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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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n e t. p i n a aurto annansas ARK ANS AS POWER & l.:GHT COMPANY 9TH & LCulSIAN A STA..TS L,TTL. ACCK A AKANS AS 72203.(5013372-4311 November 6, 1970 Mr. Paul Collins, Chief Operator Licensing Branch Division of Reactor Licensing United States Atcmic Energ/ Co=tission 7920 Ilorfolk Avenue Bethesda, Maryland 21811 SU3 JECT : ARKANSAS ITUCLEAR OIIE PERSOIIIIEL (FILE : 0400)
Dear Mr. Collins :
Enclosed is a copy of the Medical Examination Report for Mr. Robert M.
Si= tons, who is a candidate for a licensed operator position on Arkansas Huclear One.
I would appreciate your doctor's review of this report and whatever cccments he or you might have regarding this tan's eligibility for licensing.
/
Ver'/ truly yours,
/ >
- g/L .-_/
William Cavanaugh Assistant Superintendent Arkansas Nuclear One WC:=c Enclosure I 1
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to cy a ss Eureau of Budget No. J8.R084 ATOi!!C ENERGY CO!.t.'.!!SSION CERTIFICATE OF MEDICAL HISTORY Facility Oper: tor's or Senior Operator's License u'cr:ticast Applicant must complete all items en page 1. Typewrite er print in ink. Physician must comple:e ell items en page 2.
1, Lat Name First Name .'.11ddle Name 2. Date -f Birth Simmons Robert Melvin July 30,1937
- 3. Homa Address
- 4. Sex 50 Collins Road, Jacksonville, Ark. 72076 male Have you ever had or do you now have any of the following? Give details of any condition answered in the affirmative under item 38.
Yes No Y'S NO
- 5. Eh umatic fever I i x ! !6. Bene, joint, or cther deformity ! X l
- 6. FPcusnt or severe headaches l l y 117. Painful or " trick" shoulder
'T. Dizziness or fsjnting spells x l l x l 18. Painful cr " trick" elbow X
- 8. Eye trouble
- 9. Diacetes l lx i 19. Paralysis x
I x l 20. Epilepsy or fits X
- 10. Tuberculosis l l 21. Depression er excessive worry v
- 11. Ch onic shcrtness of breath x
Ix ! 22. Loss of memcry er amnesia v
- 12. Pain er pressure in chest or " heart attack" l x l 23. Nervous condition which could impair
- 13. H!;h blood pressure judgment or reliability X l l x i
- 14. Low bloed pressure I l 24. Drug or narcetic habit y
L5JNtle ulter i x
y ,25. Excessive drinking habit X Complet2 each of the following. Give details of every affirmative answer under item 37.
.S. Has your work ever been limited or restricted for medical reasons
- 27. Hava you ever been denied or rated up for life insurance for medical reasons?
x X
ES. !!:va you ever been under observation or received care er treatment for any mental cr nervcus condition as a p:tient in a horpital, sanitoilum, clinic, or other facility, ur from a physician, clinical psychologist, etc.? X
- 29. nc.70us Hrte you ever been disorder reasons rejected 7 for or discharged from employment er military service for physical, mental. or X
- 30. comp;nsation H:xe you everfor received existingisdisability?
there pending, have you applied for, or do you intend to apply for pension er x
- 31. Havo you ever seriously considered committing suicide
- 32. Itava you ever been convicted of any violation of Federal law. State law. county or municipal law, regulations cr ordinance?
which a fine ofDo
$25notor include less was anything imposed. that happened before your 16th birthday. Do not include violations for X
- 33. H ve you ever had any major illness er injury other than those already noted?
- 34. How many jobs have you had in the laat 3 years' l X
- 35. What is the length of time in your present employment? l gom 3; ,,, g ), 19 ,ay ,,
35, Giv] a brief statement of your present health in your own words: # ~
~
Good.
37.affectDitalls of any items 5 through 33 answered in the affirmative. In addition, if y0cr m your ability to function as a facility uperator. Use additional sheet if more space is needed. i Kidne> Stones that caused my life insurance rate to go up cbove normal.
l
- 38. I certify that the foregoing informatica supplied by me is true to the best of my knowledge, and authcrize the Atomic En mission to usc any of the information in this certificate in tne exercise of its authcrity over the licensing o' cperatcrs.
10-21-70 (Dct:)
Ark. Nuclear One h , 6;T7 7 / %v
( F acilit y)
(signatue of applicartt)
S6GN YOUR N WE IN INM AS IT APPEARS ON YOUR APPI.ICATION FOP. OPERATOlt'S Oft SENIOR OPERATOR 1.
m ,
- r. - ace 2e6 ' .
o-m MEDICAL EXAMlliATION ~
39, Doctora it to ocaintit! thIt seah cf thm letms on this p293 bs compi:esJ. Stgn ths Certifiesta cnJ msil to tha Dir:cter, CJvisten of Reactor Licensing, United States Atomic Energy Conimission, Washington, D.C. 20545 f ar is<ctor opsrit:r liesass cop *Iecnts or ee the Director, Division of Materials t.icensing, United States Atomic Energy Commission, Washington, D.C. 20545 t'or opp!!.
. cents.for non-reactor operator licenses.
Use additional sheet if more .po:e is needed,
- 40. Physicions's Summary and elaboratice of the medical,histery on fronkof repc7t.
.JA 4mt6% em
[yPctient states that kidney 4 stones, acid and that he is on medication for high blood uric
< . (gout? ? ?). .
L Physical Examination. Give details of abnor=al findings under item 21 below.
10-2!-70 2. Height 5'9" 3. weight 222
- 1. Date of examinaion
- 4. Blood pressura 170/90 5. Pulse -l00
- 6. Distant visual aculty uncorrected right 20/25 left 20/20 method used Snellen
I. Distant visual acuity corrected r:ght left (data required cnly if ecrrective lenges are normally werm
- 8. Naat visual acuity uncorrected right JJ 1 eft Il method used Joeger
'9. Near visual aculty corrected right left (data required cnly if corrective lanses are no = ally worm
- 10. Color vision normal method used Snellen
- 11. Gross visual fields normal
- 12. Hearing right normal left normal method used spoken word
- 13. Eyes. generr.1 normal 14 FUDil3 normcl
- 15. Ophthalm: scopic ncrmal
- 16. Ears general m aj 17. Drums normal
- 19. Vascular system normol
- 18. Heart g
- m. Date and ev21ustion of chest x *ay taxen within the past year. 10- 21-/ 0 normal
- 21. Details and evaluation of any item I through 20. above, reported abacr=al and su==ary evaluation of over-all condition.
Moderatcly cbese with some elevation systolic BP.
- 22. The foregoing er.2-ina !cn (tMM7does not) reveal any mental or physical disability which might cause impaired judgment er meter coordination. no 1 understand that any of the information in this examination may bafshd by the' Atomic Energy Commission in the exercise of its authority over the licensing of operators. ,/
10-21-70 s J- M / 4 (sicnature
- v cw Mt of esam:nang paysses'en)
, (Date)
Howard Schwander, M.D.
Typed or printed name of eaa tr. ins pnyttetan
' DOCTOR: IT IS REQUIRED ll15 Bishop THAT EVERY ITEM ON THIS Little Rock, Ark. 72202
^"""
PAGE DE COMPLETED EX-CEPT THOSE MARXED WITH
- Arkanses WHEN HOT APPLICABLE. e,,,,, . , m ,,,,,
- 2.
o p ,. .
Date: January 18, 1971 Chief, Health Protection Branch
. Division of Operational Safety CERTIFICATE OF MEDICAL EXAMINATION, DOCKET No. 55-Attached for your review is the Certificate of Medical Examination for Harry. R. Walters
@ Initial Medical Report P
C / rior Medical History Available that.was submitted as part of an application for an operator's license for the Arkansas Nuclear One Plant (W/0. Appl. ) .
It is requested that the Division of Operational Safety review this medical report and indicate below its conclusions as to the applicant's physical condition and general health. Please return the report to this office.
PRIOR MEDICAL HISTORY .
REPORT-In accordance with the above request, a review has been completed to determine
'if the physical condition and general health of the applicant are not such as to be expected to cause operational errors which might endanger public health and safety. 'The following recommendation is submitted:
M.D. The physical condition and general health Date DOS are satisfactory for licensing.
/. 3 fe< 7/ NN M.D.
The physical condition and general health Date DOS are satisfactory for licensing with the condition (s) thatc3/a t.3 m tvr m edCM M.D. The physical condition and general health.
Date DOS are not satisfactory for licensing. The adverse condition (s) is M.D. A determination cannot be made until the Date DOS following additional information is sub-mitted:
..n .-
i> I Ftrm spprwed.
, . .' 'F orm A r c 396 ggg g y Lucase er Eudgst Ns. 38.R084 to cr3 H ATOMIC ENEnGY COMMISSION CERTIFICATE OF MEDICAL HISTORY Facility Operator's or Senior Operator's Lfcense Inctructions! A;pl!ctr.t must cornplete aj! iten:s on page 1. Trenite or print in tri. Physician must complcte a!! items on pace 2.
- 1. Last Name First Na:ne Mic fle Name 2. Date of Birth WaL 6 CM Ndvrv #
Rel v Sept. 30> l9/9 3.' Home Acidress #
- 4. Sex for McCles/dy & bd Sorw9s , h/Cwm ~
7/9w A7 ale Have you ever had or do you now have any of the following) 'Give'detalis of'any condition answered in the affirmative under item 33.
Yes No Yes No
? $. Rheumatic fever i p- l 10. Bone. Jrir.t. er cther defermity } l p-
- 6. Frequent or severe headaches P 17. Paintt:1 or " trick" shoulder l l k"
- 7. D!zziness er fain!!rg spells V 18. Painful or " trick" eit ow i P
- 8. Eye trouble y" 19. Paralysis k'
- 9. Diabetes P 23. E;tlepsy or fits " i
- 10. Tuberculosis h* 21. Deeression or excessive worry M i
- 11. Ch*on!c shertness of breath l P 22. Loss of memory or r.=nesta k- l
- 12. Pain or pressure in chest er " hec.rt sttack" I k 23. Nervous ccndition which could impair
- 13. High blood pressure k' i
- "'" 0# 7 "
- 14. Low blood cressure k- l 24. Drug or narcotic habit "
JJ. Perhu!cer P i 25. Excessive drinkin: habit V l Cortclete each of the following. Give detatis of every affirmt.tive answer under item 37 Yes No
- 26. Has your werk ever been !!mited or restricted for medical reasons' u-
- 27. Have you ever been denied er rated uo for life insurance far medical reacc,ns' 4--
- 28. Have you ever been under observotion er received care er treatment fer any mental or nervous cendition as a patient in a hospita . sanitorium. c11 ic. cr other facility, or frem a physician clinical psychologist. etc.? k.-
- 29. Have vnu ever haan refce**d rnr nr r4f erhae ad fenra ampf ay~ n* ar e i!!t. - e ~!n f: ;M ci-4 -, ant:'. :- I nervous dis:rder reasons? p.
l
- 30. Have you ever received. is there pending. have you applied for. or do you intend to apply for pension er compensatien for existing rubtlity? p
- 31. Have you ever se-iously considered ccemittine suicide' i r.- 1
- 32. Have you ever been convicted of e.ny violat!cn of Fedcral law. State law. county er municip*l law. regulations or ordinsrce? Do not include ant.hin; that ha;;ened before your 16th birthday. Do not include violations for which a fine of 325 or less w:s im;caed. V
- 33. Have you ever had e.ny rnafor illness er injury other than those already ncted? v-l {
- 34. How meny fots have you had in the last 3 years) ()pe
- 35. What is the length cf time in your ; resent em;!ayment? pjge &eg wm
- 36. Give a trict statement of your present health in your cwn words: Gccg /
1
- 37. Details of it.y items 5 throu;h 33 uswered in the afttimative. In addition. if yn:r medic 22 h;stc.ty includes any matter relating to physical. Cental, er ne vcus coni!!1on. please describe tr.e concitten and set fr.h nur ex;! ant. tion cf why this matter w ;uld n:t affect your ability to function as a facility ;;erator. Use aaditional sneet if more soace is needed. .
_ SYPhd $&
- 38. I certify that the f0regt'ng informatice. supplied t;y me is true to the )est cf my+n.
.. . w knnledge'[end .
Ab/7E hhkir keler Gye Mny 7(he]lffb (catel (rn 's:y)
/ fisisut<eer.ptine.:)
S:GN YOUR NA'.iE IN INK AS IT APPFAi;.S ON 10 Lit .WPLICATION FOP. OPEftATOtt*S OR .GNIOP. OPERATO.TS LICE 55U.
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- 39. Dsetti: le is assential that occh of the items on this paga he completed. Sign the Cortificate and mell to the Director, Division el rieoctor !.lcensing, United Statss Atomic Ir:ergy Commission, 7/ashington, D.C. 20545 for rea:ter oporeter IIconse applicants er is the .rettor, Civision of Motorio!s I.lcensing, United States Atomic Energy Commission, Wasn' ington, D.C. 20545 for appli.
cz6ts for non. reactor operator IIcenses.
40 Physicions's Summery and elaboration of the medical history on front of report. Use additional sheet if mors space is needed.
n'g L AL& l lO '
6 PAystei.' Examanct:on. Give details of abnormal fincings under item 21 below.
- 1. Date of examination ), ); y;} 2. Helght [ () k 3. Weight J 7)
- 4. 3!00d pressure' f.g a /pg 5. Pulse .f a
- 6. Distant visual acuity uncorrected right M co left 10 method used b ,,,/
'7. L!stant visual eculty correc*ed right A '? / left d data died only if ccrrective lenses de normally worm
- 8. Near visual acuity uncorrected gjg g Jg ' j m y used [g, j
'9. Ner.t visucl acuity corrected right 7, left .J~, (dal rewired on!y if ccrrec:f y lense re ne nally worn)
- 10. Color vision mn, pyg ,, _ i ,, /, , , teethod used ),, g/g,, /
- 11. Gr:ss visual fields ,rf'), ,m j -
.12. Hearing ,
right )4 % k left )t.r%. method uyed L-/.'J c - 4. 6
- 13. 1'ive,gaueiai , h% j .
- 15. Ophthalmoscopic
, 14., F uad a )thd / -
kt_ A a . C A . M * ,._ 3 __ D *
- 16. Ears. general
- 13. Iturt Yewd__
)g, ,,, f)
- 17. Drums _hhdn
- 13. yascular system }4m.~d
- 20. Date and evduation of chest x ray taken within the past yect.ff/.//) O km,j'1]
- 21. Details and evaluation of any item I through 20. above reportelab$ormal and summary evaluation of over.all condition.
) '"C Cv-- Y- 4W %- '
hY 0 4 %& -
s
- 22. The tcregoing exa tination (deesAlces not) reveal a.v mental or physical disability which might cause impaired judgment er motcr coordination.
I understand that Pny of the information in this examination tnay be used by the Atomic E.a.rgy Com ission in the exercise ofits e.uth rity ovcr the licensing of operato,rs.
(Date) ll-4-70 M ,"
-co m. 8 h (Sagetare or,4 ma,risnang phy sician)
Howard Schwender, M.D.
Typed or printed name of enamaning physician DOCTOR: IT 15 REQUIRED THAT EVEkY ITE.i.) ON THIS 1115 Bishop, Little Rock, Ark. 72202 .
^ dd" "
PAGE BE CO.uPLETED EX- ..
CEPT TH05E MARXED WITH * .
Arkansas l
' WHEN NOT APPLICASLE. ,,,,,,,,,,,,ii,,,,,,e 4
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- 2. ..,
Date: January 18, 1971 Chief, Health Protection Branch Division of Operational Safety 1
CERTIFICATE OF MEDICAL EXAMINATION, DOCKET No. SS-Att' ached for your review is the Certificate of Medical Examination for
$ Initial Medical Report Bobby A. Terwilliger D riorP Medical History Available thatlwas submitted as part of an application for an operator's license for the Arkansas Nuklear One Plant (W/0 Appl) .
It is requested that the Division of Operational Safety review this medical report and indicate below its conclusions as to the applicant's physical condition and general health. Please return the report to this office.
PRIOR MEDICAL HISTORY REPORT In accordance with the above request, a review has been completed to determine if the physical condition and general health of the applicant are not such as to be' expected to cause operational errors which might endanger public health and safety. -The following recommendation is submitted:
[- '
MM* M.D. The physical condition and general health Date' DOS are satisfactory for licensing.
M.D. - The physical condition and general health Date DOS are satisfactory for licensing with the condition (s) that M.D. The physical condition and general health Date DOS are not satisfactory for licensing. The adverse condition (s) is M.D. A determina ;on cannot be made until the Date. DOS following auditional information is sub-
, mitted:
F %
- - . Penen ACC Je6 * '
(949) ** sn us. u.nh.
le cr:1 ss ATO! tlc ENERGY CObl311SSloN CERTIFICATE OF MEDICAL HISTORY Facility Operator's or Senior Operator's License Instructions:
App!! cst! mun co=plete all !: cms on page 1. TnemT!!e cr print in ink. Physician must complete all .tb.s on pue 2.
- 1. Last NrJne First Name Middle Ncme 2. Date of Birth TidwElli& &'R '
dobby 171.1. n /O (Ipnil If/31
- 3. Home Address . 4. Sox
$0). ' C l- G Vs l A [sdLbi kadll thlld AR NMM svt Ah
, H;ve you ever had or do you r.ow have any of the (o!!owing' Give details if any condition answered in the affirmative under item 3S.
Yes No Yes No
?S. Rheumatte fever '
X l 16. Bone. M!.9t, or othe deftr-ity l ,Y
- 6. Frequent er severe headaches X l 17. Painful or " trick" shoulder X
- 7. Dizziness er fair.ti .;r spe!!s X l 18. Painful or " trick" elbow %
- 8. Eye trouble )( l 19. Paralysis
- 9. Diabetes X
, X j 20. Ep!!eosy or f!:s )/
- 10. Tuberculosis )( I 21. De ression or excessive wo.rv I)(
- 11. Chronle sho:tness of trea:h X I 22. Less of memory or ammf-
- 12. Pain or pressu*e in chezt er "hsart attack" 4
X 23. Nervors condition which could impair
- 13. Hirh bloed ;rassure )( M W eterrel M ty f
- 14. Low bloed cressure )( l 24. Drug or narcctic habit __ '
4
- 15. Peh*ier _d 6 25. Execestre drinkM.; htbi: 4 :
Complete each of the f:llowing. Give detti's of every affirma:ive answer undar item 37.
Yee *
.?e
- 26. Has your work ever been limited cr restricted for medical reasons' i
- 27. Have you ever been denied of rated up f:r !!fe insursnee fer edical reasonsS X
- 28. Have you ever been under cbservation er received care er treatment for any cental or nervous condition as a patient in a hospitd. sr.a.!!crium. c!!nic. or o:her facility, ci from a physician, clinical psychologist. etc.?
[
- 29. Hnva von ever hama rajanad far ar dienweed imm agiay . ant er m!!!!ary temite fer physica.'.Y.:rtal, Or I[ I i
nervous disorder reasons?
l l
- 30. Have you ever rece!ved. !s there pendler, have you applied for, or do you inund to apply for pension er t
compens.tlen for e.tisting disabCity? y A
- 31. Have you ever serious!) ernsidered cc mitt!nc suicide
- 32. Have you cver been cont,!:ted of any violation of Federal Ir.w. State law. county or municipal : 2w. rezuintiens 1 or ordina".ce? Do not in !:de anr.hing t.a.tt happened before your 16th birthday. Do not in:1ude violations for V which a fine of 325 cr less was :: posed.
/\
- 33. llave you ever had any r:1l:r !!! ness er 1-Jury ::her th:.n itese already noted?
- 34. How er;*y Jcb3 have you t.ad in the las: 3 yea s' l )( !
- 35. What is che length of time in your prese.: emp;oyment?
% (2)
/C hws 74 r
- 36. Give a brief s;atemmet c: your present hed:h in your own w:rds: - +
JYS h 1} gek , l h4 .h .a NW f
'h?
".4, /w .,L U P e y Z w - ~ g .Af ,4,f w4
- 37. Deta!!s of any items 5 through 33 answered in the affirma::ve. In udition. If y ur medical history includes r.ny ca::er re: 2:in? ::
physlen2. mental. cr nerv::s condi::on. please descr::e t .* eendit:sn and set fr.h you expir=:Lon 3! why this t .;;er wMd nn affect nur 2:llity to fun:t!cn as a facili:y .pera:or. Use a ditional sneet it c:re soace is needed.
- 38. I certify that the f recoPg in!ormatien sunlied by me is true to :he "ts: of my kr'wledge. and authorize the Ato?. c Energy Cot-
. mission to usc any cf the informa: ion n :his certificate in :ne exercise of its at.:r.Ority over the licensing of cper::: s.
. /
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.(Datet 4 .-:'_ $c $ er bLu g.bt.,
(F ac mty)
[ * (!!chh.re of ary! Lear./
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- SIGN
- YOtn NAhtE IN INX as IT APPEAft3 ON YOUn Al'PI! CATION I'O!! GPER \ Toft's On SENIO!
1 4
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. o< 5 - MEDICAL EXAMINATION
^
3'1, Doctor lt is essential ther eac% of the items on this page be completed. Sign the Certificate and moll to the Director, Divisien of Reacter Licensing, United Statse Atorate Energy Commission, Vashington, D.C. 20545 for reacter operator licenst. i.pplicants oe t3 the Director, Division of Materlois 1.lcensing, United States Atomic Energy Commission, Washington, D.C. 20.145 for oppfi.
cents for non. react,or operati,r llcansas.
' 43. Physicians's Summary and elaborotton of the medical history on front of raport. Use additional sheer if more space Is needed, u C h d.d.2t. 2 Lo
~
4 m a- [ ) * )Y f Physical E:aninstion. Give details of abnormal findings under item 21 below.
i
- 1. D te of examination // p 2. Height f. ',y 3. Welsht / r .d i .7.-t ,
- 4. Blood pressure // e ,/-@ 5. Pulse .P//
- 6. Distant visual acuity uncorrected right A kt C teft 8 O//; ,3 method used ,,/,, / . ,y
'7. Distant visualaculty ccrrected right left (data required only tf ccrrective lenses are normally worn)
- 8. Near visual aculty uncorrected right g left J, method used [,-. , , j-
- 9. NIar visuti aculty corrected /
richt left (data recuired only if corre::f/tve leni,=s are no mally worn)
- 10. Color vision />7 f?/ m . [ jq method used M // , # , v
- 11. Cross vicual fields h_'m'ag g .
- 12. flesring s right wh left ULSWk methed used 3/3 s % Ltf r i c.
- 13. Esv., so sv.ed . -
-ht ct.wi 14. Fwiin M% %(/ /-
- 15. Ophtha!=: scopic bN ~J. , .
. - . /
- 16. Earc. general _
E 17. Drums (7GJl,%c.&w .7d!&h% %4/MJw. ,
- 13. !!eart ) h ,J/ , 13.,Vascu12r system La.ug /
- p. Date and evaluntica of chest x ray taken wit?.ta the past yect. f f / r, / ) y Mgg,%L
- 21. Ditalls and evaluation of any item 1 thrvugh.20. above, reported alnorm'al and summary evaluation of over-all condition.
k .
~
L*,, L4,.OL,.sc- 4J l' d/) O QL.;zh,$. 4 t,,~(; ,s ' uL + 5'M" L 4 3< ,". ed L"On %o s'~"cn co~au'c. '> gP
%w w & aoif , r ," -
w, e1 %c,-w~JL. L r6 . .
- 22. ThS foregoing exa:alnation (b-s/does r.ot) reveal any mentalar physical disat!.!!ty which might cacse impalted judg nent er mater coordin: tion.
I understand that any of the information in this exam nation rnay he us d y the Atcmic NC~L .f. ission in the exercise of its authority o' r th licensins of operators. \ / ,/
// (o konee) 7D 1
/w er w G .te m G l (^~ (ssr6re Mum mns any.sassas Howard Schwander, M.D.
.e Typed or printed name of enbbtMi5hGpsn C0CTOR: IT 15 RECU! RED Little Rock, Ark. 72202 THAT EVERY ITEa OH THIS
- PAGE SE COl.'PLETED EX- ^"""
CE?T TiiOSE MAiUED '.VITH * ,
Arkansas
'r! HEN MOT APPLICABLE. ,,,,,,, o ,,,, m ,,,,,
2.