token, Typical separate source test connections and numbers eleven to twenty will always appear in the up-right position when the plug is inserted in th' wiring diagram for TYPE LAC overcurren; relays top of a relay. are shown in Fig. 3.
Removable test links for through connection A c nventional representation of test con-test clips and short-circuiting clips are furnishe[1 nections used on wirmg diagrams is shown in with each test plug. See Fig. 4. Fig. 9. An outime of this plug is shown in Fig.11.
XLA13A XLA13A No external provisions need be made ' r short-h The XLA 13A test plug consists of a black Textolite* molding with ten electrically separate ing current transformer secondaries or a Jrmally closed contacts because the plug is so designed that contac ts. Each contact terminates at a separate the side away from the relay to be tested does not binding post. See Fig. 2. When the relay connecting come into contact with any of the connecting fingers plug is withdrawn any current transformer second- in the case. Power source connections can be artes will be short circuited by shorting bars in the secured to the studs of the plug by the black thumb case. The insertion of the XLA13A test plug does nuts.
- Reg. Trade-Mark of General Electric Company These instructions do no? purport to cove oII details or variations in equipment nor to provide for every possible contiorgency to be met in connection with ins'allation, operation or maintenance. Should further information be desired or should particular problems crise which ors not covered sufficiently for the purchaser's purposes, the matter should be referred to the General Electric Company.
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033 034 4
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are shown in Fig. 5.
Immediately upon receipt of the test plug, an A conventional representation of the XLA13A examination should be made for any damage sus-est plug connections used on wiring diagrar.1s is tained in transit. If injury or rough handling is shown in Fig.10 evident a damage claim should be filed at once with the transportation company and the nearest General An outline diagram of the XLA13A test plug is Electric Sales Office should be notified.
shown in Fig.12.
RENEWAL PARTS SHIPPING - UNPACKING Orders for renewal parts, should be addressed Type XLA test plugs are shipped in individual to the nearest Sales Office of the General Electric cartons which may be used for storage. All neces- Company, giving the name of part w .nted, quantity required and complete nameplate data.
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2033 035 Fig. 6 Accessory Links for the XLA Test Plugs
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GEI-25372 Test Plugs for Drawout Relays and Meters
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- F..g. 2033 037 12 Outline of the XLAl3A Test Plug
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. TABLE 1
.
ANO-: RUNNINC 10^ UPON FULL HOUSE TRANSFER TO ST 1 Centi.i R o om Chille r (2) -
Instrument Air (2)
S pe nt Fuel P o ol C oole r (2)
Se rvice Wa te r Pump (2)
Makeup Pump (2)
Auxilia ry L. O. Pump (1)
React or Building C oole r (2)
React or Building C oole r (2)
Relay R o om Unit Cl r. (2)
Inve rte r T ra ns . (2)
. Pipe Heat T ra ci ng (1)
B a t t e ry Cha rge r (2)
Inst. AC T ra ns f o rme r (2)
P re s s . 14 t rs. (2)
Inve rte r T rans. SW. (2)
B a t t e ry R o om Extinguisher Fan (2)
Di s ch a rge vlume Rad. Monit or (1)
Stack Rad. Monit or PP . (1)
P r im . Make up R o om (1)
ICW Rad. Mon. (2)
S e rvi c e H2O Rad. Monitor (2)
Au xilia ry Building Swit chgea r (1)
Inst. Ai r D rye r (1)
C omput e r Inve rte r (1)
Au xili a ry Building Ltg . (1)
Reactor Building Ltg. (1)
C ond e ns a t e Pumps (2)
Ci rcu la t i ng Wa te r (4)
Non-safety Load Ce nte rs (5) 2033 038