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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 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) 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 0CAN079015, Discusses Clarification to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Surveillance Sampling Being Performed Monthly & Analyzed Prior to Loading/Releasing Each Load to Russellville Municipal Sewage Sys1990-07-26026 July 1990 Discusses Clarification to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Surveillance Sampling Being Performed Monthly & Analyzed Prior to Loading/Releasing Each Load to Russellville Municipal Sewage Sys 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 0CAN079017, Discusses Amend 8 to Plant Updated Sar.Certifies That Info Amend Represents Changes Made,Per 10CFR50.591990-07-23023 July 1990 Discusses Amend 8 to Plant Updated Sar.Certifies That Info Amend Represents Changes Made,Per 10CFR50.59 0CAN079010, Amends 880616 Response to Violations Noted in Insp Repts 50-313/88-11 & 50-368/88-11 Re Integrated Leak Rate Test. Procedure Rev Postponed & Will Be Incorporated Into Single Rev to Be Completed by 9103011990-07-20020 July 1990 Amends 880616 Response to Violations Noted in Insp Repts 50-313/88-11 & 50-368/88-11 Re Integrated Leak Rate Test. Procedure Rev Postponed & Will Be Incorporated Into Single Rev to Be Completed by 910301 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 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 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 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 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 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 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 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 1990-09-07
[Table view] |
Text
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-4000 January 31, 1980 2-010-25 Director of Nuclear Reactor Regulation ATTN: Mr. R. W. Reid, Chief Operating Reactor Branch #4 U.S. Nuclear Pegulatory Commission Washington, D.C. 20555
Subject:
Arkansas Nuclear One-Unit 2 Docket (40. 50-368 License No. NPF-6 CPC/CEAC Software Modifications (File: 2-1510)
Gentlemen:
The operating history of ANO-2 has indicated the need for a number of CPC/CEAC software modifications to (1) improse the unit availability and (2) enhance
- the overall operation of the CPC/CEAC system. We are presently reviewing a sof tware revision to the CPC/CEAC sof tware that will accomplish the above objectives by (1) recucing the probability of spurious trips and (2) providing additional diagnostic information to the plant staff. The purpose of this letter is to provide a description of the software modifications subsumed by this revision for your review.
The software modifications are delineated below and are fully described in the attached 'Descripticn of Mod 2B/3 CPC/CEAC Sof tware Modifications'.
- 1. Modification of the CPC DNBR update logic to include cold leg temperature difference biE; algorithm for asymmetric steam generator transients to enhance CPC response to HSSS Transients.
- 2. Modification of 16-bit penality factor word to include the DNBR and LPD penalty factors and related operating flags which will improve the trans-fer of information between the CEACs and CPCs.
- 3. Addition of a pre-set LPD panalty factor to be used in the calculation of the LPD total CEA deviation penalty factor in the event both CEACs are flagged inoperable.
- 4. Calculation of an average of the hot channel power distribution for use in computing the integrated one pin radial peak which will improve com-puter efficiency.
- 5. Application of the CEAC deviation penalty factor to the core average heat flux rather than to the one pin radial peak to reduce the proba-bility of spurious channel trips and increase reactor availability.
O MEMBER M:OOLE SOUTH UTILITIES SYSTEM 8002260 9' 1 TI I
Mr. R. W. Reid January 31, 1980 Calculation of the integrated one pin peak, hot pin heat flux dis-6.
tribution, hot pin axial shape index, and integrated hot pin heat flux during the STATIC DNBR program in order to improve computer efficiency and to ensure the most up-to-date values are used in the calculation of the STATIC DNBR.
- 7. Addition of a deadband at the low end of the excore detector signal range to reduce the sensitivity of the low end out-of-range alarm to signal noise.
- 8. Modification c' the shape annealing correction logic to include checks and corrections to top and bottom detector responses.
- 9. Addition of CPC and CEAC sensors out-of-range status arrays and ac-cessibility of this information via the operator's module and a tele-type to increase the diagnostic capabilities.
- 10. Provision for a " snapshot" of CPC variables at the time of a CPC channel trip to increase the diagnostic information available to the operator and plant engineer to increase their ability to determine the cause of the trip.
- 11. Modification of logic to indicate which CEAC has failed to increase the availability of the operable CEAC to continue to provide computed deviation penalty factors and CEA positions.
- 12. Modification of the core average heat flux filter algorithm to reduce the sensitivity of the heat flux calculation to noise.
- 13. Modification of CEAC logic to compute both a DNBR and a LPD penalty factor to enhance the capabilities of the CPCs, to make the penalty factors sub-group-dependent, and to add flags to the 16-bit penalty factor word for CEAC failure and for multiple CEA deviations within a subgroup and large penalty factors.
- 14. Provisions for a " snapshot" of CEAC variables at the time of a CEAC penalty factor greater than one or when the larger PF flag is set.
- 15. Modification to CPCs to include a DNBR correction factor for rod de-viation events.
Note that Item 12 above is the software change designated MOD 3, while the re-maining items are part of the software change that ha'd been designated MOD 28.
The separate designations arose from differences in time of origin, bases of origin, and other aspects. However, both MOD 2B and MOD 3 areFor being combined this reason, into one revision level of CPC/CEAC discs and documentation.
any reference to these modifications in this correspondence will be as MOD 2B/3, which better denotes the single revision level.
Mr. R. W. Reid January 31, U 30 All the software modifications of MOD 28/3 will be made in accordance with CEN-39(A), Rev. 2 and CEN-39(A), Supplement 1, Rev. 1. All modifications will be designed such that the CPC/CEAC system will automatically initiate shutdown of the reactor to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and to assist the Engineered Safety Features in limiting the consequences of cer-tain postulated accidents. The comprehensive software modifications testing program will assure that the modified CPC/CEAC system has been implemented in accordance with the specified functional design.
Our internal review of the MOD 2B/3 is incomplete at this time, but we expect that the software modifications will be found not to constitute an unreviewed safety question. Nonetheless, owing to the extent of the modifications, we are submitting this information for your review.
Sincerely yours, oDW (. Yb David C. Trimble Manager, Licensing DCT:WBM:nak Attachment D
l
DESCRIPTI0fi 0F MOD 2B/3 CPC/CEAC SOFTWARE MODIFICATI0fiS
- 1. Change: Modify CPC DIiBR update logic to include cold leg temperature difference bias algorithm for asymmetric steam generator tran-sients.
Reason: This modification provides a CPC OfiBR penalty based on the cold leg temperature difference caused by an asymmetric steam generator transient. The design basis event is the instantaneous closure of one MSIV. This modification ensures a reactor trip will occur when the DNBR margin is projected to a 1.3.
Description:
CPC protection is prvvided by determining a penalty factor based on the difference between the two cold leg temperatures and then applying this factor to the calculation of the updated CPC-calculated DiiBR. The computed temperature difference is compensated by a digital filter. The component temperature difference is used to determine a temperature-related PF component, and the core average power is used to determine a power-related PF component. These PF components are com-bined to yield the asymmetric SG transient penalty factor (PFASGT). Calculation of the updated Dt4BR is modified to include the PFASGT.
2a. Change: Modify 16-bit penalty factor word and associated logic to be con-sistent with the CEAC modifications.
Reason: Since modifications to the CEAC will nos include calculation of a LPD penalty factor (separate from the DNBR penalty factor) and
~
the setting of a flag indicating multiple CEA deviations in a sub-group, the 16-bit penalty factor word will have to be modified to transmit this information.
Description:
The 16-bit penalty factor word will transmit to the CPCs the following information in bits location 0-15, respectively:
- 1. CEAC fail bit (1 bit)
- 2. Dr4BR PF minus 1.0 (7 bits)
- 3. Multiple CEA deviations in subgroup flag (1 bit)
- 4. LPD PF minus 1.0 (6 bits)
- 5. Scale flag (1 bit)
Logic will be added to the CEACs and CPCs to pack and un-pack this information in the 16-bit penalty factor word.
2b. Change: Add scale type to processing of penalty factors and include scale flag in 16-bit penalty factor word.
Reason: For packing and unpacking the penalty factors in the 16-bit PF word, the highest resolution is obtained if the PF word processed falls within the range of 0 to 1. Therefore, where the adjusted PF (i .e., PFadj. = PF - 1.0) is greater than one, a pre-defined scalir.g factor is used to convert the adjusted PF to within the 0 to 1 range.
Description:
In the CEACs, the adjusted PF, during processing, is compared with small-scale and large-scale limits. The small-scale limit designates the upper bound of the acceptable small-scale PF region. The large-scale limit designates the upper bound of the acceptable large-scale PF region. If the adjusted PF is less than the small-scale limit, it is adjusted by the small-scale scaling factor to fit the 0.0 to 1.0 range. If the adjusted PF lies between the small-scale and large-scale limits, the adjusted PF is scaled down by the large-scale scaling factor to fit the 0 to l range. The scaled PF is then processed for packing into the penalty factor word. If the adjusted PF is equal to or greater than the large-scale limit, the large PF flag is set; and a bit pattern indicating a large PF is set in the penalty factor word.
- 3. Change: Provide pre-set LPD penalty factor for CEAC inoperable mode.
Reason: At present, if both CEACs are inoperable, a pre-set maximum penalty factor is used to calculate the total CEA deviation penalty tactor. By modifying the CEAC-CPC logic to include a LPD penalty factor, a pre-set maximum LPD penalty factor must be added to ensure the logic for the LPD deviation pen-alty factor is consistent with that for the DNBR deviation penalty factor when both CEACs are inoperable.
Description:
This modification to the CPCs adds logic to compare and select the larger of the two LPD penalty factors received from the CEACs in order to complete the LPD total CEA de-viation renalty factor. If one CEAC is failed or in-test, this modification includes logic to compare and select the larger of the penalty factors between (1) the operable CEAC and (2) the previously stored penalty factor from the failed CEAC. It also provides a pre-determined maximum penalty factor to be used in the event both CEACs are inoperable due to being in-test or failed.
- 4. Change: Calculate an average of the hot channel power distribution and use this variable in calculating the integrated one pin radial peak.
Reason: At present, the pseude hot in axial power distribution is cal-culated during the power Ji .tribution up-date, and this 20-mode power distribution is transferred to the " POWER" program out-put buffer. It is then used in the calculation of the hot pin heat flux distribution and the integra' edt one pid radial peak.
A nodal summation is performed for each calculation of the one pin peak. Since the pseudo hot pin axial power distribution does not change with each calculation of the one pin peak and updated CPC-calculated ONBR, elimination of this additional summation will improve- computer efficiency.
Description:
As part of the calculation of the pseudo hot pin axial power distribution, the average of the hot channel power distribution will also be determined. This factor will be transferred to the output buffer for use in the cal-culation of the integrated one pin radial peak.
Sa. Change: Apply the CEAC deviation penalty factor to the core average heat flux rather than to the one pin radial peak.
Reason: CEA deviations currently cause everly conservative DNBR cal-culations because the penalty factor is applied to the one '
pin radial peak. This modification applies the deviation penalty factor to the heat flux as an overpower margin cor-rection rather than to the one pin peak.
Description:
The CEA deviation penalty factor is deleted form the cal-culation of the hot pin heat flux distribution and the in-tegrated one pin radial peak in the UPDATE program and is added to the calculation of the adjusted compensated core average power (core average heat flux) in the STATIC pro-gram. In addition, the calculation of the integrated one pin radial peak is modified to replace the nodal sommation of the pseudo hot pin axial power distribution with the average of the hot channel power distribution.
Sb. Change: Modify CEA deviation penalty factor in the calculation of the local power dcasity.
- Reason: Present operating limits yield a much greater local power density (LPD) margin than DNBR margin. At pr'sent, the same CEA deviation penalty factor is applied to both the 'NBR and LPD margin calcula-tions. As a result, a Df4BR-initiated reactor trip will always occur before a LPD-initiated trip. To conserve the same relation-ship between DNBR and LPD, a separate LPD penalty factor is cal-culated and applied to the calculation of the uncompensated local power density in te UPDATE program.
Description:
In the UPDATE program, the equation for the uncompensated local power density is modified by substituting the CEA deviation LPD penalty factor for the CEA deviation DNB penalty factor.
- 6. Change: Perform calculation for integrated one pin peak, hot pin heat flux distribution, hot pin axial shape index, and integrated hot pin heat flux in the STATIC program.
Reason: The calculation of the STATIC DNBR is initiated immediately' af ter the power distribution calculation. However, the heat flux data used in the STATIC DNBR calculation are obtained from the UPDATE program, which uses power distribution data from the last execution of the POWER program. This could re-sult in these data being as much as 1.0 seconds old, and, therefore, inappropriate for use in the STATIC DNBR calcula-tion. This modification ensures the most up-to-date power distribution data are used in the calculation of the STATIC DNBR.
Description:
This modification calculates the integrated one pin peak,
- hot pin heat flux distribution, hot pin axial shape index, and integrated hot pin heat flux in the STATIC program prior to the calculation of the revised STATIC DNBR. Out-put buffer storage space is conserved by not transferring these values to the output buffer of the UPDATE program.
- 7. Change: Add deadband at low end of excore neutror, flux detector signal rbnge.
Reason: The low end of the excore detector signal range is equivalent to a hot standby operating condition. If the raw excore detector signal is less than the raw excore detector signal lower limit, the detector signal is set equal to the scaled detector signal lower limit and a sensor failure alann is initiated. This for-mat is sensitive to signal noise and results in unnecessary spurious sensor failure alarms at zero power. This modifi-cation adds a deadband to the low end of the excore detector signal range, which reduces the probability of spurious alarms.
Description:
A raw excore neutron flux signal low limit alarm setpoint value has been added to the sensor failure logic in the CPCs. The alarm setpoint is less than the signal lower limit. If the raw signal lies between the signal lower limit and the low limit alarm setpoint, the signal is set equal to th2 lower limit. If the raw signal is equal to or less thar the lcw limit alarm setpoint, the signal is set equal to the lower limit and a sensor failure alarm is initiated.
- 8. Change: Modify shape annealing correction logic to include checks and corrections to top and bottom detector responses.
At present, the logic indicates that if the detector segment Reason:
response for the upper third of the core is less than 3%, then the peak is in the bottom of the core; and the detector seg-ment response '.' the lower third of the core is not checked.
This modificatien ensures that both the upper and lower detector responses are c.:ecked. ,
Description:
The shape annealing correction logic has been adjusted to ensure that both the apper and lower detector responses are checked.
- 9. Change: Add CFC and CEAC sensors out-of-range status arravs and make accessible for display via the operator's module and a tele-type.
Reason: Sensor status information is provided so the operator is aware of which sensor has failed and to aid the plant engineer in compiling a history of sensor out-of-range failures.
Description:
Both a s oC and a CEAC failed sensor stack will be im-plementec Each stack will contain a maximum of six failed sen. s, the failed sensor ID, a sensor status and failure type indicator, and a time associated with the failure. New failed sensors will be added at the top of the stacks, and excess failed sensors (in excess of six) will be deleted from the bottom of the stacks.
The sensor failure stacks will be accessible for display through the operator's module and a teletype. -
- 10. Change: Provide a " snapshot" of CPC variables at the time of a CPC channel trip.
Reason: There is currently no CPC/CEAC information retained to deter.nine the inputs and calculated variables at the time of trip. As a result, determining the cause of trip is sometimes difficult, particularly if caused by spurious, momentary causes external to the CPC/CEAC system. Providing a list of variables at the time of channel trip will increase the ability of the operator and plant engineer to determine the precise cause of the trip.
Description:
When a trip signal is generated in a CPC channel, a " snap-shot" of specified variables will be transferred to a buffer that is accessible by teletype. These specified variables will include the following:
- 1. All CPC inputs (Pump Speeds in Fraction, not counts)
- 2. From Trip Sequence Program:
MINDNB - Minimum DNBR with uncertainty factor.
- 3. From Flow MC - calibrated CPC mass flow rate MCS - past value of calibrated CPC mass flow rate XI - flow projected DNBR
- 4. From UPDATE BDT - CPC Static Thermal Power BDTD - Total Th' mal Pcwer
- PHICAL - Neutron Fiux Power PF - DNBR Per.alty Factor PFLPD - Local Power Density Penalty Factor LPDDC - Compensated Local Power Density FCALC - Core Average Heat Flux P1 - One Pin Radial Peak D - Maximum Value of FR 4FZ QASI - Hot Pin Axial Shape Index DXMIN - Updated Minimum Quality X2 - Updated DNBR X3 - Pressure-Projected DNBR TCMAX - Maximum Cold Leg Temperature O
- 6. From POWER ASI - Axial Shape Index
- 6. From STATIC DST - Static Maximum of FR 4FZ MCST - Static Mass Flow Rate PRST - Static Pressure TCMST - Static Cold Leg Temperature FCALCST - Static Heat Flux (Compensated Core Average Power)
HMAX - Maximum Core Exit Enthalpy HF - Enthalpy of Saturated Fluid PFST - Static DNBR Penalty Factor
- 7. The addressable constants
- 8. The time of the trip.
An addressable constant will be provided to reset (clear) the buffer. The " snapshot" will be of the first channel trip after the buffer is cleared. In addition, an auto-restart will not clear the buffer, but a software reload will.
- 11. Change: Modify logic to indicate which CEAC has failed.
Reason: At present when operating in the CEA Ih0P code, if one CEAC is indicated inoperable, then both CEACs are considered in-operable. This modification expands the CEAC IN0P status in
~
the CPCs to indicate which CEAC is inoperable and to specify the DNBR and LPD penalty factors to be used. In this manner, if one CEAC is inoperable, the penalty factors from the oper-able CEAC will continue to be used.
Description:
The addressable constant CEANOP, which indicates to the CPC which CEAC has failed, will have four allowable values: CEAN0P = 0,1, 2, 3. The following listing summarizes the steps the CPC will take for each value of CEAN0P.
0 - Both CEACs ope'rable. Use DNBR and LPD penalty factors determined by the CEAC's.
1 - CEACl inoperable. Use last good DNBR and LPD pena'.ty factors from CEACl. Auctioneer with penalty factors from CEAC2. Record failure in failed st'enr stack.
2 - CEAC2 inoperable. Use last good DNBR and LPD penalty factors from CEAC2. Auctioneer with penalty factors from CEAC1. Record failure in failed sensor stack.
3 - Both CEAC's inoperable. Use predetermined DNBR and LPD penalty factors.
- 12. Change: Modify core average heat flux filter algorithm Reason: In the calculation of the core average heat flux, the adjust-ment of the static component of thermal power by the dynamic component can result in increases in the total thermal power that are highly sensitive to noise. This modification reduces the step increases and decreases due to the biases and, there-fore, reduces the sensitivity to noise. It includes the addi-tion of a second digital filter to optimize for increasing power.
Description:
Up until now the static thermal power has been biased with the dynamic component to yield the total thermal power.
The larger of the thermal power and the calibrated neutron flux power is returned as the core average power, which is con,ansated by two digital filters to yield the core average heat flux. Because of the wide swings in power due to the dynamic bias and the filter compensation, this method has been sensitive to noise.
This modification to the CPCs separates the application of uncertainty terms and filter compensation to the calibrated neutron flux power and thermal power. The calibrated neutron flux power is biased for uncertainties and compensated by a digital filter to optimize for increasing power. The static component of thermal power is increased by the dynamic component. The resulting total thermal power is biased for uncertainties and compensated by two digital filters to optimize for increasing and decreasing power. The larger of the optimized thermal power values and the optimized calibrated neutron flux power is returned as the core average heat flux. This modification also includes changes to the data base constants to account for the additional digital filter and for the functional change in the application of the original two digital filters.
This modification provides for:
a) reduced workload requirement for the dynamic component, b) compensation of the calibrated neutron flux power with the uncertainty bias and digital filter to optimize for increasing power, c) computation of a value of core average neat flux with a reduced value of the dynamic compensation, d) compensation of the total thermal power with an un-certainty bias and two digital filters to optimize for increasing and decreasing power, e) selection from the optimized calibrated neutron flux power and optimized total thermal power the maximum value as the core average heat flux.
13a. Change: Modify CEAC logic to compute both a DNBR and a LPD deviation
". penalty factor.
Reason: At present, the same CEA deviation penalty factor is applied to both the DNBR and the LPD margin calculations. As a result, the limiting value of two penalty factors must be used by the CEAC in its data base for calculating a penalty factor to be passed to the CPC. Since the limiting value is the LPD penalty factor,'which is significantly higher than the DNBR penalty factor, an excessively conservative penalty factor is applied to DNBR calculations. This modification adds a separate LPD penalty factor, which is processed for output to the CEAC-CPC data link.
Description:
In computing the DNBR and LPD penalty factors, the CEAC de-termines the lowest and highest CEA position in each sub-group and then computes the de.iation ;aagnitude between these two positions. If the deviation magnitude is less than a deviation deadband, then no penalty factor is re-quired for that subgroup. Otherwise, the penalty factors are determined based on the amount of the deviation magni-tude. With this method, the penalty factors are group-dependent.
13b. Change: Modify CEAC logic to compute a dynamic Xenon PF component and apply component to the calculation of the DNBR and LPD subgroup penalty factors.
- Reason: Any excessive CEA deviation will result in Xenon redistribution within the core. The impact and magnitude of the Xenon redistri-bution is directly dependent on the length of time of the devia-tion. For a case where a CEA is withdrawn from the core, the power in the region of the withdrawn CEA is increased which burns off the Xenon in that region. With less Xenon in that region than in the remainder of the core, the radial peak will increase. For a case where a CEA in inserted into the core, the power in the region of the inserted CEA is decreased which causes a buildup of Xenon in that region. As a result, the core will have rel-atively less Xenon than the region of the inserted CEA and the core average radial peak will increase. The impact of Xenon re-distribution occurs over a period of hours. To account for this phenomenon, a dynamic component is determined and applied to the calculation of the DNBR and LPD subgroup penalty factors.
Description:
A Xenon PF component is applied by maintaining an elapsed time counter for each subgroup. The counter is started when excess deviation in the subgroup is first detected, is frozen at a maximum elapsed time, and is reset to zero wnen the excess deviation is removed. The Xenon PF com-ponent is computed as a function of elapsed time.
13c. Change: Add a flag to indicate CEA failure to the 16-bit penalty factor word.
Reason: An excessive number of deviations in a core quadrant or an ex-
! cessive number of failed CEA sensors throughout the core could be indications of power supply problems. If the number of de-viated CEAs per core quadrant or the number of failed CEA sen-sors exceed pre-set values, the CEAC failure flag is set.
Description:
Up until now, the left-most bit in the 16-bit penalty fac-tor word has been used to indicate a CEAC in-test mode of operation. This modification to the CEAC program expands -
the use of this bit to indicate CEAC failure. This indi-cator or flag may be set as a result of failure summations in two sections of the CEAC program. When the raw CEA po-sitions are interrogated, if the CEA position exceeds the out-of-range or rate-of-change checks, the sensor failed flag is set for that CEA and the failure is added to a running sum. In the next section of the program, the de-viation magnitude and deviation type are determined. Dur-ing this process, the number of subgroups containing exces-sive deviations is summed per core quadrant. During the cal-culation of the penalty factors, the total number of sensor failures and the total number of deviated CEAs per core quad-rant are checked. If either of these sums exceed pre-set val-ues, the CEAC failure flag is set.
13d. Change: Add a flag to the penalty factor word to indicate 2 or more de-viated CEAs within a subgroup.
Reason: Two or more deviations within a subgroup could indicate excessive RSPT failures or power supply problems Therefore, if this con-dition exists, the 16-bit penalty factor word should be set to a multiple deviation indicator and the operator alerted to the con-dition.
Description:
The processed CEA positions are manipulated on the subgroup level to determine the deviation magnitude, deviation type (CEA withdrawal or CEA insertion), and overall group con-figuration. These quantities are found by first sorting the CEAs in the subgroup by relative position. The deviation magnitude is calculated from the most and least withdrawn CEAs. The definitions for the deviation types are the following:
0 - subgroup lies totally within the upper or 'ower core deadband (i.e., no CEA deviation).
il - single CEA withdrawal (+1) or insertion (-1).
ill - 5 CEA subgroup to distinguish deviations of center CEA.
2 - multiple CEA deviation within a subgroup.
During determination of the deviation types, if multiple CEA deviations are detected in a subgroup, the deviation type is set to 2. As a result, the large PF flag is set
and processed for output to the CEAC-CPC data link as one bit of the 16-bit penalty factor word; and the deviation alarm is initiated. The large PF flag is also set if the adjusted DNBR and LPD penalty factors equal or exceed the large-scale PF region limits.
- 14. Change: Provide a "snapshr t" of CEAC variables at the time of a CEAC penalty factor greater than one or when the large PF flag is determined.
Reason: There is currently no CPC/CEAC information retained to determine the CEA position inputs and calculated penalty factors at the time a large penalty factor is calculated or the large PF flag is set.
As a result, determining the cause of failure is sometimes difficult, particularly if caused by spurious, momentary causes external to the CPC/CEAC system. Providing a list of variables at the time of either of the aforementioned occurrences will increase the ability of the operator and plant engineer to determine the precise cause of the trip.
Description:
A " snapshot" of CEA positions, penalty factors, and time of deviation occurrence shall be stored when initiated by a CEAC penalty factor greater than one or by the large PF flag. This " snapshot" shall be accessible by teletype. In addition, the CRT display will exhibit an indicator over each subgroup with a deviation to indicate whether the de-viation initiated an alarm or a penalty factor.
- 15. Change: Add DNBR correction factor algorithm to CPC UPDATE program.
Reason: In the past, a red insertion event would-in all likelihood-cause a reactor trip because the penalty factors generated as a result of the rod deviation would be conservative. This process did not fully take into consideration available over-power margin. These changes, which incorporate a DNBR correc-tion factor into the CPCs, take credit for dvailable overpower ma rgi n .
Description:
The DNBR penalty factor is saved in a PF array for 35 executions of the UPDATE program. After updating for DNBR and quality changes, the power margin loss is com-puted using the most recent and the oldest DNBR penalty factors from the PF array. If the power margin loss violates minimum acceptable conditions, a DNBR correction factor is selected and applied to the calculation of the updated CPC calculated DNBR (X2).
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