0CAN068913, Advises That Util Developing Appropriate Tech Spec for Inadequate Core Cooling Instrumentation Following Safety Review Committee Meeting on 890808,per NRC 890323 Request
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MONTHYEAR1CAN038914, Application for Temporary Amend to License DPR-51 to Limit Max Operating Power Level to 1,915 Mwt.Fee Paid1989-03-23023 March 1989
[Table View]Application for Temporary Amend to License DPR-51 to Limit Max Operating Power Level to 1,915 Mwt.Fee Paid Project stage: Request 0CAN068913, Advises That Util Developing Appropriate Tech Spec for Inadequate Core Cooling Instrumentation Following Safety Review Committee Meeting on 890808,per NRC 890323 Request1989-06-28028 June 1989 Advises That Util Developing Appropriate Tech Spec for Inadequate Core Cooling Instrumentation Following Safety Review Committee Meeting on 890808,per NRC 890323 Request Project stage: Meeting 1989-03-23 |
| ML20246B312 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/28/1989 |
| From: | James D ARKANSAS POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 0CAN068913, CAN68913, TAC-66069, TAC-71615, NUDOCS 8907070278 | |
| Download: ML20246B312 (1) | |
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Category:CORRESPONDENCE-LETTERS
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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 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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. 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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 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
[Table view]Requests Interim Relief from Inservice Testing Re Performing Partial Stroke Test for Check Valve 2SI-16A.Valve Currently Required to Be Tested by 900925 0CAN099002, Discusses Validation of Nonlicensed Operator Staffing,In Response to Insp Repts 50-313/90-01 & 50-368/90-01.Concludes That Current Level of Three Nonlicensed Operators Per Shift, Adequate to Meet Demands of Operations Under EOP1990-09-14014 September 1990 Discusses Validation of Nonlicensed Operator Staffing,In Response to Insp Repts 50-313/90-01 & 50-368/90-01.Concludes That Current Level of Three Nonlicensed Operators Per Shift, Adequate to Meet Demands of Operations Under EOP 0CAN099007, Forwards Operator Licensing Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-14014 September 1990 Forwards Operator Licensing Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 2CAN099004, Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis1990-09-0707 September 1990 Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis 0CAN099001, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/90-19 & 50-368/90-19.Corrective Actions:Surveillance Procedures Reverified & Revised1990-09-0707 September 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/90-19 & 50-368/90-19.Corrective Actions:Surveillance Procedures Reverified & Revised 1CAN099003, Requests one-time Rev to Natl Exam Schedule for Operator License & Requalification Exams at Facility to Allow Testing in Aug,Rather than Feb of 19911990-09-0606 September 1990 Requests one-time Rev to Natl Exam Schedule for Operator License & Requalification Exams at Facility to Allow Testing in Aug,Rather than Feb of 1991 0CAN089009, Informs of Relocation to New Generation Support Bldg Just Outside Protected Area Southeast of Administration Bldg1990-08-31031 August 1990 Informs of Relocation to New Generation Support Bldg Just Outside Protected Area Southeast of Administration Bldg 0CAN089006, Forwards Semiannual Radiological Effluent Release Rept for First & Second Quarters 1990 & Changes to ODCM & Process Control Manual1990-08-30030 August 1990 Forwards Semiannual Radiological Effluent Release Rept for First & Second Quarters 1990 & Changes to ODCM & Process Control Manual 0CAN089008, Forwards Facility fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.73(d)1990-08-29029 August 1990 Forwards Facility fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.73(d) 0CAN089005, Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 9010011990-08-27027 August 1990 Requests Authorization to Use Inconel 690 Tubing & Bar Stock for Steam Generator Repairs at Plant.Approval Necessary to Support Planned Use of I-690 Sleeves & Plugs During 1R9 Scheduled to Begin on 901001 1CAN089011, Requests Relief from ASME Code Section XI Requirements Re Exercise & Stroke Time Testing for Low Pressure Injection Valves CV-1432 & CV-1433.Valves Located in Bypass Lines Around Decay Heat Coolers1990-08-16016 August 1990 Requests Relief from ASME Code Section XI Requirements Re Exercise & Stroke Time Testing for Low Pressure Injection Valves CV-1432 & CV-1433.Valves Located in Bypass Lines Around Decay Heat Coolers 2CAN089009, Requests Addl Time to Respond to NRC 900607 Request for Info Re Second 10-yr Interval of Inservice Insp Program. Response Will Be Submitted No Later than 9010311990-08-13013 August 1990 Requests Addl Time to Respond to NRC 900607 Request for Info Re Second 10-yr Interval of Inservice Insp Program. Response Will Be Submitted No Later than 901031 0CAN089002, Responds to Recommendations from Insp Repts 50-313/90-04 & 50-368/90-04 on 900202 That Reporting Format for Semiannual Radioactive Effluent Release Repts Be Revised to Comply W/ Reg Guide 1.21,Rev 11990-08-0808 August 1990 Responds to Recommendations from Insp Repts 50-313/90-04 & 50-368/90-04 on 900202 That Reporting Format for Semiannual Radioactive Effluent Release Repts Be Revised to Comply W/ Reg Guide 1.21,Rev 1 05000313/LER-1989-041, Revises Commitment Completion Date for LER 89-041-00 Re Proper Method of Calibr of Startup Feedwater Control Valves CV-2623 & 2673 to 900915.Delay Due to Time Needed to Review & Implement New Calibr Guidance Criteria1990-08-0202 August 1990 Revises Commitment Completion Date for LER 89-041-00 Re Proper Method of Calibr of Startup Feedwater Control Valves CV-2623 & 2673 to 900915.Delay Due to Time Needed to Review & Implement New Calibr Guidance Criteria 2CAN089006, Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info1990-08-0202 August 1990 Forwards Steam Generator Tubing Inservice Insp Rept 2R7 Refueling Outage.No Tubes Plugged.Apologizes for Delay in Submitting Info ML20081E0891990-07-31031 July 1990 Advises That Since Guidance Contained in Reg Guide 1.97 Not Addressed in Submittals Re Generic Ltr 82-33,further Clarification of Position Re Compliance W/Generic Ltr Appropriate,Per .Ltr Will Be Submitted by 901215 0CAN079014, Amends Commitment Date for Mods to Svc Water Pump Design,Per Insp Repts 50-313/89-30 & 50-368/89-30.Project Scoping Rept Expected to Be Completed by 9009301990-07-31031 July 1990 Amends Commitment Date for Mods to Svc Water Pump Design,Per Insp Repts 50-313/89-30 & 50-368/89-30.Project Scoping Rept Expected to Be Completed by 900930 0CAN079024, Forwards Revised Response to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Specific Communication Meetings Will Be Conducted W/Staff Re Decontamination Practices & Procedures1990-07-31031 July 1990 Forwards Revised Response to Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Specific Communication Meetings Will Be Conducted W/Staff Re Decontamination Practices & Procedures 0CAN079020, Forwards Update to Status of Remaining Open Items on Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Encl Withheld (Ref 10CFR2.790)1990-07-31031 July 1990 Forwards Update to Status of Remaining Open Items on Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Encl Withheld (Ref 10CFR2.790) 0CAN079018, Certifies That Info Contained in Rev 12 to QA Manual Operations Freighted to NRC on 900723 & Accurately Represents Changes Made Since Previous Submittal,Per 10CFR50.54(a)(3)1990-07-24024 July 1990 Certifies That Info Contained in Rev 12 to QA Manual Operations Freighted to NRC on 900723 & Accurately Represents Changes Made Since Previous Submittal,Per 10CFR50.54(a)(3) 0CAN079021, Forwards Rev 12 to QA Manual Operations1990-07-23023 July 1990 Forwards Rev 12 to QA Manual Operations 0CAN079019, Forwards Rev 12 to QA Manual Operations.W/O Encl1990-07-23023 July 1990 Forwards Rev 12 to QA Manual Operations.W/O Encl 0CAN079011, Suppls Response to Violations Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Re Isolation Valve CS-26. Corrective Actions:Special Work Plan Developed & Valve Cs-26 Local Leak Rate Tested on 9002161990-07-20020 July 1990 Suppls Response to Violations Noted in Insp Repts 50-313/88-47 & 50-368/88-47 Re Isolation Valve CS-26. Corrective Actions:Special Work Plan Developed & Valve Cs-26 Local Leak Rate Tested on 900216 2CAN079008, Forwards Response to NRC Questions on CEN-386-P Re Extended Burnup Rept & Statistical Treatment of Elastic Strain in Fuel Cladding at end-of-life & Measured Axial Fuel Rod pellet-to-pellet Gaps1990-07-17017 July 1990 Forwards Response to NRC Questions on CEN-386-P Re Extended Burnup Rept & Statistical Treatment of Elastic Strain in Fuel Cladding at end-of-life & Measured Axial Fuel Rod pellet-to-pellet Gaps 0CAN079006, Provides Update to Util Providing Results of Comparison of Station Blackout Rule Submittals to NUMARC Guidance1990-07-17017 July 1990 Provides Update to Util Providing Results of Comparison of Station Blackout Rule Submittals to NUMARC Guidance 2CAN079001, Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip1990-07-0505 July 1990 Submits Addl Info Re 890822 Tech Spec Change Request for RCS Safety Valves & Plant Sys Turbine Safety Valves. Tolerance of -3% in Combination W/Current High Pressurizer Trip Setpoint Ensures Valves Will Not Open Prior to Trip ML20043H5161990-06-19019 June 1990 Informs of Changes of Responsibility for Plant Emergency Plan,Effective 900605 ML20043H3121990-06-18018 June 1990 Forwards Responses to Remaining NRC Questions Re Seismically Qualified,Partially Protected,Condensate Storage Tank (Qcst).Analyses in Calculations Demonstrate That Qcst Tank Foundation & Drilled Piers Adequate W/O Mod ML20043F3321990-06-15015 June 1990 Submits Addl Info on Tech Spec Change Request for Seismic Instrumentation,Per 890809 Request.Licensee Concurs W/Nrc Recommendation Re Editorial Change ML20043G0661990-06-13013 June 1990 Responds to Deviations Noted in Insp Repts 50-313/90-11 & 50-368/90-11.Corrective Actions:Further Evaluations Conducted to Develop Optimum List of post-accident Instruments Requiring Identification on Control Panels ML20043H3471990-06-11011 June 1990 Forwards Rev 19 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043G3801990-06-11011 June 1990 Responds to Violations Noted in Insp Repts 50-313/90-04 & 50-368/90-04.Corrective Actions:Decision Made to Staff Unit 1 Exit Location Point W/Health Physics Technician 24 H Per Day ML20043F5121990-06-0808 June 1990 Forwards List of Directors & Officers of Entergy Operations, Inc.Operation of All Plants Transferred to Entergy on 900606 ML20043F4341990-06-0707 June 1990 Informs of Receipt of Necessary Approvals to Transfer Operating Responsibilities of Plant to Entergy Operations, Per Amends 128 & 102 to Licenses DPR-51 & NPF-6, Respectively.Extension of Amend Request Unnecessary ML20043E6561990-06-0707 June 1990 Requests That Listed Distribution Be Made on All Future NRC Correspondence.Correspondence to Ns Carns Should Be Addressed to Russellville ML20043E4991990-06-0505 June 1990 Provides Supplemental Response to Violations Noted in Insp Repts 50-313/89-02 & 50-368/89-02.Corrective Actions:Listed Program Enhancements Being Implemented to LER Process to Provide Timely Determinations of Condition Rept ML20043E3851990-06-0404 June 1990 Concurs w/900516 Ltr Re Implementation of SPDS Complete for Both Units & Requirements of NUREG-0737,Suppl 1 Met ML20043E3771990-06-0404 June 1990 Forwards Response to Concerns Re Control Room Habitability Survey.Addl Mods Identified Will Enhance Overall Reliability of Control Room Sys & Changes Designed to Increase Performance,Effectiveness & Response of Habitability Sys ML20043C0821990-05-25025 May 1990 Withdraws 900410 Request to Amend Tech Spec Table 3.3-1 Re Applicable Operational Modes for Certain Reactor Protective Instrumentation Operability Requirements ML20043B6531990-05-22022 May 1990 Forwards Rev to Industrial Security Plan to Eliminate Need to Protect Certain Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21) ML20043B7091990-05-21021 May 1990 Forwards Revised Maelu Certificate of Insurance for Nuclear Onsite Property Insurance Coverage for 1990,changing Policy Number from X89166 to X90143R ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A5991990-05-15015 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Repts for Feb & Mar 1990 for Arkansas Nuclear One,Unit 1 ML20042H0551990-05-0909 May 1990 Forwards Civil Penalty in Amount of $50,000 for Violations Noted in Insp Repts 50-313/86-23 & 50-368/86-24 Re Environ Qualification of Electrical Equipment Important to Safety. Comprehensive Corrective Actions Undertaken ML20043B0841990-05-0909 May 1990 Corrects 900309 Ltr Re Completion of Security Perimeter Improvement Project,Per Insp Repts 50-313/87-31 & 50-368/87-31.Design Change Package Addressing Perimeter & Interior Lighting Scheduled to Be Onsite Late Summer 1991 ML20043A8361990-05-0707 May 1990 Responds to Violations Noted in Insp Repts 50-313/90-05 & 50-368/90-05.Corrective Actions:Personnel Involved Received Counselling Re Incident & Operations Personnel Being Trained on Significance of Surveillance Requirements ML20042F4371990-05-0404 May 1990 Requests 90-day Extension to Provide Addl Time for Reviews of Amends 128 & 102 to Licenses DPR-51 & NPF-6,respectively, Re Ownership Transfer ML20042G4771990-05-0404 May 1990 Forwards Summary of Util Exercise Critique Board Evaluation of Radiological Emergency Preparedness Exercise REX-90,per Insp Repts 50-313/90-08 & 50-368/90-08 ML20042F3351990-05-0303 May 1990 Forwards Nonproprietary Suppl 1 to CEN-386-NP & Proprietary Suppl 1 to CEN-386-P, Responses to Questions on C-E Rept CEN-386-P, 'Verification of Acceptability of 1-Pin Burnup Limit....' Proprietary Rept Withheld (Ref 10CFR2.790) ML20042F2701990-04-30030 April 1990 Provides Exam Schedules for Reactor Coolant Pumps a & B in Revised Inservice Insp Program Plan.Insps Scheduled for Refueling Outages 1R10 & 1R12 for Pump a Exams & Refueling Outages 1R10,1R12 & 1R14 for Pump B Exams 1990-09-07 |
Text
_ _________ _____ ._________ _ ____ _
mm
,7:
=r-P. O Box 551 Utw Rock AR 72203 TN 501377 4000 June 28, 1989 OCAN068913 U. S. Nuclear Regulatory Commission Document Control-Desk-Washington, DC 20555
SUBJECT:
Arkansas Nuclear One - Units 1 & 2
. Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Schedule for Submittal of TS Change Request for ICC Instrumentation (RVLMS/HLLMS)
(TAC Nos. 66069 and 71615) -
Gentlemen:
NRC letter dated March 23, 1989 (MCNA038925) transmitted the safety evaluation of the Inadequate Core Cooling (ICC) instrumentation at AN0-1 and 2, which concluded that the ICC systems for both units are performing
. satisfactorily;and meet the design and operation requirements specified in NUREG-0737, Item II.F.2. In that letter the staff also requested that additional technical specifications be developed for the the Reactor Vessel Level Monitoring Systems (RVLMSs) for both AND units and the Hot Leg Level Measurement System (HLLMS) for AN0-1, and provided guidance for their.
preparation. Technical specifications for the other portions of the ANO ICC
.instrum'entation (subcooled margin monitors and core exit thermocouple) for both units have been submitted and approved previously.
It has been AP&L's position that Technical Specifications for the RVLMSs and the HLLMS were not necessary, since this instrumentation is intended solely to enhance the operator's ability to corroborate indications of approach to ICC conditions. Further, since inventory tracking instrumentation is not used to initiate E0P actions, it is not classified as a Type A variable as definied by RG 1.97. However, in accordance with the staff's request, AP&L is presently developing appropriate technical specifications for submittal following the next Safety Review Committee meeting scheduled on August 8, t
1989.
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