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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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4 h06hJl&Y REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL -31' 368 i
REC: STOLZ J F ORG: WILLIAMS D H DOCDATE: 06/15/78 I NRC AR PWR & LIGHT DATE RCVD: 06/23/78 l DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED 1
SUBJECT:
LTR 3 ENCL 40 1 FURNISHING COMMITMENTS MADE BY APPLICANT DURING MEETING. WITH NRC STAFF ON 05/24/78 RE FIRE PROTECTION ISSUES OF SUBJECT FACILITY.. W/ATT.
I l
PLANT NAME: ARKANSAS - UNIT 1 REVIEWER INITI AL: XJM l ARKANSAS 1 - UNIT 2 DISTRIBUTER INITIAL: 4 ococoo*********** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
FIRE PROTECTION (PRIOR TO ISSUANCE OF OL). spec.
(DISTRIBUTION CODE B002) 7dp t /EM gz HMcred */f#
FOR ACTION: BR CHIEF ORB #4 BC**W/ PROJ "OR VIS5INGwxW/ ENCL L M'LY INTERNAL: RE E*
- W/ ENC' _ NRC PDR**W/ ENCL D**LTR ONLY I & E**W/3 Eb1CL DIRECTOR DPM**LTR ONLY DE YOUNG **LTR ONLY VASSALLO**LTR ONLY DIRECTOR DSS **W/ ENCL AD FOR PLANT SYSTEMS **W/ ENCL AUXILIARY SYS BR**W/2 ENCL ,
I & C SYSTEMS BR**LTR ONLY AD FOR QA & O**LTR ONLY !
QAB**W/ ENCL R. MURANAKA**LTR ONLY HANAUER**W/ ENCL EXTERNAL: LPDR'S RUSSELLVILLE, AR**W/ ENCL n TIC **W/ ENCL NSIC**W/ ENCL THis DOCUMENT CONTAgg3 POWER SYS BR**W/ ENCL 3 PLANT SYSTEMS BR**W/2 ENCL
- POOR QUAUTY PAGES AD FOR SYS & PROJ**LTR ONLY k DIRECTOR DOR **LTR ONLY OPERATOR LIC BR**W/ ENCL ACRS CAT B**W/16 ENCL YbC '
p 40 DISTRIBUTION: LTt . % ENCL 36 CONTROL NBR M &i N SIZE: 10P+1P cooocc***************************** THE END **********************************
8004240 M 2 p
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ARKANSAS POWER & LIGHT COMPANY POST OFRCE BOX 551 03DOCKETFIE ,,
UTTLE ROCK. ARKANSAS 72203 (501) 371-4000 f, ,
June 15, 1978 i-l w'
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2-068-8 >
Director of Nuclear Reactor Regulation ATTN: Mr. J. F. Stolz, Chief Light Water Reactors Branch #1 Mr. Robert W. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Arkansas Power & Light Company Arkansas Nuclear One-Units 1 & 2 Docket No. 50-313 & 50-368 License No. DPR-51 Fire Protection (File: 1050, 2040, 2-1050, 2-2040)
Gentlemen:
The following the Staff, on Mayis24,to 1978.
document comitments made during our meeting, with itemsapplicable.
where and the r umber in parenthasis refers to the previous staff ,
Item 1 -
Power Supplies for Fire Detection and Actuation Circuits Response (ANO-1)
Although we do not agree with the necessity of the requested modifications f all Fire detectors will be powered from an emergenc ,
of power available curing a loss of offsite power).y power source (a source be completed by October 1,1978. This modification will We now consider this item resolved.
Item 2 -
Smoke detectors in the ANO-1 Emergency Feedwater Pump Room
_ Response (ANO-1)
Although smoke detector we do not agree with the necessity of the requested modification, EFW pump room.(s), which alann in the control room will be provided in the [A y consider this item resolved,This modification wil' be completed by October We 1,1978.
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, t Mr. J. F. Stolz, Chief Mr. Robert W. Reid, Chief June 15, 1978 1-068-3 2-068-8 Item 3 (PF.21)
Smoke detectors which alarm.in the Control Room should be located in all safety-related areas containing combustibles.
Response (ANO-l&2)
This item will be the subject of subsequent correspondence based on the June 9,1978, meeting.
Item 4a Provide barriers betwaen redundant conduits in Fire Zone 149-E.
Response (ANO-1)
We do not believe this is a justifiable position as there are no com-bustibles in this zone. However, in order to expedite licensing, we will provide a barrier between the two redundant conduits. This modification will be completed by the end of the next refueling outage. We consider this item resolved.
Item 4b - Deleted Item 4c - Fire Barriers in Zone 98-J Response (ANO-1) i We are still evaluating the best engineering modification for this zone.
We will either install a deluge system with directional spray actuated by heat and smoke detection and provide cable coating where redundancies are in proximity or coat all trays and provide smoke detection with alarms in the Control Room, and a wet pipe sprinkler system. We understand eit5er of these modifications is acceptable to the staff. The modifica-tion will be completed by the end of the next refueling outage. We consider this item resolved.
Item 4d - Fire Barriers in Zone 2091-BB Response (ANO-2)_
A marinite board will be added to cover tray EB155 and those portions of EB154 where redundancies are in proximity. This modification will be complete by June 19, 1978. We consider this item resolved.
Item 4e - Fire Barriers in Zone 2111-T l l
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t Mr J. F. Stolz, Chief Mr. Robert W. Reid, Chief June 15, 1978 1-068-3 2-068-8
Response
The two (2) redundant circuits of concern are in EBil92 and EB236 with some black trays as combustible bridges. A marinite barrier will be installed between the two circuits and the black trays where in proximity or the black trays will be coated where in proximity to the redundant circuits.
This modification will be completed by June 19, 1978. We consider this item resolved.
Item 4f - Fire Barriers in Zone 2109-U Response (ANO-2)
Same as response to Item 4c Item 40 - Fire Barriers in Zone 2084-DD Response (ANO-2)
Since there are no combustibles in this zone and the circuits in question are in conduit, we do not believe the requested modification is justifi-abl e. However, in an effort to expedite licensing, we will coat one of the conduits where they are in proximity. Due to the physical location of the conduits, it is impossible to provide a barrier. This modification will be complete by June 19, 1978. We consider this item resolved.
Item Sa - Manual Hose Reels in Zone 2223KK Response (ANO-2)
We understand the stuff has taken a further look at the separation of circuitry in this zone and determined that a hose reel is not required in this zone. We consider this item resolved.
Item Sb - Manual Hose Reels in Zone 2055JJ Response (ANO-2)
We have further analyzed this zone and have detennined that loss of all the safety related ' circuitry in this zone combined with a single failure out-side the zone will not jeopardize our ability to safely shutdown the plant.
We understand that the staff will accept this zone without the addition of a manual hose. Therefore, no hose reels will be added. We consider this item resolved.
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Mr. J. F. Stolz, Chief Mr. Robert W. Reid, Chief June 15, 1978 1-068-3 2-068-8 Item Sc - Manual Hose Reel in Zone 2084DD Response (ANO-2)
We will replace the 75' hose on HR2-28 with a 100' hose. This is adequate hose to reach zone 2084DD. This modification will be completed by October 1,1978. We consider this item resolved.
Item 5d - Manual Hose Reels on El. 317' ANO-1 & ANO-2 Response (ANO-1 & ANO-2)
Our Fire Hazards Analysis has shown conclusively that a fire on this elevation would not jeopardize our ability to safely shutdown the plant as none of the equipment on these elevations is necessary for safe shutdown. We therefore do not believe the requested modi-fication is justifiable as a modification to improve the margin of safety to the health and safety of the public. However, as an effort to expedite licensing, we will provide manual hose capability for these elevations. The modification will be complete by the end of the next refueling outage of each unit. We consider this item resolved.
Item 6 - Protection Against loss of Service Water - ANO-1 Response (ANO-1)
As stated in our response to verbal question 2 transmitted to you April 26, 1978, there are circuits associated with two pumps routed in common conduits and trays. However, these circuits are control circuits. The circuits in question are the red control to the red pump and the red control of the swing pump. Destruction of one of the conduits / tray could only disable one pump as green control would be available to the swing pump. As illustrated on the attached drawings, there are no situations where power cables from two pumps are routed in the same conduit / tray and the destruction of one of those conduits / trays would only possibly disable one pump. We believe this is adequate justification for deletion of the position and based on the staff response to this, we consider this item resolved.
Item 7a (1.0j) - Fire Protection Quality Assurance Program Response (ANO-1 & 2)
The guidelines of Attachment No. 6 to your " Nuclear Plant Fire Protection Function Responsibilities, Administrative Controls and Quality Assurance" dated June 20, 1977, will be met by application of the appropriate sections of our QA Topical with the following exceptions:
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. l Mr. J. F. Stolz, Chief Mr. Robert W. Reid, Chief June 15, 197.8 1-068-3 2-068-8 Item 3.0 - Control of Purchased Material, Equipment and Services Vendor qualification criteria listed in APL-TOP-1 A will not be followed for qualification of vendor supplied parts, components, or services.
Upon implementaion of the Fire Protection Plan, all fire protection equipment procured, will be UL or FM listed, where applicable. This will be accomplished by requiring such on the purchase order.
Item 4.0 - Inspections Response (AN0-1 & ANO-2)
This item will be complied with by applying applicable portions of the QA Topical, Fire Protection Plan, and Technical Specifications.
Item 5.0 - Test and Test Control This item will be complied with by applying applicable portions of the QA Topical, Fire Protection Plan, and Technical Specifications.
Item 10.0 - Audits ,
Response (ANO-1 & ANO-2)
This section will be complied with by performing audits in accordance with applicable sections of the QA Topical except section d which will be complied with by application of our Technical Specifications.
Item 7e (2.0n) - Review of Work Request by the Fire Chief Response (ANO-l & AN0-2)
All job orders will be reviewed for fire protection impact by the Plant Fire Chief or the Shift Supervisor. We understand this is acceptable to the Staff and consider this item resolved. This commitment will be reflected in an amendment to the Fire Protection Plan.
Item 8a - Testing of Cable Penetration Fire Stops Response (ANO-1)
We will perform fire tests or supply adequate information of tests on similar fire stops to justify the adequacy of the cable penetration fire stops.
Details and a schedule for completion of testing (if required), will be submitted by October 1,1978. We understand that the staff considers this connitment sufficient to resolve this issue.
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Mr. J. F. Stolz, Chief Mr. Robert W. Reid, Chief June 15, 1978 1-068-3 2-068-8 Item 8b - Safety Circuits in Non-safety Related Raceways Response (ANO-1)
As discussed in our meeting with the staff on May 24, 1978, we must per- .
form a considerable amount of analysis to detennine if tnis situation exists at our facility. We will provide you with a schedule for com-pletion of the analysis by July 15, 1978.
Item 8c - Portable Air Handling Equipment Response (ANO-1 & ANO-2)
We will provide three (3) 5,000 CFM (minimum) smoke exhaust units available for each unit. Flexible duct will also be provided to aid in the removal of smoke. This equipment will be provided by December 1,1978. Ne consider this item resolved.
Item 8d - Supervision of valves of the Fire Water System
. Response (ANO-1 & ANO-2)
We understand that, at least for now, our technical specifications are adequate to resolve this issue.
Item 8e - Automatic Operation of Sprinkler Systems Response (ANO-1)
We understand the staff is concerned with the manual sprinkler systems in zone 149E and both ANO-1 Diesel Generator Rooms. We will modify these systems to automatic actuation by the end of the next refueling outage.
We consider this~ item ree;lved.
Item 8f - Water Spray Protection for Motor Control Centers
Response
Our Fire Hazards Analysis has shown that the loss of'either or both of the two MCC's (2851 and 2861) would not affect the ability to safely shutdown the plant. It is our opinion that providing the requested modification will not significantly increase the margin of safety to the health and safety of the public. However, as an effort to expedite licensing, we will provide a shield to protect the two MCC's from water spray. This modi-fication will be made by September 1, 1978. We consider this item resolved.
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Mr. J. F. Stolz, Chief Mr. Robert W. Reid, Chief June 15, 1978 1-068-3 2-068-8 Item 89 - Details of RCP C1 Collection System Response' (ANO-1 & ANO-2j_
We will provide the requested sketches and/or photogaprhs of the RCP oil collection system by September 1,1978, for ANO-2 and following the next extended outage, but no later than after the next refueling outage for ANO-1.
Item 8h - Smoke Detectors in Areas of Combustibles Response (ANO-1 & ANO-2)
This item will be the subject of subsequent correspondence based on the June 9, 1978, meeting.
Item 81 - Smoke Detectors for Actuation of Halon System Response (ANO-1)
We will modify the Halon System in the false ceiling and floor of the ANO-1 control room to be activated by smoke detectors. This modification will be completed by the end of the next refueling outage. We consider this item resolved.
Item 8j - Replace non-UL/FM Listed Detertors Respons.: (AND-1)
We are identifying the location of all non-UL/FM listed detectors and evaluating their necessity. Those identified that are detennined necessary by your requirements and/or our convitments will be replaced (if possible) by UL/FM listed equipment. This analysis and modification (if necessary) will be completed by September 1, 1978. We consider this commitment adequate to resolve this issue.
I' tem 8k (PF.14) - Hose Reel in Containment Response (ANO-1 & ANO-2)
Manual hose capability will be provided in the Reactor Building (ANO-1) and I Containment Building (ANO-2) by the end of the next respective refueling outage. We consider this item resolved.
Item 9.la - Control Room Cabinet with Redundant Safe Shutdown Equipment
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Mr. J. F. Stolz, Chief .
Mr. Robert W. Reid, Chief 1-068-3 Juna 15, 1978 2-068-8
_ Response (ANO-1 & ANO-2)
The only 2C33. Control Room cabinet with redundant safe snutdown circuitry is cabling except for a common open area ,at the We topwillof the cabin provide detection consistent with our comitment in our April 24, 1978, letter. We consider this item resolved.
Item 9.lb Combined With 9.la - Resolved floor and ceiling. Item 9.lc - Redundant safe shutdown circuitry in ANO-1 C Rerponse ( AN0-1)
There is no redundant safe shutdown circuitry in the false ceiling. The false floor area contains all control circuits. Since all safety circuits are in conduit, we propose to provide a cable coating on all open trays.
We believe the number of barriers necessary to achieve complete separation of conduits and trays would render the Halon System useless. Coating each tray along with the modification to llalon System detection should provide this item.more than adequate protection and should be sufficient to resolve Item 9.2a - ANO-1 Cable Spreading Room Response (ANO-1) i We will either provide a deluge system similar to item 4c cable coating for each open cable tray.
completed item resolved.
by the end of the next refueling outage.This modification will be We consider this Item 9.2b and 9.2c - ANO-2 Cable Spreading Room .
_ Response 2
The total ceiling area 0.23 provide of this zone is 2484 ft . Sprinklers located at the gpm/ft2 sprinklers provide 0.21 gpm/ftof2 floor areaofand or a '.otal 0.44the inteqdiate level gpm/ft This system uns isdesigned andtoinstalled of floor area.
1977 and therefore not designed that code.before the issuance of NFPA 35, to evaluate this system with respect to the new code.It is not practical put s.ignificantly less water into the zone than our pre
Mr. J. F. Stolz, Chief Mr. Robert W. Reid, Chief -9 '
June 15, 1978 1-068-3 2-068-8 Although all trays do not receive direct spray, the trays are no more than 18 to 20% full and extremely clean. Water should pour through upper trays and impinge on lower trays very effectively.
.We trust this infonnation is sufficient to resolve your concern in this area.
In addition, we will provide a flame retardant barrier and/or cable coating where redundant safe shutdown circuitry are in proximity.
This modification will be provided by the end of the first refueling outage. We consider this item resolved.
Item 9.3 - Barriert in ANO-2 Switchgear Room Response (ANO-2)
We will provide a fire retardant barrier or coating where two chan::els of circuitry are. in proximity. This modification will be completed by the end of the first refueling outage. We consider this item resolved.
Item 9.4a - Emergency Lights in the Control Room Response (ANO-1 & ANO-2 Fixed emergency lights will be provided in the Control Rooms by December 1,1978. We consider this item resolved.
Item 9.4b - Portable Hand Held Lights Response (ANO-1 & ANO-2)
Ten (10) hand held sealed beam lanterns will be provided for fire fighting use by July 1,1978. We consider this item resolved.
The implementation schedules presented here are realistic as of this date. However, for inodifications to be performed during the next ANO-1 i refueling outage, ali engineering and review must be completed by 1 November 1, 1978. Shoeld NRC or required insurance review delay completion of design change package and impcat this date, the implementation schedule could also be impacted. Also, should we have procurement problems, ,
these implementation dates could be impacted. We anticipate you will be considerate of these problems should they occur. Should the Staff 1
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l Mr. J. F. Stolz, Chief Mr. Robert W. Reid, Chief June 15, 1978 1-068-3 2-068-8 Response (ANO-1 & ANO-2) (Cont')
. review our Fire Hazard Analysis to its fullest extent and fully consider the information we believe it contains, the need for many of the above modifications will be negated. We reserve the right to reconsider these commitments with the staff should that review occur.
Very truly yours, 1/ '
Daniel H. Williams Manager, l.icensing DHW/JTE/ew 4
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