Responds to Generic Ltr 91-06, Resolution of Generic Issue A-30, 'Adequacy of Safety-Related DC Power Supplies.'ML20085K253 |
Person / Time |
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Site: |
Arkansas Nuclear ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
10/25/1991 |
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From: |
James Fisicaro ENTERGY OPERATIONS, INC. |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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References |
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REF-GTECI-A-30, REF-GTECI-EL, TASK-A-30, TASK-OR 0CAN109106, CAN109106, GL-91-06, GL-91-6, NUDOCS 9110300255 |
Download: ML20085K253 (11) |
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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
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g: - Entcrgy ""av oa 'a"aa '"c-Operations October 25, 1991 OCAN109106 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station P1-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 & 50-368 License Nos. DPR-51 & NFP-61 Resolution of Generic issue A-30,
" Adequacy o f Sa fety-Relat ed DC Powe r Supplies" - Generic Letter 91-06 C
GentIemen:
The NRC Staf f completed the evaluation of Generic Issue (01) A-30 as part of the resolution of Gl-128, " Elect rical Power Reliability." G1 A-30
[
focuses on safety-related de systems. As a result of this evaluation, the Staf f dott rmined that cert ain maintenance, surveillance, and '
monitoring provisions are appropriate for safety-related de systems. The Staff believes that most plants have already implemented most of these provisions because of a number of actions taken previously by the Staff and the industry.
Generic Letter (GL) 91-06 (dated April 29, 1991) provided the results of the NRC's evaluation of the generic issue and requested licensees to provide written responses to the questions provided in Enclosure 1 of the GL.
This submittal provides the requested responses for Arkansas Nuclear One, Units 1 and 2 (ANO-1 & 2). The ANO-1 & 2 specific responses are provided in Attachments 1 and 2, respectively.
In accordance with the requirements of GL 91-06, this letter is being signed under oath. Should you have any questions regarding our' response to this issue, please contact me.
Very truly yours, f,, ~<. )5%
(amos . FisIcaro Director, Licensing JJF/RWC/sjf 1 Attachments I
A\ l I
91103002b5 Y110D n~ PDR ADOCK 05000313 (
4a p PDR
U. h. NRC October 25, 1991 Page 2 cc: Mr. Robert Martin D. S. Nuclear Regulatory Com.alssion Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Resident inspector g Arkansas Nuclear Une - ANO-1 6 2 Number 1, Nuclear Plant Road Iussellville, AR 72801
, Mr. Thomas W. Alexion NRR Project Mannger, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mall Stop ll-D-23 One White Flint North
( 11555 Rockville Pike Rockvilln, Maryland 20852 Ms. Sheri Peterson NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mai1 Stop 11-D-23 One White Tilnt North 11555 Rockv111n Pike Rockville, Maryland 20852
. 'STATE OF ARKANSAS )
) SS COUNTY OF 1,0GAN )
'1, James J. Fisicaro, bning duly sworn, subscribe to and say that I am Director, l.icensing at ANO for Entergy Operations, that I have full authority to execute this af fidavit; tha' I have road the document numbered OCAN109136 and know the contents thereof; and that to the best of my knowledge. Information and belief the statements in it are true, tw h.bAL4.~
Jamesf). Fisicaro SUBSCRIBED AND SWORN TO beforo me, a Notary I'ublic in and for the County and State above named, this _ _ day of ,
1991.
Notary Public My Commission Expirns:
?
4
.- ATTACitMENT 1
, 1. ' Unit ANO-1
- 2. a. The number.of independent redundart divisions of Class IE or safety-related de power for this plant is TWO. (include any separate Class 1E or sa fety-related de, such as ar1y de dedicated to the diesel generators.)
- b. The number of functional safety-related divisions of de power necessary to attain safe shutdown for this unit is ONE.
- 3. . Does the control room at this unit have the following separate, independently annunciated alarms and judications for each division of de pcwor? ,
- a. alarms 1-. Battery disconnect or circuit breaker open? YES (Multipoint Alarm) ,
- 2. Battery charger disconnect or circuit breaker open (both input ac and output de)? YES (Multipoint Alara)
- 3. de system ground? YES (Multipoint Alarm)
L 4. de bus undervoltage? YES
- 5. de bus overvoltage? YES (on SPDS)
- 6. Battery charger failure? YES (Mu'itipoint Alarm)
- 7. Battery discharge? ND
- b. Indications 1, Battery float char; current? NO
- 2. Battery circuit output current? -NO
- 3. Battery discharge?. NO
- 4. Bus voltage? YES (on SPDS)
- c. Does the unit have written procedures for response to the above alarms and indications? YES
- 4. Does this unit have indication of bypassed and inoperable status of circuit breakers or other devices that can be used to disconnect the
-battery and battery charget from its.dc bus and the battery charger-from
-its'ac power source during maintenance or testing? YES
f, . If the answer to any pntt of question 3 or 4 is no. then provido in.
. formation justifying the existing design features of the Pellity's '
safety-related dc systems. *Sco note below.
3 ad Although battery discharge is not specifically annunch tad in the 3
control ro,)m, the operators have alnres which will indicate when the battery is discharging. -
4 l' the battery is discharging due to loss of AC poser or battery charger fa.11 ore, the control room operators will receive alarms that the battery charger in disconnected or the circuit breaker is oper, and that the charger has failed.
If the battery begins to discharge because the load exceeds the corrent supplying capacity of the battery charger. then the de bus must be at 116 Vdc or below sin,e this is the terminal voltage of the battery. This condition is annunciated in the control room.
3.b J: An ammeter is located on the battery chntgert however, the scale is not adequate to accurately read small float charge currents. Control room float current indication is 1,ot necessary since the condition of the battery is ensured by recording pilot cell voltage, temperature, and specific gravity and the overr.11 battery bank voltage on a daily basis as required by Technical Specification 4.6.2.
3.b.2: The lentication of the battery circuit output current is provided by n -
local ammeter. Local indication is sufficient with the control room alarms described in 3.a above and the daily surveillance procedure required for these battery banb hb.3r Although there is no specific battery discharge indication in the control room, an alarm which alerts tbs operators when the battery bank is beginning to discharge is provided as described in response to question 3.a.7.
The operators can then monitor the local ammeters and voltmeters and the bus voltage indication in the control room as necessary.
- 6. (1) llave you conducted a review of maintennnce and testing activities to minimize the potential for human error causing more than one de division to bn unavailable? NO and (2) do plant procodores prohibit maintenanen or testing on redundant de divisions at the same time? YES !
11 the facility Technical Specifications have provisions equivalent to those found in the Westinghouse and Combustion Engineering Standard Technical Specification for maintenance and surveillance, then question 7 may bn skipped and a statemont to that offect mny be inserted horn.
NOT APPLICABLE t
l.
I l
,7.. Aro maint erwocn, s,'irvellinnre and t est procoduren r egarding stat ion ,
, batterien conducted tuntinely /it this plant? Speciffently
- n. At Ice enco par 7 days, are ihn following verified to he ,
within are.vtabir I Nits;
- 1. "; tot c Ii c1 ict rolyte levol? YES r
? -er 4
- 4c gravit y nr chntging e ntrent ? YES
- 3. I'lont voltage? YES
- 4. Total bus voltagn on float charge? YES 5 Physient condit ion of all cells? YES :
- b. At lennt once per 92 dnya, or withlei 7 dayn af ter a battety ;
dischargo, overchargo, or if the pilot coll rendingn are outside the 7-day survoillance requirements nro the following '
verified to be within acceptablo limita: (Sco number 7.b under question 9)
- 1. Electrolyto level of-cach coll? YES
- 2. The averngn specific gravity of all celln? YES
- 3. The specific gravity of _ eneti coll? TES
- 4. Tho averngn electrolyte t emperat urn of a reprencatat ive numb.ir of calls? YES i
- 5. The float voltage of ench en117 YES i
- 6. Visually innpect or mensurn renistanco of toiminnin and I connectorn (including the connectorn at the de bus)? YES ,
- c. At least nyery 18 months, are the following verified:
- 1. l.ow resistance of each connection (by test )? YES I
- 2. Physical condition of t he b:tt ery? ; YES i 3.11nttery charger capability to deliver its design duty cycle to the de bus? YES
- 4. The capability of thn batacry to deliver its design duty cycle to the de bon? NO-l S. Ench individual' coll volingo in within acceptable limitn during thn nervice test? N0
- d. At least nyery 60 months, in capacity of each batt ery vert fled by performance of a discharge test? YES
- e. At innat annually, in thn hattery capacity vnrified by per-formance dischargo tent , if the hatt ery shows signs of de- _
i_
gradation or has reached 85*. of the expected service lifo? 8 l NO_
l l
e *- em +' --M-ree---e, _+e.c.,r---,e+-
amem ,,rs w y-e, v y ma r r -
- t- t"i r e-* sween----r*==r-<-m-ew- sw e 'e= g n---wv & ew 1 e w.-m e e -w--w w e 's m 't w r+
- r - wt e mn-ye ry ..r--+m r
,8 . Doca this plant have operat ional f ontur es such t hat following loss of one safety-related de power supply or bon:
- a. Capabilit y is maintained for ensuring continued and adequate reactor cooling? YES
- b. React or coolant system totegrity and isolnt ton onpnbility are mnintained? YES
- c. Opetating procedures, inst t ument at ion (including indicator s and annuncintors), and contr01 funttions nre adequntr to initiate systems as required t o maint ain adequat e core cooling? YES 9 If the answer t_ my part of question 6, 7 or f. is no, then provide your basis for not onr f orening t he rnnint enance , surveillance and test procedures dest si i and/or the bases for not including the operationnt f eat ures cited. *H , note below.
6.(1): Although no specific documented review for this purpose han been recorded, ptocedures that involve taking a redundant de divinfon out of service do contain ateps to verify the opposite train is in service prior to beginning the maintenance activity.
7_. b Concerning battery "overchargo" referred to in thin question, this condition is not referred to, an such, in ANO-1 proceduren. Ilowever, a proceduro doen address the condition when the battery bank voltage in abovn the Technical Specificat ion limit and specif f en correcti e nilonn in accordeaco with other procedurcs.
7.c_.4 and 5: ANO-1 Technical Specifict, tion 4.6.2.3 staten, " Onco every eighteen months, a performance discharge test shall be conducted in accordance with the manufacturer's instructions, for the purpose of determining battery capacity." ANO-1 is preparing a change request to the Technient Specifications to incorporate the appropriato Standard Technient Specifications that will include the surveillance requirement identified in item 7.c.4. This change request is currently scheduled to be submitted by June 30, 1992.
7 o: This surveillance 19 performed ovory eighteen months as specified in ANO-1 Technien1 Specifications 3.7.1.D, 3.7.2 F, and 4.6.2.3.
Additionally, ANO battery surveillanco proceduren staten, "If the enpacity eniculated is less than 907., then notify Maintenanco Engincoring for evaluation."
- Not e : For quest ions involving support ing type information (question numbers 5 and 9) in%t end of developing and supply tt;g t he informction in responsn to this letter, you may commit to further evalunte the need for such provisions during the per f ormance of your trulividuni plant examination for severo accidont vulnernbillt les (lpE). If you select thin option, you are required to:
(1) So state in response to these questions, and (2) Cornm i t to explicitly addrnss questfons 5 nnd 9 in your lpE submittal per the guidelines outlined in NUKEG-1335 (Sect ion 2.1.6. Subitem 7). "Individuni plant Examinntion: Submittal Guidance".
i
, ATTAtllMENT 2 ,
- 1. -Unit ANO-2
- 2. a. The number of independent indundalit divisions of Class 10 or safoty-related de power for this plant is TWO. (includo any separato Class IE or safety-related de, such as any de dedicrted to the dicsol generators.)
- b. The number of funct ional saf ety-t einted divisions of de power necessnry to attain safo shutdown f or t his unit is ONE.
- 1. Does the control room at this unit have the following separat e, independently annuncleted alarrns amt indications for each division of de power?
- h. alarma
- 1. Battery disconnect or circuit breaker open? YES
- 2. Battery charger disconnect or ciscuit breaker open (both input ac and output de)? YES (Hultipoint Alarm)
- 3. de system ground? YES
- 4. de bus undervoltage? YES
- 5. de bus overvoltago? YES (Multipoint Alarm)
- 6. Battery charger failure? YES (Hultipoint Alarm)
- 7. Battery discharge? NO
- b. Indications
- 1. Battery float charge current? NO
- 2. Battery circuit output current? NO
- 3. Battery discharge? NO
- 4. - lius valtngn? YES (on SPDS)
- c. Does the unit have written proceduren for responso to thn abovo alarms and indications? YES
- 4. Does this unit havn indiention of bypassed and inoperabln status of
. circuit bronkers or other devices that can be used to disconnnet thn battery and bat. tory charger from its de bus and the battery charger from its ac power sourco during maintenance or testing? YES (ace number 4 under question 5)
.- , ., r ._
,5. If the answer to any part of quest ion 3 or 4 is no, then provide in-i formation jurtiiving the exist ing design features of the f acility's saf et y-reint ed dc syst ems. *See note holow.
3.a.7 Although battery discharge is not specifically annunciated in the control room, the operators have alarms which will indicate when the battery is discharging.
If the battery in discharging due to loss of AC power or battery charger (silure, the control room operators will recolve alarms that the battery cnarger is disconnected or the circuit breaker is open and that the charger has failed.
If the bsttery begins to diechargo becaus,c the load exceeds t he current supplying capacity of the bat tery charger, then the de bus must be at 116 Vdc or below since this in the terminal voltage of the battery. This condition is annunciated in the control room.
3.b.1: Control room float current indication is not necessary sinco the parameters monitored in the wockly surveillances required by Technical Specification 3/4.8.2.3 are considered to be adequate.
3.b.2: The indiention of the bat tory circuit output current is provided by a local ammetet. Local indication is sufficient with the conttol room alarms described previously and the surveillance procedure required for these battery banks.
hb.3: Although there is no specific battery dischargo indication in the control room, an alarm which alerts the operators when the battery bank is beginning to dischargo la provided as described in responso to question 3.a.7. The operators can then monitor the local ammeters and voltmotors and the bus voltage indication in the control room as necessary.
_4_ : The exception to this responso in that the battery charger feedor breaker to the de bus is not alarmed. An alarm is provided in the control room if the battery safety disconnect switch is open or if the battery fuso is blown or removed and an additional alarm is provided in the control room if the ac battery charger input or de output breaker is open. Even though there is not an alarm in the control room in the ovent the de bus feeder breaker from the charger is open or tripped, this conditim will be detected during periodic surveillance of the battery / charger system or if the bus voltago drops to the low voltage alarm setpoint of 110 Vdc.
- 6. (1) linve you conduct ed a review of maint enance and testing act ivit ies to minimize the potential for human error causing more than onn de division to be unavailnble? NO and (2) do plant procedures prohibit maint enance or testing on redundant de divisions at the same time? YES If the incilit y Technient Spect ricationn have provisions equivalent to those found in the Westinghouse and Combustion Engineciing Standard Technical Specification for maintennnee and surveillance, then question 7 may bn skipped and a statement to that effect may be inserted here.
NOT APPh1 CABLE
Arn anintenance, sur veilletico nin1 t est procedures regarding sintion 7.
bat teries coiniucted rout inety at this plant? Specifically:
- n. At least once per 7 days, ora the following vertiled to be within acceptable limits:
- 1. Pilot cell electrolyte leve l Tr YES
- 2. Specific gravity or ohniging current? YES
- 3. Float voltage? YES I
4 Total bus voltage on float charge? YES
- 5. Physical condition of all cells? YES
- b. At lenst once per '.72 days, or within 7 days af t er n bnt t er y dischargo, overcharge, or if the pilot cell rendingn are ou t s ide the 7-day surveillance requirements, are the following verified to be within acceptablo limits:
- 1. Electrolyte level of each cell? YES
- 2. The averagn specifft gravity of all cells? YES
- 3. The specific gravity of each cell? YES
- 4. The nyerngo electrolyte temperature of a representntIvo number of colis? YES
- 5. The ilont voltngn of ench cell? YES 6 Visually inspect or mensure resistance of terminals and connectors (including the connectors at the dc bus)? NO
- c. At least overy 18 months, nrn the following verified:
- 1. how resist ance of each connection (by t est )? YES
- 2. Physical condition of the battery? YES
- 3. Battery charger capability to deliver its design duty cycle to the de bus? YES
- 4. Thn capability of the bat tery to deliver its design duty cycle to the de bus? YES
- 5. Each individual cell voltago is within acceptable limits during thn servi,co test? N0
- d. At least every 60 month,i, is capacity of ench bat t ery verified by performance of a dischargo test? YES
- e. At 1 cast annutolly, is the battery capacity verified by per-formance dischargo test, if thn battery shows signs of dn-gradation or has renched 85%, of thn expected service life?
NO
- 8. Doon this pinut have opnratfunn! featutes such that following loss
. of one safety-related de power supply or bus t J i, a. Capability is mai 'nined for ensuring cont inued and adequat o redctor cooling? u.S
- b. Ronctor coolant systern int egrit y and isolat ion capnhilit y ,
are maintained? YES '
- c. Operating procedures, instrumentation (including indientons and gununciators), and ront rol f unct ions nie adequat e t o initiate systems as required to maintain adequnto core cooling? YES
- 9. If the answer to nay part of quest ton 6. 7 or 8 is no, then provide your basis for not per forming the maintennnco, surveillance nint test procedures described and/or the bnses for not including the operat ional features cited. *Sco not o below. '
6d}): Although no specific documented review for this purpose has bocn ,
recorded, procedures that involve taking a redundant de division out of '
service do contain steps to verify the opposite t rain is in service prior to beginning thu maintenance activity.
7.b.6 Resistance measurements on inter-cell and inter-tier connections are taken as well as the connections at the batteries which lend to the busca, llowever, resistance measuremn'.ts or visual inspections are not performed on the connectors at the buses themac1ves. The buscs are located in a separate room from the battories and are not subject to the same corrosive environment as that potentially created in the battery rooms.
7.c.5: The total battery bank voltago is surveyed just prior to cach duty cycle change.
Les This surveillanco is performed every eighteen months as speciflod in '
ANO-2 Technical Specification 4.8.2.3.f.
- Noint 1"or quest ions involving supporting type information (question numbers 5 aad 9) instead of devnloping niul supplying the information in '
response to this letter, you may commit to furt.hnr evalunto the need for such provisions during the performance of your individual plant examinintion- for severe accident vulnernbilit les (lpE), If you select this option, you are required to:
(1) So stato in response to these questions, and (2) Commit to explicit ly address questions 5 and 9 in your IPE submit tal por the guidelines out lined in NUREG-1335 (Section 2.1.6. Subit em 7), " Individual Pinnt Examination: Submittal Guidance".
.. - _ _