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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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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKtNSAS 72203 (501) 371-4000 January 15, 1979 1-019-6 Director of Nuclear Reactor Regulation ATTN: M. R . 'd . Reid, Chief Operating Reactor Branch #1 U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Inservice Testing Program (File: 3065)
Gentlemen:
In October, 1977, we submitted our Inservice Inspection and Inservice Testing Programs which incorporated the 1974 AoME B6PV Code,Section XI through the Summer 1975 Addenda. Your April 20, 1978, letter granted interim approval, and on September 13, 1978, you requested additional in-formation in order to complete your evaluation. Attached are responses to those items c the IST Program which were not resolved during the meet-ings at Arkansas Nuclear One (ANO) on November 15 and 16,1978. These responses include a list of valves requiring IST (Enclosure 2), Relief Requests (Enclosure 1) for the equipment we feel that we cannot reasonably inspect and/or test, and explanation of why some valves cannot be quarterly stroked (fully or partially) during normal plant operation (Enclosure 3),
and justification for the deletion of certain valves from our IST Program.
Ver truly yours, W '
v/
Daniel H. Williams Manager, Licensing DHW: ERG:nj 7ef 790124 o/#f
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ENCLOSURE 1 INSERVICE INSPECTION RELIEF REQUESTS
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- 1. Component: Reactor Coolant Pumps ASME Class 1 Table IWB-2600 Item Category Description B.5.6 B-L-1 Pump Casing Welds Impractical Code Requirement: Table IWB-2500 Category B-L-1
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"The volumetric examination of 100% of the. pressure-retaining welds in at least one pump in each group of pumps performing similar~
functions in a system."
Raason for Relief:
The examination of reactor coolant pump casing welds by means of UT is, at present, beyond the " State of the Art". The use of RT is not practical, since the radioactive source must be placed inside the reactor coolant pump. Such an examination would expose personnel involved to dangerously high radiation IcVels. Surface preparation and decontamina-tion problems prohibit surface examination.
Alternate Examination:
A visual examination for evidence of leakage, structural distress, or corrosion.
- 2. Component: Buried Portions of the Service Water System ASME Class 3 Impractical Code Requirement: IWD-2600(b)
"A. system pressure. test in lieu of visual examinacion."
Reasons for Relief:
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- 1. Valves provided for isolation were not designed for pressure testing and are not adequate for this service.
- 2. S ufficient service water flow during normal operation . assures suf ficient flow during any emergency condition. (See FSAR s ection 9.3).
Alternate Examination:
Confirm service water flow is adequate during normal operation.
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- 3. Component: CF 1 A S B Valvb Category: C P G ID # 230 t
Impractical Code Requirement: INV-3520 (b)
"Normally closed check valves. . . shall be full-stroke exercised during each cold shutdown." .
Reason for Relief:
Full-stroking of these valves during cold shutdown could delay "
. start-up more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and create as much as 28,000 gallons of liquid waste.
.
Testing in lieu of Code Requirement:_
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.These valves shall be partial. stroke exercised during each refueling outage.
- 4. Component: BS 4ASB Valve Category: C P G ID #236 Impractical Code Requirement: IWV-3520 (b)
"Normally closed check Valves. . .shall be full-stroke exercised during each cold' shutdown."
Reason for Reli.cf: .
These valves are immediately upstream of the RB spray nozzels.
Water Flow cannot be used for stroking these check valves because the system is open ended into containment. Alternate test procedures require more manpower and equipment than is normal.ly available during cold shutdown.
Testing in lieu of Code Requirement:
These valves shall be partial-stroke exercised during each re-fuelinF outage.
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Page 1 of 15 -
ENCLOSURE 2 '
UNIT 1 VALVES REQUIRING INSERVICE TESTING .
1 LIrllTING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE PROCEDURE VALVI; N_0. _SYSTEtt DESCRI_PTION (IN) TYPE CAT CLASS _ POS POS tit!E EXERCISE LEAK EXERCISE _
PSV-1001 RCS Relief Pzr 3 Relief C 1 C 0 . NA- CODE NA 1401.03
-- . .-
PSV-1002 RCS Relief Pzr 3 Relief C 1 C 0 NA CODE NA 1401.03 Core Flood 1104.01 CF-1A RCS Discharge 14 Check
- C 1 C 0 NA + NA Supp. 1 Core Flood 1104.01 CF-1B RCS Discharge 14 Check C 1 C 0 NA + NA Supp. 3 1104.04 DH-13A RCS LP Injection 12 Check C 1 C 0 NA CSD* NA Supp. 3 1104.04 Dil-13B RCS LP Injection 12 Check C 1 C 0 NA CSD
1104.01 Dil-14A RCS LP Injection 14 Check C 1 C 0 NA CSD* NA Supp. 1 ,
_
1104.01 Dil-14B RCS LP Injection 14- Check C 1 C 0 NA CSD
_ _ _ _ . . _
1104.01 DIl-17 RCS LP Injection 8 Check C 1 C 0 NA CSD
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1104.04 Dif-18 RCS- LP Injection C Check C 1 C 0 NA CSD
- NA Supp. 1 1104.02 t!U-34A RCS IIP Injection 2 Check C 1 C 0 NA CSD
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1104.02 11U-34B RCS IIP Injection , 2 Check C 1 C 0 NA CSD * ,
NA Supp. 5 Revision'0 1005.08 December 19, 1978
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Page 2 of 15 ,
ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING
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f LIMITING SIZE [WV NOR ACC CLOSE TESTING PROCEDURE PROCEDURE VALVE NO._ SYSTEM DESCRIPTION (IN)_ TYPE CAT CLASS POS POS TIME EXERCISE LEAK EXERCISE 1104.02 MU-34C RCS IIP Injection 2 Check C 1 C 0 NA CSD* NA Supp. 5 1104.02 MU-34D RCS ]IP Injection 2 Check C 1 C 0 NA CSD* NA. Supp. 5 Main Steam to 1106.06 CV-2617 MS EFW Turbine 4 Gate
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2 C 0 70 see CODE NA Supp. 4 Main Steam to 1106.06 CV-2666 MS EFW Turbine Bypass 3 Gate B 2 C NA 80 see CODE NA Supp,. 3 Main Steam to' 1106.06 CV-2667 MS EFW Turbine 4 Gate B 2 C 0 70 see CODE NA Supp. 3 Main Steam 1102.01 CV-2691 MS Isolation 36 Gate B 2 0 C 10 sec CSD
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'tr in Steam 1102.01 CV-2692 MS lsolation 36 Gate B 2 0 C 10 see CSD
PSV-2684 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01
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PSV-2685 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01
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PSV-2686 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01
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PSV-2687 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01
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PSV-2688 MS Relief Main Steam l 10 Relief C 2 C 0 NA CODJ ,
NA 1404.01 ;
Revision'0 1005.08 -
December 19, 1978
Page 3 of 15 ENCLOSURE 2 UNIT 1 V'TNES REQUIRING INSERVICE TESTING LIrlITING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE PROCEDURE VALVE NO. SYSTEM DESCRIPTION (IN) TYPE CAT CLASS POS P03 TIME EXERCISE LEAK EXERCISE PSV-2689 t1S Relief Main Steam 10 Relief C 2 C 0 NA CODE .NA 1404.01
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l PSV-2690 MS Relief Main Steam 10 Relief C 2 C .0 NA CODE NA 1404.01 PSV-2691 MS Relief Main Steam 10 Reliel C 2 C 0 NA CODE NA 1404.01 PSV-2692 MS Relief Main Stean 10 Relief C 2 C 0 NA CODE NA 1404,.01 PSV-2693 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01
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PSV-2694 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01 l.
PSV-2695 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01 ,
PSV-2696 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01 PSV-2697 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01
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PSV-2698 MS Relief Main Steam 10 Relief C 2 C 0 NA CODE NA 1404.01.
I PSV-2699 MS Relief Main Steam 10 Relief C 2 C 0 NA' CODE NA 1404.01
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' CV-1214 MU RCS Letdown 2 Ca t:- A 2 0 C 20 sec CSD* Table 3 Supp. 2 g Revision'0 1005.08 December 19, 1978
Page 4 of 15 ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING .
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]- SIZE IWV NOR ACC LIMITING CLOSE TESTING PROCEDURE' PROCEDURE
_ VALVE NO. SYSTEM DESCRIPTION (IN) TYPE CAT CLASS POS POS ' TIME EXERCISE LEAK EXERCISE 1304.23 1J04.20 CV-1216 MU RCS Letdown 2 Gate A 2 0 C 20 see CSD* Table 3 Supp. 2 l ---
CSD* 1104.02 CV-1219 MU IIP Injection 2 Globe B 2 C 0 20 see NA Supp. 1 CBD
- 1404.02 CV-1220 MU IIP Injection 2 Globe B 2 C 0 20 see NA- Supp. 1 CSD*
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1403.23 1304.70 CV-1221 MU RCS Letdown 2 Gate A 2 0 C 20 sec Table 3 Supp. 1 SD*
1104.02 CV-1227 MU HP Injection 2 Globe B 2 C 0 20 sec NA Supp. 1 CSD*
1104.02 CV-1228 MU IIP Injection 2 Globe B 2 C 0 20 see NA Supp. 1 l 1304.70 CV-1234 MU RCS Makeup - 2 Gate B 2 0 C 20 see CODE NA Supp. le 1304.23 1104.02 CV-1270 MU RCP Seal Bleed Off 1 Globe A 2 0 C 20 sec CSD* Table 3 Supp. 5 1304.23 1104.02 CV-1271 MU- RCP Seal Bleed Off 1 Globe 'A 2 0 C 20 see CSD
. 1304.23 1104.02 CV-1272 MU RCP Seal Bleed Off 1 Globe A 2 0 C '20 sec CSD
- Table 3 Supp. 5 1304.23 1104.02 CV-1273
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MU RCP Seal Bleed Off 1 Globe *A 2 0 C 20 see CSD
- Tabic 3 Supp. 5 1304.23 1104.02
- CV-1274 MU RCPSealBleedOffj 1 Globe A 2
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O C 20 see CSD
- Table 3 Supp. 5 Revision 0 1005.08 December 19, 1978
Page 5 of 15 ENCLOSURE 2 -
UNIT 1 VALVES REQUIRING INSERVICE TESTING
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LIMITING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE' PROCEDURE VALVE NO. SYSTEM DESCRIPTION (IN> TYPE CAT CLASS POS POS TIME EXERCISE LEAK EXERCISE 1104.02 CV-1300 MU MU Pump Recirc 2 Globe A 2 0
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C 20 see CSD* NA Supp. 5 1104.02 CV-1301 MU MU Pump Recirc 2 Globe A 2 0 2 20 sec CSD* NA Supp. 5 1104.02 MU-19A MU Pump Discharge 4 Check C 2 C 0 NA CODE NA Supp. 4
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1104.02 MU-19B l HU Pump Discharge. 4 Check C 2 C 0 NA CODE NA Supp. 3 1104.02 MU-19C MU Pump Discharge 4- Check C 2 C 0 NA CODE NA Supp. 2 1304.70 CV-1400 ,
Dil Pump Isolation 10 Gate B 2 C 0 20 see CSD
, 1304.70 CV-1401 Dl! Pump Isolation 10 Gate B 2 C 0 20 see CSD
- NA Supp. 2 1304.70 CV-1405 Dli Pump Suction 14 Gate B 2 C 0 90 sec CSD
.. - --
1304.70 CV-1406 Dii- Pump Suction 14 Gate 'B 2 C 0 90 see CSD
. 1104.04 CV-1407 Dli BWST Outlet 14 Gate B 2 C 0 20 see CODE NA Supp. 1
_
1104.04 CV-1408 DII BWST Outlet 14 Gate *B 2 C 0 20 see CODE NA Supp. 2
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1104.04 711-2A Dil Pump Discharge 10 Check C 2 C 0 NA CODE NA Supp. 1 g Revision 0 1005.08 December 19, 1978
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Page 6 of 15 ,
. ENCLOSURE 2' UNIT 1 VALVES REQUIRIP: INSERVICE TESTING
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LIMITING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE ^ PROCEDURE (VALVE NO. SYSTEM DESCRIPTION (IN) TYPE CAT CLASS POS POS TIME EXERCISE LEAK EXERCISE 1104.04 DH-2B Dil Pump Discharge 10 Check C 2 C ,
0 NA CODE NA Supp. 2 1104.05 CV-2400 BS Puiup Discharge. 8 Globe B 2 C 0 20 sec CODE NA Supp. 4 1104.05 CV-2401 ES Pump Discharge 8 Globe B 2 C 0 20 sec CODE NA Supp. 4
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Stop 1104.05 CV-2410 BS N Thio Sulfate 4 Check C 2 C 0 NA CODE NA Supp. 4 Stop 1104.05 CV-2411 BS Na Thio Sulfate 4- Check C 2 C 0 NA CODE NA Supp. 5 1104.05 BW-6A ,BS Pump Suction 10 Check C 2 C 0 NA CODE NA Supp. 3 1104.05 BW-6B BS Pump Suction 10 Check C 2 C 0 NA CODE NA Supp. 9
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BS-4A BS Pump Discharge 8 Check C 2 C 0 NA +
BS-4B BS- Pump Discharge 8 Check 'C 2 C 0 NA +
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- 1102.01 CV-2630 FW MFW 18 Ga'e B 2 0
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- 1102.02 CV-2680 FW MFW 18 Gate B 2 0
, FW-7A FW FEV Check C 2 0 C NA CSD
} 18 Revision 0 1005.08 December 19, 1978
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- Page 7 of 15 ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING
- LIMITING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE' PROCEDURE VALVE NO. , SYSTEM DESCRIPTION _( IN) _ TYPE CAT CLASS POS POS TIME EXERCISE LEAK EXERCISE 1102.02 FW-7B FW MFW 18 Check C 2 0 C NA CSD* NA Supp._2
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1106.06
, FW-13A EFW EFW 4 Check C 2 C 0 NA CSD* NA Supp. 4
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1106.06 FW-133 EFW EFW 4 Check C 2 C 0 NA CSD* NA Supp. 4
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1106.06 CV-2617 EFW MS to EFW Pump. 4 Gate B 2 C 0 70 see CODE NA Supp. 4
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1106.06 CV-2620 EFW CV-2626 Bypass 4- Gate B 2 C 0 30 see CODE NA Supp. 3
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1106.06 CV-2626 EFW EFW Control 4 Gate B 2 C 0 30 see CODE NA Supp. 3 1106.06 CV-2627 EFW CV-2670 Bypass 4 Gate B 2 C 70 see CODE NA Supp.e4 1106.06 CV-2670 EFW EFW Control. 4 Gate B 2 C 0 30 sec CODE NA Supp. 3
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1404.05 CV-1616 CA- NaOH Tank Outlet 4 Gate B 2 C 0 30 sec CODE NA Supp. 2
.. -- - - ..
. 1404.05 CV-1617 CA NaOH Tank Outlet 4 Gate B 2 C 0 30 sec CODE NA Supp. 2 Stop 1404.05 CA,-61 CA NaOH Discharge 4 Check 'C 2 C 0 NA CODE NA Supp. 2 Stop 1404.05
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CA-62 CA NaOH Discharge
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4 Check C 2 C 0 NA CODE NA Supp. 2
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Revision 0 1005.08 December 19, 1978
Page 8 of 15 ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING l
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LIrllTING SIZE IWV NOR ACC - CLOSE TESTING PROCEDURE' PROCEDURE VALVE NO. SYSTEf! DESCRIPTION (IN) TYPE CAT CLASS POS. POS TIrlE EXERCISE LEAK EXERCISE Stop 1104.05 CA-90A CA Na Thio Discharge 4 Check C 2 C
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0 NA CODE NA Supp. 2.
Stop 1104.05 CA-90B CA Na Thio Discharge 4 Check C 2 C 0 NA CODE NA Supp. 1 Stop 1104.02 BW-2 BW HU Pump Suciion 6 Check C 2 C 0 NA CSD* NA Supp. 5
, Stop 1104.02 BW-3 BW MU Pump Suction 6 Check C 2 C 0 dA CSD* NA Supp. 5 1104.04 BW-4A BW BWST Outlet 14 Check C 2 C 0 NA CODE NA Supp. 1 1104.04 BW-4B ,BW BWST Outlet 14 Check C 2 C 0 NA CODE NA Supp. 2 t ____
1304.23 1304.70 CV-2214 ICW Letdown Cooler Iso 8 Gate A' 2 0 C 20 see CSD* Table 3 Supp. 2' 1304.23 1304.70 CV-2215 ICW Letdown Cooler Iso 8 Gate A 2 0 C 90 see CSD* Table 3 Supp. 2 CRD/RCP , 1304.23 1304.70 CV-2220 ICW Cooling Iso 8 Cate A 2 0 C 90 sec CSD* Table 3 Supp. 2 CRD/RCP -
1304.23 1304.70 CV-2221 ICW Cooling Iso 8 Gate A 2 0 C 60 sec CSD* Table 3 Supp. 2 Letdown 1304.23 1304.70 CV-2233 ICW Cooler Iso 8 Gate 'A 2 0 C 60 sec CSD* Table 3 Supp. 2 1304.23 1304.70 CV-2234 ICW RCP Motor Iso I8 Globe A 2 0 C 30 sec CSD* Table 3 Supp. 2 Revision 0 1005.08 December 19, 1978
Page 9 of 15 ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING
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lit!ITING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE' PROCEDURE VALVE NO. SYSTEM DESCRIPTION (lN) TYPE CAT CLASS POS POS title EXERCISE LEAK EXERCISE 1304.23 1304.70 CV-2235 ICW CRD Iso 3 Globe A 2 0
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C 30 sec CSD* Table 3 Supp. 2 1304.23 1304.70 CV-1052 CZ Quench Tank Drain 3 Gate A 2 0 C 1 sec CODE Tabie 3 Supp. 2 1304.23 1304.70 CV-1053 CZ Quench Tank Drain 3 Gate A 2 0 C 20 see CODE Table 3 Supp. 2
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1304.23 1304.70 CV-1054 SS Quench Tank Drain 1 Gate A 2 0 C 30 sec CODE Table 3 Supp. 2 1304.70 CV-1814 SS Pz Steam Sample -
Globe B 1 0 C 20 sec CODE NA Supp. I 1304.70 CV-1816 ,
SS Pz Water Sample Globe B 1 0 C 20 sec CODE NA Supp. 1 1304.23 1304.70 CV-1845 SS Quench Tank Sample Globe A 2 0 C 20 sec CODE Table 3 Supp. le 1304.23 1304.70 CV-5611 FIRE RB Iso 3 Gate A 2 0 C 30 see CODE Table 3 Supp. 1
_
1304.23 1304.70 CV-5612 FIRE RB Iso 3 Gate 'A 2 0 C 30 sec CODE Table 3 Supp. 1
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1304.23 1304.70 CV-1065 CS Quench Tank Iso 3 Gate A 2 0 C 20 see CODE Table 3 Supp. 1
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1304.23 1304.70 CV-1667 N2 N2 Supply 1 Globe 'A 2 0 C 20 see CODE Table 3 Supp. I 1304.23 1304.70 CV-6202 CW Inlet Iso i6 ' ate A 2 0 C 30 see CSD* Table 3 Supp. 2 Revision 0 1005.08 December 19, 1978
Page 10 of 15 ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING
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LitlITING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE' PROCEDURE VALVE NO. SYSTEtl DESCRIPTION (TN) TYPE CAT CLASS POS. POS ' TI tlE EXERCISE LEAK EXERCISE 1304.23 1304.70 CV-6203 CW Outlet Iso 6 Gate A. 2 0 C 30 sec CSD* Table 3 Supp. 2 1304.23 1304.70 CV-6205 CW Outlet Iso 6 Gate A 2 0 C 60 sec CSD* Table 3 Supp. 2 "D" Dil Rm 1104.04 CV-3800 SW Cooler Inlet 3 Gate B 3 C 0 90 cec CODE NA Supp. 2
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"B" DII Rm , 1104.04 CV-3801 SW Cooler Inlet 3 Gate B 3 C 0 90 see CODE NA Supp. 1 "C" DII Rm 1104.04 CV-3802 SW Cooler Inlet 3- Gate B 3 C 0 90 see CODE NA Supp. 1 "A" Dl! Rm 1104.04 CV-3803 ,SW Cooler Inlet 3 Gate B 3 C 0 90 see CODE NA Supp. 2 1104.05 CV-3804 SW E47A Spray'P 1 Gate B 3 C 0 20 sec CODE NA Supp. 3 1104.05 CV-3805 SW E47B Spray P 1 Gate B 3 C 0 2 sec CODE NA Supp. 5 1104.05 CV-3805 SW- E47B Spray P li Gate B >3 C 0 20 see CODE NA Supp. 5 Emergency Diesel
- 1104.02 CV-3806 SW "A" Cooler Inlet 6 Gate B 3 C 0 120 see CODE NA Supp. 2 Emergency Diesel ,
CV,-3807 SW "B" Cooler Inlet 6 Gate B 3 C 0 120 sec CODE NA
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MU Pump LO 1104.02 CV-3808 SW Clr Inlet A 3 Cate B 3 C 0 90 see CODE NA Supp. 4 l
Revisiou 0 1005.08 December 19, 1978
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Page 11 of 15 -
_ ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING -
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LIMITING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE' PROCEDURE VALVE N0. _ SYSTEM DESCRIPTION (IN) TYPE CAT CLASS POS POS TIME EXERCISE LEAK EXERCISE MU Pump LO 1104.02 CV-3809 SW Cooler Inlet B 3 Gate B 3 C 0 90 sec CODE NA Supp. 2 MU Pump LO 1104.02 cv'-3810 SW Cooler Inlet C 3 Gate B 3 C 0 90 sec CODE NA Supp. 3 1104.04 CV-3821 SW B-DH Cooler Outlet 12 Btfly B 3 C 0 45 see CODE NA Supp. 2
, 1104.04 CV-3822 SW A-DH Cooler Outlet 12 Btfly B 3 C 0 45 sec CODE NA Supp. 1 A-DIf. Lube Oil 1194.04 CV-3840 SW Cooler Outlet 1 Gate B 3 C 0 20 sec CODE NA Supp. 1 A-DH Lube Oil 1104.04 CV-3S41 ,SW Cooler Outlet 1 Gate B 3 C 0 20 sec. CODE NA Supp. 2 l VUC-2B ES SW 1304.70 CV-3900 SW Gear Rm Clr Inlet 3 Gate B 3 C 0 20 see CODE NA Supp. 'l VUC-2B ES SW 1304.70 CV-3902 SW Gear Rm Clr. Outlet 3 Gate B 3 C 0 20 see CODE NA Supp. 1
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-t VUC-2D ES ,
1304.70 CV-3903 SW- Gear Rm Clr Inlet 3 Gate B 3 C 0 20 see CODE NA Supp. 1 VUC-2D ES SW '
1304.70 CV-3905 SW Gear Rm Clr Outlet 3 Gate B 3 C 0 20 sec CODE NA Supp. 1
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SW Loop II , 1304.70 CV-3811 SW Iso to ICW 14 Btf y B 3 0 C 60 sec CSD* NA Supp. 2 SW Loop I 1304.70 CV-3320 SW Iso to ICW 14 Btfly B 3 0 C 60 see CSD* NA Supp. 2 Revision 0 1005.08 December 19, 1978
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Page 12 of 15 ENCLOSURE 2 UNIT 1 VALVES REQU'ETNG INSERVICE TESTING .
7 Lit!ITING (
SIZE IWV NOR ACC CLOSE TESTING PROCEDURE' PROCEDURE VALVE NO. SYSTEM DESCRIPTION (IN) TYPE CAT CLASS POS POS TIllE EXERCISE LEAK EXERCISE Cross-tie SW '1304.70 CV-3640 SW B to C Discharge 18 Btfly B 3
- C 60 sec CSD* NA Supp. 2 1304.70 CV-3641 SW Loop II Iso 18 Btfly B 3
- C '9 see CSD* NA Supp. 2 Cross-tie SW 1304.70 CV-3642 SW 18 3
- Supp. 2 B to C Discharge Btfly B C 60 sec CSD* NA
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1304.70 CV-3643 SW Aux C1g Loop Iso 18 Btfly B 3 0 C 60 see CSD* NA Supp. 2 Cross-Tie SW
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1304.70 CV-3644 SW A to B Discharge 18 Btfly B. 3
- C 60 see CSD* NA Supp. 2 1304.70 CV-3645 SW Loop I Iso 18 Btfly B 3
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60 see CSD* NA Cross-tie SW 1304.70 CV-3646 SW A to B Discharge 18 Btfly B 3
- C Supp. 2 60 sec CSD* NA RB Cooler 1104.33 CV-3812 SW SW Inlet 10 Btfly B 2 C 0 30 see CODE NA Supp. 3 RB Cooler 1104.33 CV-3813 SW SW Inlet 10 Btfly B 2 C 0 30 see CODE NA Supp. 3 RB C<,oler . 1104.33 CV-3814 SW SW Outlet 10 Btfly B 2 C 0 30 sec CODE NA Supp. 3 RB Cooler
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SW SU Outlet 10 Btfly B 2 C 0 30 see CODE NA Supp. 3 1304.23 1304.70 .
CV-7443 HVAC Hydrogen Purge j 2 Gate A 2 C 0 30 sec coaa Table 3 Supp. 1
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Revision 0 1005.08 December 19, 1978
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Page 13 of 15 ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING .
1 - LIMITING SIZE NOR ACC CLOSE TESTING PROCEDURE PROCEDURE
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IWV VALVENO.l SYSTEM DESCRIPTION (IN) TYPE CAT CLASS POS POS TIME EXERCISE LEAK EXERCISE 1304.23 1304.70 CV-7444 IIVAC IIydrogen Purge 2 Gate A. 2 C 0 30 sec icoog Table 3 Supp. 1 1304.23 1304.70 CV-7445 IIVAC llydrogren Purge 2 Gate A 2 C 0 30 sec CODE Table 3 Supp. 1 1304.23 1304.70 CV-7446 IIVAC IIydrogen Purge 2 Gate A 2 C 0 30 sec CODE Table ~3 Supp. 1
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1304.23 1304.70 CV-7447 IIVAC Ilydrogen Purge- 2 Gate A 2 C 0 30 sec CODE Table 3 Supp. 1 1304.23 1304.70 CV-7448 IIVAC IIydrogen Purge 2 Gate A 2 C 0 30 sec CODE Table 3 Supp. 1 1304.23 1304.70 CV-7449 , IIVAC lIydrogen Purge 2 Gate A 2 C. 0 30 sec. CODE Table 3 Supp. 1 1304.23 1304.70 CV-7450 llVAC llydrogen. Purge 2 Gate A 2 C 0 30 sec CODE Table 3 Supp.el Air Particulate 1304.23 1304.70 CV-7453 IIVAC Monitor 1 Globe A 2 0 C 30 sec CODE Table 3 Supp. 1
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Air Particulate 1304.23 1304.70 CV-7454 IIVAC Monitor' 1 Globe A 2 0 C 60 see CODE Table 3 Supp. 1 PSV-1000 RCS Pz Relief 2 1 0 j
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CV-1404 Dil Dll Pump Suction 12 Gate 2 0 Operator Controlled g gg Dil Removal
- CV-1410 Dil From Reactor 12 Gate Operator Controll :d
_.___1_____
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Revision 0 1005.08 December 19, 1978
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Page 14 of 15
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ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING .
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. LIMITING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE' PROCEDURE VALVEhj0._ SYSTEM DESCRIPTION (TN) TYPE CAT CLASS POS POS ~ TIME EXERCISE LEAK EXERCISE RCB CV-1414 DH Sump Suction 14 Gate 0pc ator Con . rolled jg,y
, 777 RCB CV-3415 DH Sump Suction 14 Gate Ope cator Con trolled jg7 _7
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CV-1428 DH Cooler Outlet 10 Globe Ope rator Controlled pgq
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CV-1429 DH Cooler Outlet 10 Globe Operator Controlled jpg , p g ,j CV-2415 CF CFT Outlet 14 Gate Locked in Position CV-2419 ,
CF CFT Outlet 14 Gate Locked in Position 1304.23 CV-4100 DWD RB Sump Drain 4 Gate A ? C C NA NA Table 3 NA e 1304.23 CV-4446 DWD RB Sump Drain 4 Gate A 2 C C NA NA Table 3 NA RB Vent to 1304.23 CV-4803 GZ- Gaseous Waste 2 Globe 'A 2 C C NA NA Table 3 NA RB Vent to . 1404.23 CV-4804 GZ Gaseous Waste 2 Globe A 2 C C NA NA Table 3 NA 1304.23 CV-7401 VSF RB Purge Air 54 Btfly *A 2 C C NA NA Table 3 NA 1304.23
!CV-7402 VSF RB Purge Air 54 Btfly A 2 C C NA NA Table 3 NA
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Revision 0 1005.08 December 19, 1978
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Pdge 15 of 15 '
ENCLOSURE 2 UNIT 1 VALVES REQUIRING INSERVICE TESTING ~
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LltilTING SIZE IWV NOR ACC CLOSE TESTING PROCEDURE PROCEDURE
, VALVE NO. SYSTEf! DESCRIPTION (IN) TYPE CAT CLASS POS. PDS TIllE EXERCISE LEAK EXERCISE
- 1304.23 CV-7403 VSF RB Purge Air 54 Btfly A 2 C C NA NA Table 3 NA
[___ _ _ _ _
_
1304.23 CV-7404 VSF RB Purge Air 54 Btfly A 2 C C NA NA Table 3 NA
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Ci.-49 CA Na0l! Tank Outlet 4 Gate E 2 Loc ked Open NA NA
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Combined SW Loop CV-3823 SW
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Discharge to Pond 18 Btfly E 3 Opc rator Cor trolled gg 7 Combined SW Loop C'!-3824 SW Discharge to Flume 18 Btfly E 3 Opera to r. Cor trolled ggg g g ggg l
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Revision 0 1005,08 December 19, 1978
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FOOTNOTES FOR ENCLOSURE TWO
+ This indicates that we have requested relief in Enclosure 1.
- These valves cannot be operated during normal plant operation and shall be full-stroke exercised during each cold shutdown as required by IWV-3520 (b) .
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O 4
O e
4
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O e e
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ENCLu..URE 3 EXPLANATION OF WHY VALVES CANNOT BE STROKED DURING NORMAL PLANT OPERATION CF 1 A 6 B, DH 13 A 6 B, DH 14 A 6 B, DH 17 and DH 18 - Valves cannot be lifted against reactor pressure.
MU 34 A, B, C 6 D - Testing would the: mally shock HPI -nozzels.
CV 2691 6 2692 . Stroking during normal oepration would cause a reactor trip due to high RC pressure and/or temperature.
CV 1214, 1216, 1221 - Failure of these valves in closed position during test would necessitate stopping RC pwnp seal injection and the RC pimps.
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CV 1219, 1227, 1228 - If RCS pressure exists down stream of these valves, one check' valve is all that protects low pressure piping upstream.
CV 1220 - RCS pressure exists downstream of this valve due to make-up in-jection. Testing during normal oepration would result in high pressure.
bcing applied to upstream check valve, and if this check valve failed, the pressure in piping upstream would exceed design conditions. ,
CV 1270,.1271,1272,1273 and 1274 - Failure of these valves in a closed
- position during test could result in damage to the RC pump seals. ,
CV 1300, 1301 - Closing either of these valves during normal . operation would damage the operating make-up pump. ,
CV 1400, 1401 - If RCS pressure exists downstream of these valves, opening them would damage the. low pressure injection system.
CV 1405, 1406- Stroking these valves would allow a partial draining of LP.I and HPI pump suction piping. Should ES actuation occur during a test, the HPI and LPI pumps would be damaged.
BS 4 A 6 B - These valves are immediately upstream of the RB. spray nozzels.
Water flow cannot be used for stroking these. check valves. Stroking requires draining lines inside the reactor building which is impractical.during normal operation.
CV 2630, 2680 - Stroking during normal operation would result in a reactor trip due to high power or high pressure.
FW 7 A.6 B - Closing these valves during normal oepration would stop feedwater flow to a steam generator. Loss of heat sink to either RCS loop would cause
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high pressure and temperature. Eittar.of these conditions would trip the reactor.
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FW 13 A 6 B - Cold emergency feedwater cannot be introduced into a steam generator without upsetting the feedwater control system and causing a-reactor trip.
CV 2214, 2215, 2233 - Closing these valves during normal operation would increase letdown temperature and cause isolation of the letdown system.
Without letdown, seal injection would raise the pressurizer level above safe operating limits.
CV 2220, 2221 - Failure of either valve in a closed position would require stopping all RC pumps and de-energi ing the control rod drives.
CV 2234 - Failure in a closed position would result in the loss of cooling for the RC pump motor air and lube oil coolers. Without this cooling, all RC pumps would have to be stopped.
CV 2235 - Failure in a closed position would require de-energizing the control rod dri.es.
CV-6202, 6203, 6205 - Failure of one of these valves in a closed position
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would trip the main chillers.
CV 3640, 3641, 3642, 3643, 3644, 3645, 3646, 3811, 3820 - Testing these valves during normal operation would result in inadequate flow to components
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at high elevations due to reductions in service water flow.
BW 2, BW 3 - Testing during normal operation would berate the RCS and
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cause control rod positioning outside Tech. Spec. limits.
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