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Category:CORRESPONDENCE-LETTERS
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20210K1621999-07-0707 July 1999 Informs That Licensee in Process of Preparing Scope of Service Delineation for Environ Assessment to Be Performed for New Airport Located Near Russellville,Ar,To Identify Anticipated Environ Impacts from Various Agencies 1CAN079902, Documents ANO-1 Position Discussed on 990705,with Members of NRC Staff & Formally Requests Enforcement Discretion from Requirements of TS 3.7.2.C to Allow Continued Power of Operation1999-07-0606 July 1999 Documents ANO-1 Position Discussed on 990705,with Members of NRC Staff & Formally Requests Enforcement Discretion from Requirements of TS 3.7.2.C to Allow Continued Power of Operation ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 0CAN069906, Forwards Corrected Pages to 1997 & 1998 Annual Radiological Environ Operating Repts, Issued 980430 (0CAN049804) & 990506 (0CAN059902).Ltr Number & Page Number Are at Top of of Corrected Pages to Replace Originally Pages1999-06-30030 June 1999 Forwards Corrected Pages to 1997 & 1998 Annual Radiological Environ Operating Repts, Issued 980430 (0CAN049804) & 990506 (0CAN059902).Ltr Number & Page Number Are at Top of of Corrected Pages to Replace Originally Pages 1CAN069905, Forwards non-proprietary Version of Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs1999-06-17017 June 1999 Forwards non-proprietary Version of Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs 0CAN069903, Submits Rept of Each Change to or Error Discovered in Acceptable Evaluation Model or in Application of Such Model for ECCS That Affects Peak Cladding Temp,Iaw 10CFR50.46(a) (3)(ii)1999-06-10010 June 1999 Submits Rept of Each Change to or Error Discovered in Acceptable Evaluation Model or in Application of Such Model for ECCS That Affects Peak Cladding Temp,Iaw 10CFR50.46(a) (3)(ii) 2CAN069901, Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 20001999-06-0202 June 1999 Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 2000 1CAN069901, Submits 10CFR50.46 Rept Re Inconsistent Input in SBLOCA Analysis.Rept Submitted in Accordance with Recommendations Stated in Notice1999-06-0202 June 1999 Submits 10CFR50.46 Rept Re Inconsistent Input in SBLOCA Analysis.Rept Submitted in Accordance with Recommendations Stated in Notice 0CAN059906, Forwards Response to NRC 990402 RAI Re GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-05-28028 May 1999 Forwards Response to NRC 990402 RAI Re GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs ML20207E4341999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft 1CAN059904, Informs NRC That Wl Franklin No Longer Has Need to Maintain Operating License on Ano,Unit 1.Requests License for Wl Franklin Be Withdrawn1999-05-20020 May 1999 Informs NRC That Wl Franklin No Longer Has Need to Maintain Operating License on Ano,Unit 1.Requests License for Wl Franklin Be Withdrawn 2CAN059906, Informs That ANO-2 UFSAR Will Be Revised to Include Comprehensive Discussions of Each Category of Containment Penetration Overcurrent Protective Devices,Per NRC Review of 980806 TS Change Request Re Relocation of TS Table 3.8-11999-05-18018 May 1999 Informs That ANO-2 UFSAR Will Be Revised to Include Comprehensive Discussions of Each Category of Containment Penetration Overcurrent Protective Devices,Per NRC Review of 980806 TS Change Request Re Relocation of TS Table 3.8-1 1CAN059902, Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program1999-05-17017 May 1999 Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program 2CAN059905, Expresses Appreciation for Staff & Mgt Team Efforts in Aggressively Pursuing Risk Informed ISI Initiative1999-05-14014 May 1999 Expresses Appreciation for Staff & Mgt Team Efforts in Aggressively Pursuing Risk Informed ISI Initiative ML20206P7681999-05-10010 May 1999 Forwards Applications for Renewal of Operating License (Form 398) for MW Little & F Uptagrafft.Without Encl 2CAN059903, Forwards Rev to Footnote Submitted to Provide Clarity to Aforementioned Guidance1999-05-10010 May 1999 Forwards Rev to Footnote Submitted to Provide Clarity to Aforementioned Guidance ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206H7121999-05-0606 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept, for Ano.All Radionuclides Detected by Radiological Environ Monitoring Program During 1998 Were Significantly Below Regulatory Limits 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEAR2CAN099009, Requests Interim Relief from Inservice Testing Re Performing Partial Stroke Test for Check Valve 2SI-16A.Valve Currently Required to Be Tested by 9009251990-09-21021 September 1990 Requests Interim Relief from Inservice Testing Re Performing Partial Stroke Test for Check Valve 2SI-16A.Valve Currently Required to Be Tested by 900925 0CAN099002, Discusses Validation of Nonlicensed Operator Staffing,In Response to Insp Repts 50-313/90-01 & 50-368/90-01.Concludes That Current Level of Three Nonlicensed Operators Per Shift, Adequate to Meet Demands of Operations Under EOP1990-09-14014 September 1990 Discusses Validation of Nonlicensed Operator Staffing,In Response to Insp Repts 50-313/90-01 & 50-368/90-01.Concludes That Current Level of Three Nonlicensed Operators Per Shift, Adequate to Meet Demands of Operations Under EOP 0CAN099007, Forwards Operator Licensing Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-14014 September 1990 Forwards Operator Licensing Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 2CAN099004, Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis1990-09-0707 September 1990 Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis 0CAN099001, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/90-19 & 50-368/90-19.Corrective Actions:Surveillance Procedures Reverified & Revised1990-09-0707 September 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/90-19 & 50-368/90-19.Corrective Actions:Surveillance Procedures Reverified & Revised 1CAN099003, Requests one-time Rev to Natl Exam Schedule for Operator License & Requalification Exams at Facility to Allow Testing in Aug,Rather than Feb of 19911990-09-0606 September 1990 Requests one-time Rev to Natl Exam Schedule for Operator License & Requalification Exams at Facility to Allow Testing in Aug,Rather than Feb of 1991 0CAN089009, Informs of Relocation to New Generation Support Bldg Just Outside Protected Area Southeast of Administration Bldg1990-08-31031 August 1990 Informs of Relocation to New Generation Support Bldg Just Outside Protected Area Southeast of Administration Bldg 0CAN089006, Forwards Semiannual Radiological Effluent Release Rept for First & Second Quarters 1990 & Changes to ODCM & Process Control Manual1990-08-30030 August 1990 Forwards Semiannual Radiological Effluent Release Rept for First & Second Quarters 1990 & Changes to ODCM & Process Control Manual 0CAN089008, Forwards Facility fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.73(d)1990-08-29029 August 1990 Forwards Facility fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.73(d) 0CAN089005, Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 9010011990-08-27027 August 1990 Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 901001 1CAN089011, Requests Relief from ASME Code Section XI Requirements Re Exercise & Stroke Time Testing for Low Pressure Injection Valves CV-1432 & CV-1433.Valves Located in Bypass Lines Around Decay Heat Coolers1990-08-16016 August 1990 Requests Relief from ASME Code Section XI Requirements Re Exercise & Stroke Time Testing for Low Pressure Injection Valves CV-1432 & CV-1433.Valves Located in Bypass Lines Around Decay Heat Coolers 2CAN089009, Requests Addl Time to Respond to NRC 900607 Request for Info Re Second 10-yr Interval of Inservice Insp Program. Response Will Be Submitted No Later than 9010311990-08-13013 August 1990 Requests Addl Time to Respond to NRC 900607 Request for Info Re Second 10-yr Interval of Inservice Insp Program. Response Will Be Submitted No Later than 901031 0CAN089002, Responds to Recommendations from Insp Repts 50-313/90-04 & 50-368/90-04 on 900202 That Reporting Format for Semiannual Radioactive Effluent Release Repts Be Revised to Comply W/ Reg Guide 1.21,Rev 11990-08-0808 August 1990 Responds to Recommendations from Insp Repts 50-313/90-04 & 50-368/90-04 on 900202 That Reporting Format for Semiannual Radioactive Effluent Release Repts Be Revised to Comply W/ Reg Guide 1.21,Rev 1 05000313/LER-1989-041, Revises Commitment Completion Date for LER 89-041-00 Re Proper Method of Calibr of Startup Feedwater Control Valves CV-2623 & 2673 to 900915.Delay Due to Time Needed to Review & Implement New Calibr Guidance Criteria1990-08-0202 August 1990 Revises Commitment Completion Date for LER 89-041-00 Re Proper Method of Calibr of Startup Feedwater Control Valves CV-2623 & 2673 to 900915.Delay Due to Time Needed to Review & Implement New Calibr Guidance Criteria 2CAN089006, Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info1990-08-0202 August 1990 Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info ML20081E0891990-07-31031 July 1990 Advises That Since Guidance Contained in Reg Guide 1.97 Not Addressed in Submittals Re Generic Ltr 82-33,further Clarification of Position Re Compliance W/Generic Ltr Appropriate,Per .Ltr Will Be Submitted by 901215 0CAN079014, Amends Commitment Date for Mods to Svc Water Pump Design,Per Insp Repts 50-313/89-30 & 50-368/89-30.Project Scoping Rept Expected to Be Completed by 9009301990-07-31031 July 1990 Amends Commitment Date for Mods to Svc Water Pump Design,Per Insp Repts 50-313/89-30 & 50-368/89-30.Project Scoping Rept Expected to Be Completed by 900930 0CAN079024, Forwards Revised Response to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Specific Communication Meetings Will Be Conducted W/Staff Re Decontamination Practices & Procedures1990-07-31031 July 1990 Forwards Revised Response to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Specific Communication Meetings Will Be Conducted W/Staff Re Decontamination Practices & Procedures 0CAN079020, Forwards Update to Status of Remaining Open Items on Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Encl Withheld (Ref 10CFR2.790)1990-07-31031 July 1990 Forwards Update to Status of Remaining Open Items on Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Encl Withheld (Ref 10CFR2.790) 0CAN079018, Certifies That Info Contained in Rev 12 to QA Manual Operations Freighted to NRC on 900723 & Accurately Represents Changes Made Since Previous Submittal,Per 10CFR50.54(a)(3)1990-07-24024 July 1990 Certifies That Info Contained in Rev 12 to QA Manual Operations Freighted to NRC on 900723 & Accurately Represents Changes Made Since Previous Submittal,Per 10CFR50.54(a)(3) 0CAN079021, Forwards Rev 12 to QA Manual Operations1990-07-23023 July 1990 Forwards Rev 12 to QA Manual Operations 0CAN079019, Forwards Rev 12 to QA Manual Operations.W/O Encl1990-07-23023 July 1990 Forwards Rev 12 to QA Manual Operations.W/O Encl 0CAN079011, Suppls Response to Violations Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Re Isolation Valve CS-26. Corrective Actions:Special Work Plan Developed & Valve Cs-26 Local Leak Rate Tested on 9002161990-07-20020 July 1990 Suppls Response to Violations Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Re Isolation Valve CS-26. Corrective Actions:Special Work Plan Developed & Valve Cs-26 Local Leak Rate Tested on 900216 2CAN079008, Forwards Response to NRC Questions on CEN-386-P Re Extended Burnup Rept & Statistical Treatment of Elastic Strain in Fuel Cladding at end-of-life & Measured Axial Fuel Rod pellet-to-pellet Gaps1990-07-17017 July 1990 Forwards Response to NRC Questions on CEN-386-P Re Extended Burnup Rept & Statistical Treatment of Elastic Strain in Fuel Cladding at end-of-life & Measured Axial Fuel Rod pellet-to-pellet Gaps 0CAN079006, Provides Update to Util Providing Results of Comparison of Station Blackout Rule Submittals to NUMARC Guidance1990-07-17017 July 1990 Provides Update to Util Providing Results of Comparison of Station Blackout Rule Submittals to NUMARC Guidance 2CAN079001, Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip1990-07-0505 July 1990 Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip ML20043H5161990-06-19019 June 1990 Informs of Changes of Responsibility for Plant Emergency Plan,Effective 900605 ML20043H3121990-06-18018 June 1990 Forwards Responses to Remaining NRC Questions Re Seismically Qualified,Partially Protected,Condensate Storage Tank (Qcst).Analyses in Calculations Demonstrate That Qcst Tank Foundation & Drilled Piers Adequate W/O Mod ML20043F3321990-06-15015 June 1990 Submits Addl Info on Tech Spec Change Request for Seismic Instrumentation,Per 890809 Request.Licensee Concurs W/Nrc Recommendation Re Editorial Change ML20043G0661990-06-13013 June 1990 Responds to Deviations Noted in Insp Repts 50-313/90-11 & 50-368/90-11.Corrective Actions:Further Evaluations Conducted to Develop Optimum List of post-accident Instruments Requiring Identification on Control Panels ML20043H3471990-06-11011 June 1990 Forwards Rev 19 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043G3801990-06-11011 June 1990 Responds to Violations Noted in Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Decision Made to Staff Unit 1 Exit Location Point W/Health Physics Technician 24 H Per Day ML20043F5121990-06-0808 June 1990 Forwards List of Directors & Officers of Entergy Operations, Inc.Operation of All Plants Transferred to Entergy on 900606 ML20043F4341990-06-0707 June 1990 Informs of Receipt of Necessary Approvals to Transfer Operating Responsibilities of Plant to Entergy Operations, Per Amends 128 & 102 to Licenses DPR-51 & NPF-6, Respectively.Extension of Amend Request Unnecessary ML20043E6561990-06-0707 June 1990 Requests That Listed Distribution Be Made on All Future NRC Correspondence.Correspondence to Ns Carns Should Be Addressed to Russellville ML20043E4991990-06-0505 June 1990 Provides Supplemental Response to Violations Noted in Insp Repts 50-313/89-02 & 50-368/89-02.Corrective Actions:Listed Program Enhancements Being Implemented to LER Process to Provide Timely Determinations of Condition Rept ML20043E3851990-06-0404 June 1990 Concurs w/900516 Ltr Re Implementation of SPDS Complete for Both Units & Requirements of NUREG-0737,Suppl 1 Met ML20043E3771990-06-0404 June 1990 Forwards Response to Concerns Re Control Room Habitability Survey.Addl Mods Identified Will Enhance Overall Reliability of Control Room Sys & Changes Designed to Increase Performance,Effectiveness & Response of Habitability Sys ML20043C0821990-05-25025 May 1990 Withdraws 900410 Request to Amend Tech Spec Table 3.3-1 Re Applicable Operational Modes for Certain Reactor Protective Instrumentation Operability Requirements ML20043B6531990-05-22022 May 1990 Forwards Rev to Industrial Security Plan to Eliminate Need to Protect Certain Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21) ML20043B7091990-05-21021 May 1990 Forwards Revised Maelu Certificate of Insurance for Nuclear Onsite Property Insurance Coverage for 1990,changing Policy Number from X89166 to X90143R ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A5991990-05-15015 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Repts for Feb & Mar 1990 for Arkansas Nuclear One,Unit 1 ML20042H0551990-05-0909 May 1990 Forwards Civil Penalty in Amount of $50,000 for Violations Noted in Insp Repts 50-313/86-23 & 50-368/86-24 Re Environ Qualification of Electrical Equipment Important to Safety. Comprehensive Corrective Actions Undertaken ML20043B0841990-05-0909 May 1990 Corrects 900309 Ltr Re Completion of Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Design Change Package Addressing Perimeter & Interior Lighting Scheduled to Be Onsite Late Summer 1991 ML20043A8361990-05-0707 May 1990 Responds to Violations Noted in Insp Repts 50-313/90-05 & 50-368/90-05.Corrective Actions:Personnel Involved Received Counselling Re Incident & Operations Personnel Being Trained on Significance of Surveillance Requirements ML20042F4371990-05-0404 May 1990 Requests 90-day Extension to Provide Addl Time for Reviews of Amends 128 & 102 to Licenses DPR-51 & NPF-6,respectively, Re Ownership Transfer ML20042G4771990-05-0404 May 1990 Forwards Summary of Util Exercise Critique Board Evaluation of Radiological Emergency Preparedness Exercise REX-90,per Insp Repts 50-313/90-08 & 50-368/90-08 ML20042F3351990-05-0303 May 1990 Forwards Nonproprietary Suppl 1 to CEN-386-NP & Proprietary Suppl 1 to CEN-386-P, Responses to Questions on C-E Rept CEN-386-P, 'Verification of Acceptability of 1-Pin Burnup Limit....' Proprietary Rept Withheld (Ref 10CFR2.790) ML20042F2701990-04-30030 April 1990 Provides Exam Schedules for Reactor Coolant Pumps a & B in Revised Inservice Insp Program Plan.Insps Scheduled for Refueling Outages 1R10 & 1R12 for Pump a Exams & Refueling Outages 1R10,1R12 & 1R14 for Pump B Exams 1990-09-07
[Table view] |
Text
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.- * .- .e ARKANSAS POWER & LIGHT COMPANY POST OF FICE GOX SS1 LITTLE ROCK. ARKANSAS 72203 (5011371-4000 July 26, 1982 l
l OCAN078222 Mr. Darrell G. Eisenhut, Director Division of Licensing i Office of Nuclear Reactor Regulation l U. S. Nuclear Regulatory Commission
- Washington, D. C. 20555 1
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 & 50-368 License Nos. DPR-51 & NPF-6 i
NUREG-0737, Item No. II.K.3.17 l Report on Outages of Emergency Core Cooling (ECC) Systems Gentlemen:
In accordance with your letter dated March 24, 1982, (2CNA038206)
! requesting additional information on outages of ECC systems, attached are detailed reports for Arkansas Nuclear One - Unit 1 (Attachment 1) and Unit 2 (Attachment 2). These reports contain a complete summary of each component outage in the ECC and diesel generator systems for the five years of plant operation through 1980.
l l
l Very truly yours, t.
John R. Marshall Manager, Licensing JRM:Hgsc Attachments l
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8208110196 820726 PDR ADOCh 05000313 MEMot" M'oote sours uTiutts cysTru P PDR
0 0 9 t
l ATTACHMENT 1 REPORT ON OUTAGE OF DIESEL GENERATOR OR ECC SYSTEM COMP 0NENTS I
FOR ARKANSAS NUCLEAR ONE UNIT-1 I
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I DATE: 11/26/75 DURATION: 8.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ECC SYSTEM OR COMP 0NENT: No. 2 Diesel Generator MODE OF OPERATION: Power Operation TRAIN AFFECTED: Green CAUSE: During testing of No. 2 Diesel Generator, an oil leak developed at the oil cooler outlet flange. An 0-ring gasket had failed.
No. 1 Diesel Generator was operable.
CORRECTIVE ACTION: Replaced o-ring
(
REFERENCE:
LER 50-313/75-009)
DATE: 5/11/76 i DURATION: 0.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ECC SYSTEM OR COMPONENT: No. 1 Diesel Generator MODE OF OPERATION: Cold Shutdown TRAIN AFFECTED: Red CAUSE: Diesel Generator No. 1 failed to start on simulated E.S.
Actuation during checks preparatory to integrated E.S. test.
CORRECTIVE ACTION: Diode was replaced in auto-start circuit.
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REFERENCE:
LER 50-313/76-008) l l
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a l
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DATE: 10/3/76 DURATION: 10.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> ECC SYSTEM OR COMP 0NENT: Primary Makeup Pumps 'B' & 'C' MODE OF OPERATION: Power Operation TRAIN AFFECTED: Green and Swing CAUSE: Primary makeup pump removed from service due to pipe weld leak in the suction relief line. Redundant pump (P368) placed in service; however, pump discharge pressure degraded, due to impleller failure, after approximately 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of service.
Pump P36C was returned to E.S. standby until the following day, then was removed from service for leak repair, leaving one operable makeup pump.
CORRECTIVE ACTION: Primary makeup pump 'C' suction relief line pipe weld leak repaired. Pump returned to service, giving the two required pumps operable status.
(
REFERENCE:
LER's 50-313/76-029 and 76-030) i DATE: 11/22/76 DURATION: 20.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ECC SYSTEM OR COMPONENT: No. 1 Diesel Generator MODE OF OPERATION: Power Operation TRAIN AFFECTED: Red CAUSE: An inadvertant trip of the fire system deluge while being returned to service rendered Diesel Generator No. 1 inoperative due to wet control circuitry. The cause was an apparent leak off of sealing pressure to the deluge valve when the system was
, taken out of the service for modifications.
CORRECTIVE ACTION: The engine control cabinet and exciter control cabinet were dried and the generator and cables were
, meggered for proper readings.
1 i (
REFERENCE:
LER 50-313/76-033) l 2
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DATE: 10/23/77 DURATION: 11.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> ECC SYSTEM OR COMPONENT: No. 1 Diesel Generator MODE OF OPERATION: Power Operation TRAIN AFFECTED: Red CAUSE: The No. 1 Diesel Generator failed to start during monthly test.
The starter failure time delay relay set point had drifted causing the air starters to cycle before they could start the diesel. Also, Diode CR-1 was found shorted.
CORRECTIVE ACTION: The Diode was replaced and the relay set point was properly set.
(
REFERENCE:
LER 50-313/77-020)
DATE: 11/22/77 DURATION: 52.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ECC SYSTEM OR COMPONENT: Reactor Building Emergency Cooling Fan MODE OF OPERATION: Power Operation TRAIN AFFECTED: N/A CAUSE: Reactor building emergency cooling fan inoperable where the two remaining cooling fans were not powered from operable independent emergency buses. Cooling fan motor failed due to lack of bearing lubrication.
CORRECTIVE ACTION: Unit was brought to cold shutdown conditions as required by the conditions of the technical specifications limiting conditions for operations.
All cooling fans were inspected and repaired, as necessary. A lubrication requirement was added to the fan preventive maintenance program. Outage time was 361 hours0.00418 days <br />0.1 hours <br />5.968915e-4 weeks <br />1.373605e-4 months <br />.
(
REFERENCE:
LER 50-313/77-021) 3
DATE: 3/20/78 DURATION: 59.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ECC SYSTEM OR COMPONENT: No. 2 Diesel Generator MODE OF OPERATION: Refueling Shutdown TRAIN AFFECTED: Green CAUSE: During a test of the No. 2 Diesel Generator it was manually tripped due to abnormal indications. Fire from exhaust stake, then smoke alarm was noted. Fire was present.inside turbo charger. Probable cause of fire was failure of the bearing between the air inlet blading and exhaust turbine blading of the engine turbocharger. The subsequent failure of the bearing oil seal allowed lube oil into exhause, which ignited.
- CORRECTIVE ACTION
- Turbocharger was replaced.
(
REFERENCE:
LER 50-313/78-008)
DATE: 7/28/78 DURATION: 6.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ECC SYSTEM OR COMPONENT: No. 2 Diesel Generator MODE OF OPERATION: Power Operation TRAIN AFFECTED: Green CAUSE: During monthly surveillance operational test, Diesel Generator No. 2 was removed from the line due to excessive smoke in turbocharger area. The smoke was caused by an oil seal leak on the turbocharger at a rate of 5 drops per minute. Vendor representative confirmed unit could be operated; therefore, unit was declared operational.
CORRECTIVE ACTION: The turbocharger was replaced 7/28/78.
(
REFERENCE:
LER 50-313/78-017) l l
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DATE: 9/26/78 DURATION: 12.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ECC SYSTEM OR COMPONENT: Borated Water Storage Tank MODE OF OPERATION: Power Operation TRAIN AFFECTED: N/A CAUSE: Borated water storage tank boron concentration less than the -
technical specifications required 2270 ppmb due to unidentified causes.
CORRECTIVE ACTION: Boron concentration increased to required amount.
(
REFERENCE:
LER 50-313/78-026)
DATE: 11/21/78 DURATION: 23.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ECC SYSTEM OR COMPONENT: Borated Water Storage Tank MODE OF OPERATION: Power Operation TRAIN AFFECTED: N/A CAUSE: Borated water storage tank boron concentration less than the technical specifications required 2270 ppmb due to condensate valve misaligment.
CORRECTIVE ACTION: Closed valve and increased boron concentration to required amount.
(
REFERENCE:
LER 50-313/78-030) 5
DATE: 8/27/79 DURATION: 102.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ECC SYSTEM OR COMPONENT: No. 2 Diesel Generator H0DE OF OPERATION: Power Operation TRAIN AFFECTED: Green
-CAUSE: During the monthly surveillance operational test, Diesel Generator No. 2 tripped on oil pressure after three minutes of operation. The diesel lube oil cooler was leaking allowing water to enter the oil system. The water vaporized on unit operation causing a high crankcase pressure which tripped the engine.
CORRECTIVE ACTION: Replaced oil cooler.
(
REFERENCE:
LER 50-313/79-016)
DATE: 9/11/79 DURATION: 48.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> ECC SYSTEM OR COMPONENT: No. 1 Diesel Generator MODE OF OPERATION: Power Operation TRAIN AFFECTED: Red CAUSE: During the monthly surveillance operational test, Diesel Generator No. 1 tripped on oil pressure after three minutes of operation. The diesel lube oil cooler was leaking allowing water to enter the oil system. .The water vaporized on unit operation causing a high crankcase pressure which tripped the engine.
CORRECTIVE ACTION: Replaced lube oil cooler.
! (
REFERENCE:
LER 50-313/79-017) 6 L
DATE: 10/8/79 DURATION: 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ECC SYSTEM OR COMP 0NENT: Engineered Safety Feature Valve Associated with Sodium Hydroxide ES Operation.
MODE OF OPERATION: Power Operation TRAIN AFFECTED: Red CAUSE: Sodium hydroxide tank discharge valve, CV1617, declared inoperable due to a control power fuse failure caused by a control wire being pinched and grounded to the valve operator cover. Valve failed in the ES position (open).
CORRECTIVE ACTION: Valve operator was repaired and maintenance personnel were cautioned.
(
REFERENCE:
LER 50-313/79-018)
DATE: 4/7/80 DURATION: 6.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ECC SYSTEM OR COMP 0NENT: Loop 'B' High Pressure Injection Valve MODE OF OPERATION: Power Operation TRAIN AFFECTED: Green CAUSE: High pressure injection valve, CV-1227, failed to open on demand due to the valve operator manual engaging level stuck in the engaged position.
CORRECTIVE ACTION: Valve operator repaired and returned to service.
(
REFERENCE:
LER 50-313/80-013) l l
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DATE: 8/27/80 DURATION: 18.65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br /> ECC SYSTEM OR COMP 0NENT: No. 2 Diesel Generator MODE OF OPERATION: Power Operation TRAIN AFFECTED: Green CAUSE: Diesel Generator No. 2 secured approximately 7 minutes into the monthly surveillance operational test. Excessive smoke was observed coming from the turbocharger exhaust flange. Loose exhaust flange bolts and a broken exhaust flange gasket allowed lube oil to come in contact with exhause gas.
CORRECTIVE ACTION: Replaced gasket and added flange bolt inspection to preventive maintenance schedule.
(
REFERENCE:
LER 50-313/80-031)
DATE: 10/13/80 DURATION: 12.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ECC SYSTEM OR COMPONENT: No. 1 Diesel Generator MODE OF OPERATION: Power Operation TRAIN AFFECTED: Red CAUSE: During testing of the No. 1 Diesel Generator, it's voltage regulator failed to respond to a higher or lower signal. The cause was an inoperable voltage regulator. Regulator failure was due to internal mechanical wear.
4 CORRECTIVE ACTION: Replaced voltage regulator.
(
REFERENCE:
LER 50-313/80-038)
I l
8 i
. , - _ . - _ - - . = - - , - _ - - - - - - - . - . -
DATE: 1975-1980 DURATION: 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> total time ECC SYSTEM OR COMPONENT: Diesel Generators MODE OF OPERATION: Appear Listed Below CAUSE: Prior to diesel start during the monthly operational surveillance test the selector switch on the local panel is placed on maintenance, cylinder drain cocks are opened and the diesel generator is turned over one turn. The maintenance turn is required to check for oil or water in the culinders prior to diesel start. During this portion of the operational surveillance test the diesel generator cannot respond to an ES actuation signal. Drain cocks must be closed and local panel returned to auto before diesel start will occur. Prior to November 1979, diesel generator surveillance tests were performed on an annual basis, thereafter, tests were performed on a monthly basis. The maintenance portion of the surveillance test takes approximately 5 minutes. Test dates for the diesel generators are listed below (year-month-day).
Diesel Generator Test Date Mode of Operation Train Affected 1
750101 Cold Shutdown Red 750101 Cold Shutdown Green 1 760101 Cold Shutdown Red 760101 Cold Shutdown Green 770101 Power Operation Red 770101 Power Operation Green
- 780101 Power Operation Red 780101 Power Operation Green 791102 Cold Shutdown Green 791103 Cold Shutdown Red 791113 Cold Shutdown Red 791127 Power Operation Green 791213 Power Operation Red 791227 Power Operation Green i 800113 Cold Shutdown Red l 800127 Cold Shutdown Green 800213 Power Operation Red i
800227 Power Operation Green 800227 Power Operation Red 800313 Power Operation Red 800327 Power Operation Green 800403 Power Operation Red 800403 Power Operation Green l 800413 Power Operation Red 800424 Cold Shutdown Red 800427 Cold Shutdown Green 800430 Cold Shutdown Red l 800513 Cold Shutdown Red l 800527 Cold Shutdown Green 9
800613 Cold Shutdown Red 800627 Cold Shutdown Green 800713 Power Operation Red 800727 Cold Shutdown Red 800728 Cold Shutdown Green 800802 Cold Shutdown Green 800813 Power Operation Red 800827 Power Operation Green 800827 Power Operation Red 800913 Cold Shutdown Red 800927 Heat Up Green 801013 Power Operation Red 801013 Power Operation Green 801113 Power Operation Red 801113 Power Operation Green 801114 Power Operation Green 801114 Power Operation Red 801119 Power Operation Green 801119 Power Operation Red 801120 Power Operation Red 801127 Power Operation Green 801213 Power Operation Red 801215 Power Operation Green 801227 Power Operation Green CORRECTIVE ACTION: Only one diesel generator is tested at a time. An operator remains in the vicinity of the diesel generator during the pre-start maintenance turn.
Should ES actuation occur during that portion of the surveillance test the operator could return the diesel generator to service.
(
REFERENCE:
Procedure 1104.36 Sop. 1) h O
! 10 c
f DATE: 1975-1980 OURATION: 12.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> total time based upon an approximate test length of 17 minutes.
ECC SYSTEM OR COMPONENT: Low Pressure Injection Pump MODE OF OPERATION: Appear Listed Below CAUSE: Performance of the monthly operational surveillance test requires alignment of the pump discharge to the test and recirculation header. An ES actuation signal during the surveillance test would start the low pressure injection pump, however, low pressure injection would not occur. Closure of the low pressure injection pump discharge to test and recirculaiton header isolation valve would be required for low pressure injection. Prior to November 1979, operational surveillance tests were performed on an annual bas'.s. Since that time they have been performed on a monthly basis.
Approximate test length is 17 minutes. Individual test dates for 'A' and 'B' low pressure injection pumps are listed below (year-month-day).
P-34A TRAIN AFFECTED: Red P-34B TRAIN EFFECTED: Green i
Date Mode of Operation Date Mode of Operation 750101 Cold Shutdown 750101 Cold Shutdown 760101 Cold Shutdown 760101 Cold Shutdown 770101 Power Operation 770101 Power Operation 780101 Power Operation 780101 Power Operation 790101 Cold Shutdown 790101 Cold Shutdown 791117 Cold Shutdown 791110 Cold Shutdown 791218 Power Operation 791203 Power Operation 800117 Cold Shutdown 800109 Cold Shutdown 800119 Cold Shutdown 800206 Cold Shutdown 800217 Power Operation 800303 Power Operation 800317 Power Operation 800403 Power Operation 800417 Power Operation 800502 Cold Shutdown 800522 Cold Shutdown 800606 Cold Shutdown
, 800605 Cold Shutdown 800703 Power Operation t' 800617 Power Operation 800804 Power Operation 800623 Power Operation 800903 Power Operation i
800804 Power Operation 800925 Cold Shutdown 800817 Power Operation 801003 Power Operation l 800926 Cold Shutdown 801103 Power Operation l 801017 Power Operation 801203 Power Operation Power Operation 801117
- 801217 Power Operation 801218 Power Operation 11 1
(
CORRECTIVE ACTION: Only one loop of the low pressure injection system is tested at a time. An operator is required to remain in the vicinity of the lower pressure injection pump being tested at all times during the test. Should ES' actuation occur during the surveillance test the operator could return the pump to service.
(
REFERENCE:
Procedure 1104.004) 12 i
ATTACHMENT 2 REPORT ON OUTAGE OF DIESEL GENERATOR OR ECC SYSTEM COMP 0NENTS FOR ARKANSAS NUCLEAR ONE UNIT-2 l
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DATE: 9/16/78 DURATION: 18.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ECC SYSTEM OR COMPONENT: Refueling Water Tank MODE OF OPERATION: 3 TRAIN AFFECTED: N/A CAUSE: Refueling water tank level below technical specifications required 91.7% (indicated) one to inadvertant ECC system actuation caused by a loss of relay power to ECC system components due to an injector failure.
CORRECTIVE ACTION: Unit taken to cold shutdown conditions and refueling water tank level increased to required level.
(
REFERENCE:
LER 50-368/78-006)
DATE: 11/9/78 DURATION: N/A ECC SYSTEM OR COMP 0NENT: No. 1 Diesel Generator MODE OF OPERATION: 5&6 TRAIN AFFECTED: Red CAUSE: A dramatic change in engine acoustics was noticed during a surveillance. The enginee tripped before it could be unloaded.
This was due to bearing damage.
CORRECTIVE ACTION: The damage was repaired and the diesel proved operable.
DATE: 12/17/78 DURATION: 15.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ECC SYSlEM OR COMPONENT: No. 2 Diesel Generator MODE OF OPERATION: 2&3 TRAIN AFFECTED: Green CAUSE: The Diesel Generator was out of service while performing preventing maintenance.
CORRECTIVE ACTION: Verify operability after the preventive maintenance.
1
{
DATE: 1/30/79 DURATION: 0.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ECC SYSTEM OR COMPONENT: Safety Injection Tank 'D' MODE OF OPERATION: 1 TRAIN AFFECTED: N/A CAUSE: Safety injection tank pressure below technical specification
- required 600 psig due to past system check valve.
CORRECTIVE ACTION: Safety injection tank pressure was immediately restored. Valve maintenance was completed.
(
REFERENCE:
LER 50-368/79-016)
DATE: 3/30/79 DURATION: 12.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> i ECC SYSTEM OR COMP 0NENT: High Pressure Safety Injection Header 'A' 4
MODE OF OPERATION: 3 TRAIN AFFECTED: N/A CAUSE: High pressure safety injection header removed from service to allow maintenance on the header relief valve.
CORRECTIVE ACTION: Complete maintenance on relief valve and return header to service.
1
(
REFERENCE:
LER 50-368/79-027) 2 4
y -.
m_, , . . g ., y_ _ . . . _ ,, , - . , _ _ , ___,m - , , ..__, m_ . _ . ,,
DATE: 4/19/79 DURATION: 23.73 hours8.449074e-4 days <br />0.0203 hours <br />1.207011e-4 weeks <br />2.77765e-5 months <br /> ECC SYSTEM OR COMPONENT: No. 2 Diesel Generator MODE OF OPERATION: 5 TRAIN AFFECTED: Green CAUSE: Excessive engine vibration during a surveillance. Vibration was due to bearings being improperly located relative to the position of journals of the crank.
CORRECTIVE ACTION: The main bearing caps were relocated and extensive load testing performed.
(
REFERENCE:
LER 50-368/79-32)
DATE: 8/14/79 DURATION: 8.42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> ECC SYSTEM OR COMPONENT: No. 2 Olesel Generator MODE OF OPERATION: 1 TRAIN AFFECTED: Green CAUSE: Following a surveillance test the diesel could not be secured from the control room. This was due to an internal spring on the handswitch contacts being out of adjustment.
CORRECTIVE ACTION: Proper adjustment was made and the diesel was proved operable.
(
REFERENCE:
LER 50-368/76-69) 3
DATE: 8/26/79
- DURATION
- 1.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ECC SYSTEM OR COMPONENT: Safety Injection Tank 'D' MODE OF OPERATION: 1 TRAIN AFFECTED: N/A CAUSE: Safety injection tank level below technical specifications required 80.1% due to makeup valve failing to open on command.
CORRECTIVE ACTION: Makeup valve was manually opened and level was returned to normal. Valve maintenance was completed.
(
REFERENCE:
LER 50-368/79-077)
DATE: 9/25/79 DURATION: 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ECC SYSTEM OR COMP 0NENT: Refueling Water Tank MODE OF OPERATION: 1 TRAIN AFFECTED: N/A CAUSE: Refueling water tank boron concentration less than the technical specifications required 1749 ppmb due to incorrect tank makeup calculated baron concentration. Inaccuracy due to insufficient mixing prior to tank sampling.
, CORRECTIVE ACTION: Procedure modification to require tank volume i recirculation prior to sampling for boron analysis for RWT makeup concentration purposes.
(
REFERENCE:
LER 50-368/79-085) t 1
4 1
DATE: 2/22/80 DURATION: N/A ECC SYSTEM OR COMP 0NENT: No. 1 Diesel Generator MODE OF OPERATION: 5 TRAIN AFFECTED: Red CAUSE: During a surveillance test high vibration and load oscillations were experienced. This was caused by a sheared generator rotor shaft.
f CORRECTIVE ACTION: The generator shaft was replaced and the diesel generator was proved cperable.
J
(
REFERENCE:
LER 50-368/80-12)
DATE: 6/3/80 DURATION: 3.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ECC SYSTEM OR COMPONENT: Safety Injection Tanks 'C' & 'D' MODE OF OPERATION: 1 TRAIN AFFECTED: N/A CAUSE: Safety injection tank boron concentration less than the
- technical specifications requirec 1731 ppmb.
CORRECTIVE ACTION: Increase tank boron concentration.
(
REFERENCE:
LER 50-368/80-037) i I
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I 5
DATE: 6/7/80 DURATION: 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> i ECC SYSTEM OR COMPONENT: Safety Injection Tank 'D' MODE OF OPERATION: 3 TRAIN AFFECTED: N/A CAUSE: Safety injection tank boron concentration less than technical specifications required 1731 ppmb.
CORRECTIVE ACTION: Increase boron concentration of safety injection tank.
p (
REFERENCE:
8.ER 50-368/80-038) i t
DATE: 7/1/80 DURATION: 9.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
! ECC SYSTEM OR COMPONENT: Safety Injection Tank 'C' MODE OF OPERATION: 3 TRAIN AFFECTED: N/A l
CAUSE: Safety injection tank boron concentration less than the technical specifications required 1731 ppmb.
CORRECTIVE ACTION: Increase boron concentration of safety injection i tank.
(
REFERENCE:
LER 50-368/80-044) .
6
DATE: 7/2/80
- DURATION: 7.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i
ECC SYSTEM OR COMPONENT: Safety Injection Tank 'D' MODE OF OPERATION- 1 TRAIN AFFECTED: N/A CAUSE: Safety injection tank boron concentration less than the technical specifications required 1731 ppmb.
CORRECTIVE ACTION: Increase boron concentration of safety injection tank.
(
REFERENCE:
LER 50-368/80-044)
DATE: 9/2/80 DURATION: 10.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> ECC SYSTEM OR COMP 0NENT: Safety Injection Tanks 'A' & 'C' MODE OF OPERATION: 1 TRAIN AFFECTED: N/A CAUSE: Safety injection tank boron concentrations less than the technical specifications required 1731 ppmb due to dilution of
! the tank makeup path during extended shutdown cooling system operation.
i CORRECTIVE ACTION: Increase tank boron concentration and administrative controls to ensure accurate boron concentration values of makeup. .
(
REFERENCE:
LER 50-368/80-044 Rev. 1) i l
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l_ _ . . . . _ . __ _ _ _ _ , _ . . _ _ _ _ _ . . . . _ _ _ . .
J 1
DATE: 10/7/80 .
DURATION: 0.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Safety Injection Tank 'A' ECC SYSTEM OR COMP 0NENT:
MODE OF OPERATION: .1 TRAIN AFFECTED: N/A CAUSE: Safety injection tank pressure below technical specifications required 600 psig due to volume loss during sampling without capability of remote repressurization caused by inoperable valve.
I CORRECTIVE ACTION: Safety injection tank pressure was restored. Valve maintenance was completed.
(
REFERENCE:
LER 50-368/80-075)
. DATE: 10/14/80 DURATION: 0.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ECC SYSTEM OR COMP 0NENT: High Pressure Safety Injection Pump 'B' MODE OF OPERATION: 3 TRAIN AFFECTED: Green CAUSE: High pressure safety injection (HPSI) pump tripped on overcurrent due to a motor bearing misalignment.
CORRECTIVE ACTION: Complete corrective maintenance on pump motor. Line up redundant HPSI pump to flow path.
i LER 50-368/80-078)
(
REFERENCE:
I l
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8
DATE: 11/29/80 DURATION: 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ECC SYSTEM OR COMPONENT: High Pressure Safety Injection (HPSI) Valve, 2CV-5056 MODE OF OPERATION: 1 TRAIN AFFECTED: Orange CAUSE: HPSI valve failed to close and could not be remotely throttled to meet HPSI system flow requirements.
CORRECTIVE ACTION: Valve operator failure caused by a blown control power fuse. Fuse was replaced and valve returned to operable status.
(
REFERENCE:
LER 50-368/80-087)
- DATE
- 12/20/80 DURATION: 0.08 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ECC SYSTEM OR COMP 0NENT: No. 2 Diesel Generator MODE OF OPERATION: 3 TRAIN AFFECTED: Green
! CAUSE: The emergency diesel generator tripped on reverse power on breaker closure. This was due to manually increasing load too slowly. " -
l CORRECTIVE ACTION: The importance of applying load quickly to the i
emergency diesel generator during the evolution was discussed with all operators.
f (
REFERENCE:
LER 50-358/80-93) l l
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9 i
i DATE: 12/20/80 DURATION: 5.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> ECC SYSTEM OR COMPONENT: Refueling Water Tank ,,
MODE OF OPERATION: 3 TRAIN AFFECTED: All Trains , ,
CAUSE: RWT level indications inoperable due to frozen transmitters ', ,
caused by very low ambient temperatures and a de-energized heat tracing circuit.
' \-
CORRECTIVE ACTION: Reactor was shutdown to mode 3 operation. The level J transmitters were thawed out and the heat tracing circuits re-energized.
(
REFERENCE:
LER 50-368/80-091)
Unit 2 DATE: 1978-1980 ,
DURATION: Approximately 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per pump per test (total duration 14.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) 4 ECC SYSTEM OR COMP 0riENT: Sodium Hydroxide Pump 2P136A/B MODE OF OPERATION: Appear Listed Below t .
~
CAUSE: During surveillance testing the valve lineup does not permit d ,
full flow sodium hydroxide.
CORRECTIVE ACTION: During the-surveillance an operator is stationed in the area in order to return the system to full flow;'t .,
)'
conditions if needed. Also, it should be noted that th' full flow conditions could be returned within approximately five minutes. Specific dates of
, occurence are listed below (year-month-day).
I I
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.- - . - - . ._. - . .2
4 2P-136-A TRAIN AFFECTED: RED 2P-136-B TRAIN AFFECTED: GREEN Date Mode of Operation Date Mode of Operation 780101 , 5 780101 5 790101 ', 1 790101 1 800104 1 800119 1 800204 5 800218 5
' ',- 800304 5 800319 3
~! '
800403 , 1 800418 3 800502 1 800516 1 800601' 1 800616 1
- i. *800702' 1 800716 1 f
,, ! 800716' l 800815 1 t
800818 1 800918 5 800902 1 ~801018 1 801005 l' 801118 -
1 801103 3- 801219 1 801203 1 DATE: 1978-1980 4 .
l DURATION: Approximately 0.17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> pe'r pump per test.(total duration 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
ECC SYSTEM OR COMPONENT:' Sodium Hydroxide Tank CAUSE: Duringsurveillancetestingthevalveiineupdoesnotpermit
~
full flow from sodium hydroxide tank with the associated pump.
CORRECTIVE ACTION: During the surveillance test an operator is stationed in the area in order to return the system to full flow conditions if needed. Also, it should be noted l r. that the pump could be returned-to service within approximately five minutes. Specific dates of occurence are listed below.
Mode of Operation , Train Affected 780101 5 All Trains 790101 1 All Trains 600204 5 All Trains 800505 1 All Trains 800808 1 , All Trains 801108 1
~
'All Trains I
11 3' s
.-,.-e-- - -_ _ _ _ _ _ , - - . ,