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Category:CORRESPONDENCE-LETTERS
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 ML20217J4971999-10-18018 October 1999 Requests Addl Info Re Results of Util Most Recent Steam Generator Insp at ANO-2 & Util Methodology Used to Predict Future Performance of SG Tubes ML20217J3871999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through SG, Rev 0 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs ML20217J3601999-10-15015 October 1999 Informs That Topical Rept BAW-10235P, Management Program for Volumetric Outer Diameter Integranular Attack in Tubesheets of Once-Through SG, Rev 1 Marked as Proprietary Will Be Withheld from Public Disclosure 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp ML20217D1721999-10-0808 October 1999 Forwards RAI Re 990729 Request for Amend to TSs Allowing Special SG Insp for Plant,Unit 2.Questions Re Proposed Insp Scope for Axial Cracking Degradation in Eggcrate Support Region Submitted.Response Requested by 991015 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included ML20212L0621999-10-0101 October 1999 Forwards Safety Evaluation & Exemption from Certain Requirements of 10CFR50,App R,Section III.G.2, Fire Protection of Safe Shutdown Capability 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR ML20212F5031999-09-22022 September 1999 Forwards SER Granting Relief Requests 1-98-001 & 1-98-002 Which Would Require Design Mods to Comply with Code Requirements,Which Would Impose Significant Burden Pursuant to 10CFR50.55a(g)(6)(i) 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments ML20212D9961999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Arkansas Nuclear One.Nrc Plan to Conduct Core Insps at Facility Over Next 7 Months.Details of Insp Plan Through March 2000 Encl 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211L4901999-09-0101 September 1999 Forwards Insp Repts 50-313/99-12 & 50-368/99-12 on 990711- 0821.No Violations Noted ML20211J2351999-08-31031 August 1999 Forwards Request for Addl Info Re SG Outer Diameter Intergranular Attack Alternate Repair Criteria for Plant, Unit 1 ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211F4181999-08-25025 August 1999 Forwards SE Accepting Licensee 980603 & 990517 Requests for Approval of risk-informed Alternative to 1992 Edition of ASME BPV Code Section Xi,Insp Requirements for Class 1, Category B-J Piping Welds ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves IR 05000368/19990111999-08-12012 August 1999 Forwards Insp Repts 50-313//99-11 & 50-368/99-11 on 990719-23.No Violations Noted.Insp Focused on Review of Licensed Operator Requalification Program & Observation of Requalification Exam Activities at Unit 1 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 ML20210L3581999-07-29029 July 1999 Ltr Contract,Task Order 43, Arkansas Nuclear One Safety System Engineering Insp (Ssei), Under Contract NRC-03-98-021 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D8131999-07-28028 July 1999 Forwards Request for Addl Info Re SG Tube End Cracking Alternate Repair Criteria for Plant,Unit 1 ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 ML20210C2191999-07-21021 July 1999 Forwards Insp Repts 50-313/99-08 & 50-368/99-08 on 990530-0710 at Arkansas Nuclear One,Units 1 & 2,reactor Facility.No Violations Noted.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations ML20209H5251999-07-15015 July 1999 Informs That as Result of NRC Review of Licensee 980701 & 990311 Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 RAI, Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20209E5551999-07-0808 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1,suppl 1,staff Revised Info in Rv Integrity Database & Releasing Database as Rvid Version 2 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR1CAN109906, Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 11999-10-19019 October 1999 Forwards Framatome Technologies,Inc non-proprietary TR BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheet of Once-Through Sgs, Rev 1 2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs1999-10-15015 October 1999 Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs 2CAN109903, Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp1999-10-14014 October 1999 Forwards Response to RAI Re Proposed Tech Specs Change for Special SG Insp 1CAN109905, Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included1999-10-0404 October 1999 Discusses Insp of Once Through SG Tubing Surveillance Performed During 1R15 Scheduled RFO on 990910.Category C-3 Results,Included 1CAN099908, Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria1999-09-30030 September 1999 Withdraws 990919 Exigent TS Change Request to Allow Continued Installation of re-rolls for One Cycle of Operation Through End of Cycle 16 in Conjunction with Addl Insp Criteria 2CAN099902, Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,20001999-09-29029 September 1999 Requests That NRC Assign CENPD-132,Suppl 4-P, Calculative Methods for Abb Cenp Large Break LOCA Evaluation Model, Review Priority So That Approval Will Be Granted No Later than Oct 31,2000 1CAN099903, Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.31999-09-27027 September 1999 Forwards Rev 0 to COLR for ANO-1 Cycle 16, IAW TS 6.12.3 1CAN099907, Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative1999-09-26026 September 1999 Requests That Alternative Be Allowed in Accordance with 10CFR50.55a(a)(3)(i) & (II) as Discussed in Encl 1.Encl 2 & 3 Stress Analysis & Flaw Evaluation Summaries Ref in Encl Alternative 2CAN099901, Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 9908271999-09-24024 September 1999 Informs That G Kendrick,License SOP-43658,no Longer Has Need to Maintain Operating License on Ano,Unit 2.Entergy Requests That License for Individual Be Withdrawn,Due to Resignation, Effective 990827 1CAN099906, Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data1999-09-24024 September 1999 Forwards 1R15 Growth Data Obtained & Analyzed Through 990922 & Includes Plus Point Voltages,Axial Extent & Circumferential Extent Patches,As Well as Preliminary Growth Conclusions Based on Analysis of Data 2CAN099904, Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR1999-09-23023 September 1999 Forwards Ano,Unit 2 10CFR50.59 Rept for Time Period Ending 990225.Rept Contains Brief Description of Changes in Procedures & in Facility as Described in Sar,Tests & Experiments Conducted & Other Changes to SAR 1CAN099905, Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments1999-09-17017 September 1999 Submits Supplemental Info in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria.Proposed TS Rev & Info Related to Use of Alternate Repair Discussed in Attachments 1CAN099902, Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld1999-09-15015 September 1999 Forwards Proprietary Rev 1 to Topical Rept BAW-10235P, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs, in Response to 990831 Rai.Proprietary Encl Withheld 2CAN099905, Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested1999-09-0909 September 1999 Informs That Jk Caery,License OP-42589 & as Bates,License OP-42506,no Longer Need to Maintain Operating License at Ano,Unit 2.Withdrawal of Licenses Is Requested ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) 1CAN099901, Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments1999-09-0707 September 1999 Forwards Responses to 990831 RAI Containing follow-up Questions Discussed on 990823-26,in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria. Revs to Proposed TSs Included in Attachments 0CAN099906, Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs1999-09-0101 September 1999 Forwards Comments on Ano,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid,Version 2,in Response to NRC 990708 & 0715 Ltrs ML20211E6161999-08-25025 August 1999 Forwards Amend 15 to ANO Unit 2,USAR,per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of 10CFR50.59 Evaluations Associated with Amend 15 of ANO Unit 2 SAR Will Be Provided Under Separate Cover Ltr with 30 Days 0CAN089905, Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 19991999-08-25025 August 1999 Forwards Arkansas Nuclear One Units 1 & 2 FFD Program Performance Data for Period Jan-June 1999 ML20211G0731999-08-19019 August 1999 Forwards Applications for Renewal of Operating License for Kw Canitz & Aj South.Without Encls 1CAN089904, Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl1999-08-19019 August 1999 Forwards Addl Info in Support of SG Tube End Cracking Alternate Repair Criteria,In Response to NRC 990728 Rai. Proposed TS Changes Encl ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 0CAN089903, Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves1999-08-12012 August 1999 Submits Addl Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Gate Valves 2CAN089901, Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 9907291999-08-0606 August 1999 Forwards Description of Planned Scope & Expansion Criteria for Special SG Tube Insp,In Support of Proposed ANO-2 TS Amend for 2P99 Special SG Insp Submitted on 990729 1CAN089902, Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License1999-08-0505 August 1999 Requests NRC Input on Encl Proposed Draft Format for ANO-1 License Renewal Application,Which Will Provide Option to Continue Operating Plant for Addl Twenty Years Beyond End of Current Operating License 2CAN089902, Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested1999-08-0404 August 1999 Informs That Tl Russell,License SOP-43587-1 & Jk Fancher, License OP-42300-1,no Longer Have Need to Maintain Operating License at ANO-2.Withdrawal of Licenses Requested 0CAN089901, Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 9906031999-08-0202 August 1999 Forwards Info Re Estimate of licensee-originated Licensing Actions for ANO-1 & ANO-2,in Response to Administrative Ltr 99-02,dtd 990603 0CAN089902, Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified1999-08-0202 August 1999 Submits 60 Day Response to GL 99-02, Laboratory Testing of Nuclear Grade Activated Charcoal. Proposed Actions That Will Be Taken on ANO Unit 1 RB Purge Filtration Sys & Unit 2 Containment Purge & Exhaust Sys,Clarified 1CAN079903, Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-07-29029 July 1999 Forwards non-proprietary Addendum to Rev 0 of Topical Rept BAW-2346P,in Support of Proposed TS Changes Revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks ML20216D3561999-07-23023 July 1999 Discusses non-cited Violation Identified in Insp Rept 50-313/98-21,involving Failure to Have Acceptable Alternative Shutdown Capability for ANO-1 1CAN079901, Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages1999-07-14014 July 1999 Forwards Proposed Changes to Current Util 990409 Submittal Re Rev to RB Structural Integrity Requirements Contained in Plant Ts.Proposed Revs Affect ACs & Applicable Bases Re ISI Reporting for Containment Structures,Tendons & Anchorages 0CAN079902, Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl1999-07-14014 July 1999 Responds to NRC Telcon RAI Re Proposed Administrative Controls TS Changes.Revised TS Pages Which Replaces Pages Previously Provided in 981124 Submittal,Encl ML20210K1621999-07-0707 July 1999 Informs That Licensee in Process of Preparing Scope of Service Delineation for Environ Assessment to Be Performed for New Airport Located Near Russellville,Ar,To Identify Anticipated Environ Impacts from Various Agencies 1CAN079902, Documents ANO-1 Position Discussed on 990705,with Members of NRC Staff & Formally Requests Enforcement Discretion from Requirements of TS 3.7.2.C to Allow Continued Power of Operation1999-07-0606 July 1999 Documents ANO-1 Position Discussed on 990705,with Members of NRC Staff & Formally Requests Enforcement Discretion from Requirements of TS 3.7.2.C to Allow Continued Power of Operation ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 0CAN069906, Forwards Corrected Pages to 1997 & 1998 Annual Radiological Environ Operating Repts, Issued 980430 (0CAN049804) & 990506 (0CAN059902).Ltr Number & Page Number Are at Top of of Corrected Pages to Replace Originally Pages1999-06-30030 June 1999 Forwards Corrected Pages to 1997 & 1998 Annual Radiological Environ Operating Repts, Issued 980430 (0CAN049804) & 990506 (0CAN059902).Ltr Number & Page Number Are at Top of of Corrected Pages to Replace Originally Pages 1CAN069905, Forwards non-proprietary Version of Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs1999-06-17017 June 1999 Forwards non-proprietary Version of Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs 0CAN069903, Submits Rept of Each Change to or Error Discovered in Acceptable Evaluation Model or in Application of Such Model for ECCS That Affects Peak Cladding Temp,Iaw 10CFR50.46(a) (3)(ii)1999-06-10010 June 1999 Submits Rept of Each Change to or Error Discovered in Acceptable Evaluation Model or in Application of Such Model for ECCS That Affects Peak Cladding Temp,Iaw 10CFR50.46(a) (3)(ii) 2CAN069901, Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 20001999-06-0202 June 1999 Forwards Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14. Replacement of SGs Planned for Next Refueling Outage (2R14) Scheduled for Fall of 2000 1CAN069901, Submits 10CFR50.46 Rept Re Inconsistent Input in SBLOCA Analysis.Rept Submitted in Accordance with Recommendations Stated in Notice1999-06-0202 June 1999 Submits 10CFR50.46 Rept Re Inconsistent Input in SBLOCA Analysis.Rept Submitted in Accordance with Recommendations Stated in Notice 0CAN059906, Forwards Response to NRC 990402 RAI Re GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-05-28028 May 1999 Forwards Response to NRC 990402 RAI Re GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs ML20207E4341999-05-25025 May 1999 Submits 30-day Written Rept on Significant PCT Changes in ECCS Analysis for ANO-1.CRAFT2 Limiting PCT for ANO-1 Was Bounded by 1859 F PCT Calculated at 2568 Mwt for Crystal River 3 Cold Leg Pump Discharge Break Size of 0.125 Ft 1CAN059904, Informs NRC That Wl Franklin No Longer Has Need to Maintain Operating License on Ano,Unit 1.Requests License for Wl Franklin Be Withdrawn1999-05-20020 May 1999 Informs NRC That Wl Franklin No Longer Has Need to Maintain Operating License on Ano,Unit 1.Requests License for Wl Franklin Be Withdrawn 2CAN059906, Informs That ANO-2 UFSAR Will Be Revised to Include Comprehensive Discussions of Each Category of Containment Penetration Overcurrent Protective Devices,Per NRC Review of 980806 TS Change Request Re Relocation of TS Table 3.8-11999-05-18018 May 1999 Informs That ANO-2 UFSAR Will Be Revised to Include Comprehensive Discussions of Each Category of Containment Penetration Overcurrent Protective Devices,Per NRC Review of 980806 TS Change Request Re Relocation of TS Table 3.8-1 1CAN059902, Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program1999-05-17017 May 1999 Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program 2CAN059905, Expresses Appreciation for Staff & Mgt Team Efforts in Aggressively Pursuing Risk Informed ISI Initiative1999-05-14014 May 1999 Expresses Appreciation for Staff & Mgt Team Efforts in Aggressively Pursuing Risk Informed ISI Initiative ML20206P7681999-05-10010 May 1999 Forwards Applications for Renewal of Operating License (Form 398) for MW Little & F Uptagrafft.Without Encl 2CAN059903, Forwards Rev to Footnote Submitted to Provide Clarity to Aforementioned Guidance1999-05-10010 May 1999 Forwards Rev to Footnote Submitted to Provide Clarity to Aforementioned Guidance ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206H7121999-05-0606 May 1999 Forwards 1998 Annual Radiological Environ Operating Rept, for Ano.All Radionuclides Detected by Radiological Environ Monitoring Program During 1998 Were Significantly Below Regulatory Limits 1999-09-09
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NOTE: This transmittal contains Emergency Preparedness exercise information that should Not be released to the Public Document Room before 6/24/93.
March 19, 1993 OCANO39310 Mr. James L. Milhoan, Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, Tx 76011-8064
Subject:
Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 & 50-368 License Nos. DPR-51 and NPF-6 Objectives for the 1993 Radiological Emergency Preparedness Exercise
Dear Mr. Milhoan:
The objectives to be demonstrated by the utility during the Arkansas Nuclear One 1993 Radiological Emergency Exercise (REX-93) are attached for your review.
Please contact me or Mr. Fred VanBuskirk, Supervisor, Emergency Planning (501-964-6901), if you have any questions or comments regarding this information.
Sincerely, F / /. Wdc, Robert S. Berent Manager, Training and Emergency Planning RSB/hdy Attachment cc: Dr. D. Blair Spitzberg Eraergency Preparedness Analyst NRC Region IV 611 Ryan Plaza Drive, Suite 400 t 28003._ Arlington, Tx 76011-8064 U. S. Nuclear Regulatory Commission n
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Document Control Desk f Mail Station F1-137 ,/
Washington, DC 20555 f f J
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Page 2 of 2 Anna styn Health Program Analyst Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72201-3867 J. J. Fisicaro F. P. VanBuskirk ANO-DCC o
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l REX-93 ANO OBJECTIVES The 1993 exercise will be an off-year exercise, and will not include participation by the NRC or local governments. The State of Arkansas will play, but will not be evaluated by the Federal Emergency Management Agency.
All of the one-year objectives, as outlined in NRC Inspection Procedure 82302, will be exercised in the 1993 exercise along with seven (7) five-year objectives.
The scenario contains several interactive features. As in previous exercises, the scenario will be driven by the plant simulator.
Additionally, Repair and Damage Control Teams will be evaluated in detail, and attention will be given to the ef fectiveness of the new Operational Support Center. Simulation of team activities will be-held to a minimum. This will be accomplished through the use of mock-ups where practical. Success pathways by the Repair and Damage Control Teams will be rewarded based upon satisfactory completion of assigned tasks rather than predetermined scenario times. This concept will apply to the performance of operators and the Emergency Medical Team as well. The event times provided in the scenario are approximations based on anticipated response times of emergency teams.
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- 1. Demonstrate the use of the Emergency Action Level Classification procedure for Emergency Class declarations.
- 2. Notification and deployment of the Initial Response Staff (IRS) and the Emergency Response Organization (ERO) as dictated by the scenario.
- 3. Make notifications to the Arkansas Department of Health within 15 minutes of the declaration of an Emergency Class.
- 4. Make emergency class notifications to the NRC in accordance with 10CFR50.72 (may be simulated if the NRC chooses not to participate).
- 5. Activation of the Technical Support Center (TSC) within one hour following the declaration of an Alert or higher emergency class.
- 6. Activation of the Operational Support Center (OSC) within one hour following the declaration of an Alert or higher emergency class.
- 7. Activation of the Emergency Operations Facility (EOF) within one hour of a Site Area or General Emergency.
- 8. Establishment of communications between the Control Room, Technical Support Center, Operational Support Center, Emergency Operations Facility, NRC (simulated), and State emergency response officials.
- 9. Demonstrate effective and accurate information flow within and between each Emergency Response Facility.
- 10. Demonstrate an effective teamwork response within and between 1 the Control Room, Technical Support Center, Operational Support Center and Emergency Operations Facility throughout ;
the exercise. !
- 11. Transfer Emergency Direction and Control responsibilities (and l maintain continuity) from the Initial Response Staff to the Emergency Response Organization.
12 Demonstrate proper selection of Protective Action l Recommendations (PAR) and timely delivery of PARS to the Arkansas Department of Health.
- 13. Activation of the ANO Emergency Medical Team.
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- 14. Emergency Medical Team response to- a simulated ' injured individual.
- 15. Demonstrate activation of the ANO Fire Brigade.
- 16. Fire Brigade response to a simulated fire onsite.
- 17. Radiation monitoring and contamination control of plant areas by the onsite section of the Emergency Radiation Team.
- 18. Demonstrate offsite radiological field monitoring by the offsite section of the Emergency Radiation Team.
- 19. Demonstrate radiation monitoring and contamination control in the EOF.
- 20. Demonstrate coordination between field monitoring. teams and dose assessment personnel.
- 21. Utilize the Radiological Dose Assessment Computer System (RDACS) to demonstrate dose assessment capabilities, as dictated by the scenario.
- 22. Utilize the Safety Parameter Display System (SPDS) to monitor selected plant parameters.
- 23. Demonstrate security procedures for the site and the Emergency Operations Facility.
- 24. Formation of Repair and Damage Control Teams and demonstrate initial recovery and reentry actions.
- 25. Demonstrate coordination between ANO and the Corporate Emergency Center (CEC) at Echelon. i
- 26. Demonstrate the capability to effectively brief the NRC site team upon their arrival (ANO personnel will play the roles of NRC site team members).
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SUPPLEMENT 1 The following supplement to the Arkansas Nuclear One REX-93 objectives identifies the elements that should be exercised each year or over a 5-year period during emergency preparedness exercises. The first section denotes those elements which should be exercised each year and how ANO will address these elements during REX-93. The second section denotes those elements which should be exercised over a 5-year period and those elements which will be exercised by ANO during REX-93. Additionally , each listed element is referenced to the appropriate section of NUREG-0654, Part II or Supplement 1 to NUREG-0737.
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I. ONE YEAR ELEMENTS A. ACCIDENT DETECTION AND ASSESSMENT - I.1, I.2
- 1. The scenario will require utilization of the Emergency Action Level Classification procedure as well as the following plant systems,
- a. Plant Simulator
- b. Radiological Dose Assessment Computer System (RDACS).
- c. Safety Parameter Display System (SPDS)
- 2. Applicable REX-93 Objectives: i Obiective No. 1: Demonstrate the use of the Emergency Action Level Classification procedure for Emergency Class declarations.
Obiective No. 21: Utilize the Radiological Dose Assessment Computer System (RDACS) to demonstrate dose assessment capabilities, as dictated by the scenario.
Obiective No. 22: Utilize the Safety Parameter Display System (SPDS) to monitor selected plant parameters.
B. EMERGENCY CLASSIFICATION - D.1, D.2
- 1. Off-normal plant conditions will be presented which will require the use of the emergency classification and emergency action level scheme contained in procedure 1903.010, " Emergency Action Level Classification".
- 2. Applicable REX-93 Objective:
Obiective No. 1: Demonstrate the use of the Emergency Action Level Classification procedure for Emergency Class declarations.
C. NOTIFICATION OF ONSITE AND OFFSITE EMERGENCY RESPONDERS
- E.1, E.2, E.3, J.1
- 1. Proper response to scenario events will require that notifications be accomplished to the ANO Emergency Response Organization, the Arkansas Department of Health, and the Nuclear Regulatory Commission (ENS) .
- 2. Applicable REX-93 Objectives:
Obiective No. 2: Notification and deployment of the Initial Response Staff (IRS) and the Emergency Response Organization (ERO) as dictated by the scenario.
Obiective No. 3: Make notifications to the Arkansas Department of Health within 15 minutes of the declaration of an Emergency Class.
Obiective No. 4: Make emergency class notifications to the NRC in accordance with 10CFR50.72 (may be simulated if the NRC chooses not to participate).
D. COMMUNICATIONS - F.1, F.2, E.2, E.4, H.6, 8.1, 8.2, 8.3, 8.4
- 1. Communications activities during the exercise will include the following:
- a. Use of Procedure 1903.011, " Emergency Response /
Notifications" to perform notifications.
- b. Activation of the TSC, OSC, and EOF communica-tion links.
- c. Use of the Emergency Response Facility voice and data acquisition systems (e.g. telephone, radio system, status board network, SPDS).
- d. Use of an automated computer-based emergency communication system.
- 2. Applicable REX-93 Objectives:
Obiective No. 3: Make notifications to the Arkansas Department of Health within 15 minutes of the declaration c2 an Emergency Class.
Obiective No. 4 : Make emergency class notifications to the NRC in accordance with 10CFR50.72 (may be simulated if the NRC chooses not to participate).
Obiective No. 5: Activation of the Technical Support Center (TSC) within one hour following the declaration of an Alert or higher emergency class.
Obiective No. 6: Activation of the Operational Support Center (OSC) within one hour following the declaration of an Alert or higher emergency class.
Obiective No. 7: Activation of the Emergency Operations Facility (EOF) within one hour of a Site Area or General Emergency.
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Obiective No. 8: Establishment of communications between the Control Room, Technical Support Center, Operational Support Center, Emergency operations Facility, NRC (simulated), and State emergency response officials.
Obiective No. 9: Demonstrate effective and accurate information flow within and between each Emergency Response Facility.
Obiective No. 18: Demonstrate offsite radiological field monitoring by the offsite section of the Emergency Radiation Team.
E. RADIOLOGICAL EXPOSURE CONTROL - K.1, K.2, K.3, K. 5, K . 6, J.6
- 1. Methods for exercising this element include implementation of Procedure 1903.033, " Protective Action Guidelines for Rescue / Repair and Damage Control Teams". This procedure contains guidelines for exceeding 10CFR20 limits under emergency conditions. Additional measures include dosimetry coverage for emergency response activities and facilities, contamination control, and the use of protective clothing and equipment.
- 2. Applicable REX-93 Objectives:
Obiective No. 17: Radiation monitoring and contamination control of plant areas by the onsite section of the Emergency Radiation Team.
Obiective No. 19: Demonstrate radiation monitoring and contamination control in the EOF.
Obiective No. 24: Formation of Repair and Damage Control Teams and demonstrate initial recovery and reentry actions. :
F. PROTECTIVE ACTION RECOMMENDATIONS - J.7
- 1. The scenario will present simulated conditions which will require that protective action recommendations, based on plant conditions and/or projected dose to the public, be issued to responsible offsite authorities.
- 2. Applicable REX-93 Objectives: j Objective No. 12: Demonstrate proper selection of l Protective Action Recommendations (PARS) and timely I delivery of PARS to the Arkansas Department of I Health.
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G. STAFF AUGMENTATION - A.1, A.3, A.4, B.7, B.8, B.9
- 1. The exercise scenario will provide for the notification and activation of the ANO Emergency Response Organization. The State emergency response organization will be activated on a limited basis only. Support capabilities from offsite agencies (i.e. , Pope County Emergency Medical Service and St.
Mary's Hospital) will not be tested.
- 2. Applicable REX-93 Objectives:
Obiective No. 5: Activation of the Technical Support Center (TSC) within one hour following the declaration of an Alert or higher emergency class.
Obiective No. 6: Activation of the Operational Support Center (OSC) within one hour following the declaration of an Alert or higher emergency class.
Obiective No. 7: Activation of the Emergency Operations Facility (EOF) within one hour of a Site Area or General Emergency.
Obiective No. 11: Transfer Emergency Direction and Control responsibilities (and maintain continuity) from the Initial Response Staff to the Emergency Response Organization.
Obiective No. 14: Emergency Medical Team response to a simulated injured individual.
H. SHIFT STAFFING - B.1, B.2, B.3, B.5, TABLE 2
- 1. The on-shift staff will be comprised of Operations personnel located in the Unit-2 Simulator, as well as nonlicensed operators and other personnel located in the plant. This staffing level represents a normal shift complement.
Initially, the Shift Superintendent will be responsible for Emergency Direction and Control.
The exercise scenario events will require this responsibility to be transferred ultimately to the EOF Director.
- 2. Applicable REX-93 Objectives:
Obiective No,_1: Notification and deployment of the Initial Response Staff (IRS) and the Emergency Response Organization (ERO) as dictated by the i scenario. I l
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Obiective No. 11: Transfer Emergency Direction and control responsibilities (and maintain continuity) from the Initial Response Staff to the Emergency
II. ELEMENTS THAT SHOULD BE EXERCISED OVER A 5-YEAR PERIOD A. OFF-HOURS STAFFING (6 P.M. TO 4 A.M.) - N.1.b
- 1. Not exercised during REX-93.
B. ACTIVATION OF EMERGENCY NEWS CENTER - G.3, G.4
- 1. Not exercised during REX-93.
C. USE OF FIRE CONTROL TEAMS - N.2.b, 0.4.d
- 1. The scenario will include a simulated fire within the plant site boundary, and will necessitate activation of the Fire Brigade.
- 2. Applicable REX-93 Objectives:
Obiective No. 15: Activation of the ANO Fire Brigade.
Obiective No. 16: Fire Brigade response to a simulated fire onsite.
D. USE OF FIRST AID AND/OR RESCUE TEAMS - K.1, K. 2, K. 3, K. 4 K.5, L.2, 0.4.f
- 1. The exercise scenario contains a simulated injury to a Repair Team member (not contaminated), and is intended to test first aid and rescue capabilities.
- 2. Applicable REX-93 Objectives: .
Obiective No. 13: Activation of the ANO Emergency Medical Team.
Obiective No.14: Emergency Medical Team response to a simulated injured individual.
E. USE OF MEDICAL SUPPORT PERSONNEL - N. 2.c, L.1, L. 4, 0. 4.h
- 1. The event referred to in D.1 above will require a involvement by the Emergency Medical Team and Health Physics personnel. However, the Pope County Emergency Medical Service and St. Mary's Hospital (offsite medical support) will not participate.
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F. USE OF LICENSEE' S HEADQUARTERS SUPPORT PERSONNEL - 0.4. i
- 1. The Corporate Emergency Center (CEC) at Echelon in 1 Jackson, Mississippi will be activated and staffed l to demonstrate support efforts.
- 2. Applicable REX-93 Objectives Obiective No. 25: Demonstrate coordination between ANO and the Corporate Emergency Center (CEC) at Echelon.
G. USE OF SECURITY PERSONNEL TO PROVIDE PROMPT ACCESS FOR EMERGENCY EQUIPMENT AND SUPPORT - O.4.d
- 1. The ANO Security Force will participate in the exercise under the direction of the TSC Support Superintendent who reports to the TSC Director.
- 2. Applicable REX-93 Objectives:
Obiective No. 23: Demonstrate security procedures for the site and the Emergency Operations Facility.
H. USE OF BACKUP COMMUNICATIONS - F.1
- 1. Not exercised during REX-93.
I. RUMOR CONTROL - G.4.c
- 1. Not exercised during REX-93.
J. USE OF EMERGENCY POWER (WHERE NOT A PART OF PLANT SAFETY SYSTEMS, E.G. TECHNICAL SUPPORT CENTER (TSC)) - 8.2.1
- 1. Not exercised during REX-93.
K. EVACUATION OF EMERGENCY RESPONSE FACILITIES (ERFs) AND RELOCATION TO BACKUP ERFs, WHERE APPLICABLE - J.10.g
- 1. Not exercised during REX-93.
L. INGESTION PATHWAY EXERCISE - J.9, J.11
- 1. Not exercised during REX-93.
M. FIELD MONITORING, INCLUDING SOIL, VEGETATION, AND WATER SAMPLING - I.7, I.8, I.11, H.2.d
- 1. Field monitoring by ANO and State personnel will be performed, however, sampling by offsite teams will be limited to particulate and iodine sampling along with direct radiation measurements.
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- 2. Applicable REX-93 Objective:
Ohiective No. 18: Demonstrate offsite radiological field monitoring by the offsite section of the Emergency Radiation Team.
N. CAPABILITY FOR DETERMINING THE MAGNITUDE AND IMPACT OF THE PARTICULAR COMPONENTS OF A RELEASE - I.3, I.4, I.6, I.8, I.9, I.10
- 1. Scenario events will require activation and '
operation of the Dose Assessment Team to determine the magnitude of the simulated release and the offsite consequences. The results of these assess-ments will be utilized to develop Protective Action Recommendations (PAR) for the general public to be issued to offsite authorities.
- 2. Applicable REX-93 Objectives:
Obiective No. 12: Demonstrate proper selection of Protective Action Recommendations (PAR) and timely delivery of PARS to the Arkansas Department of Health.
Obiective No. 20: Demonstrate coordination between field monitoring teams and dose assessment personnel (i.e. , between the Of f site Monitoring Supervisor and the Dose Assessment Supervisor).
Obiective No. 21: Utilize the Radiological Dose Assessment Computer System (RDACS) to demonstrate dose assessment capabilities, as dictated by the scenario.
O. CAPABILITY FOR POST-ACCIDENT COOLANT SAMPLING AND ;
ANALYSIS - I.2
- 1. Although the exercise ' scenario will not present conditions which will require the use of the Post ,
Accident Sampling System, the ERO may elect to utilize the system.
P. USE OF POTASSIUM IODIDE - J.6.c
- 1. Not exercised during REX-93.
Q. ASSEMBLY AND ACCOUNTABILITY - J.S
- 1. Not exercised during REX-93.
R. RECOVERY AND RE-ENTRY - M.1
- 1. Initial recovery and re-entry planning will be .
demonstrated by the TSC/OSC staffs and the resulting plans will be implemented by the Repair and Damage Control Taams.
- 2. Obiective No. 24: Formation of Repair and Damage Control Teams and demonstrate initial recovery and ,
re-entry actions.
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