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 Issue dateTitleTopic
ML20212K97830 September 1999Safety Evaluation Accepting USI A-46 Implementation ProgramSafe Shutdown
Ultimate heat sink
Safe Shutdown Earthquake
Earthquake
ML20209H82815 July 1999Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear StationPower-Operated Valves
Backfit
ML20206P04812 May 1999Safety Evaluation Concluding That NPP Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at CNS & Adequately Addressed Actions Requested in GL 96-05Stroke time
Past operability
ML20204B37011 March 1999SER Accepting Third 10-year Interval Inservice Insp Plan Requests for Relief for RI-17,Rev 1 and RI-25,Rev 0.Request for Relief RI-13,Rev 2 Involving Snubber Testing & Is Being Evaluated in Separate ReportScaffolding
ML20196J9647 December 1998Safety Evaluation Accepting Licensee Third 10-yr Interval Inservice Insp Plan Request for Relief RI-27,rev 1Incorporated by reference
Scaffolding
ML20196A28623 November 1998SER Re Core Spray Piping Weld for Cooper Nuclear Station. Staff Concluded That Operation During Cycle 19 Acceptable with Indication re-examined During RFO 18
ML20196A52423 November 1998Safety Evaluation Accepting Proposed Alternative to Use UT Techniques Qualified to Objectives of App Viil as Implemented by PDI Program in Performing RPV Shell Weld & Shell to Flange Weld Examinations
ML20196A50623 November 1998Safety Evaluation Re Flaw Indication Found in Main Steam Nozzle to Shell Weld NVE-BD-N3A at Cns.Plant Can Be Safely Operated for at Least One Fuel Cycle with Indication in as-is Condition
ML20195H17617 November 1998SER Authorizing Proposed Alternative in Relief Requests RV-06,RV-07,RV-09,RV-11,RV-12 & RV-15 Pursuant to 10CFR50.55a(a)(3)(ii).RV-08 Granted Pursuant to 10CFR50.55a(f)(6)(i) & RV-13 Acceptable Under OM-10Safe Shutdown
Stroke time
Incorporated by reference
Power-Operated Valves
ML20151Z61416 September 1998SER Accepting Util Responses to NRC Bulletin 95-002 for Cooper Nuclear StationGrab sample
ML20236R91320 July 1998SER Accepting Rev 13 to Quality Assurance Program for Operation Policy Document for Plant
ML20203K03526 February 1998SER Approving Third ten-year Interval Inservice Inspection Program Plan,Request for Relief PR-10 for Cooper Nuclear Station.Technical Ltr Rept on Request Relief PR-10 Also EnclVT-2
Incorporated by reference
ML20212E08123 October 1997SER Accepting Third 10-yr Interval Insp Program Plan & Associated Requests for Relief for PlantBoric Acid
Hydrostatic
Nondestructive Examination
VT-2
Incorporated by reference
Pressure boundary leak
Through-Wall Leak
ML20217E61423 September 1997Safety Evaluation Accepting Util Proposed Changes to Licensing Basis for Plant to Reflect Incorporation of Safer/Gestr Methodology for LOCA Analysis
ML20199F74114 August 1997Safety Evaluation Rept Accepting Design of torus-to-reactor Bldg Vacuum Breakers at PlantPower Operated Valves
Backfit
ML20210J57313 August 1997Safety Evaluation Denying Relief Request for Plant Third 10-yr Interval Program for Inservice Testing of Pumps. Request Not in Sufficient Detail to Justify Proposed AlternativeIncorporated by reference
ML20148H2386 June 1997Safety Evaluation Granting Licensee Relief Requests for 10-yr Interval Inservice Insp Program Plan for Plant,Unit 1Hydrostatic
VT-2
Incorporated by reference
ML20138K0247 May 1997Safety Evaluation Supporting Proposed Rev to RPV Surveillance Capsule Withdrawal ScheduleHydrostatic
ML20134N69119 February 1997Safety Evaluation Related to Third ten-year Interval Inservice Testing Program Nebraska Public Power District Cooper Nuclear StationSafe Shutdown
Stroke time
Incorporated by reference
Scram Discharge Volume
Power-Operated Valves
ML20198E10925 November 1992Safety Evaluation Accepting Licensee 920921 120-day Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46Earthquake
ML20127N37419 November 1992Supplemental SE Accepting Analysis & Results in Response to SBO rule,10CFR50.63
ML20128C29119 November 1992Safety Evaluation Accepting Revised ACAD Sys Into Nitrogen Containment Atmosphere Dilution,Eliminating Potential post-accident Oxygen Source
ML20059E27831 August 1990Safety Evaluation Granting Licensee 900525 Relief Requests RP-14 & RP-15 from Requirements to Measure Pump Inlet Pressure & Instrument Ranges,Respectively
ML20246B25031 May 1989Safety Evaluation on Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Domestic Operating Reactors. Intervals for on-line Functional Testing Consistent W/ Achieving High Reactor Trip Sys Availability at Reactors
ML20247A42420 March 1989Safety Evaluation Accepting Revised Process Control Program Re General Methods of Sampling,Processing,Analysis & Waste Formulation During Solidification of RadwasteProcess Control Program
ML20205S2033 November 1988Safety Evaluation Supporting Interim Operability of Piping SysEarthquake
ML20147B51623 February 1988Safety Evaluation Supporting Amend 117 to License DPR-46
ML20148C95913 January 1988Safety Evaluation Concluding That Inservice Testing Program Submitted w/860730 Ltr as Modified in Subj Safety Evaluation Will Provide Reasonable Assurance of Operational Readiness of safety-related Pumps & ValvesStroke time
Cold shutdown justification
Power Operated Valves
ML20238C40023 December 1987Safety Evaluation Supporting Proposed Mod to 10CFR50.62, ATWS Rule
ML20237E32621 December 1987Safety Evalution Supporting Amend 113 to License DPR-46
ML20236B89020 October 1987Sser Re Alternate Rod Insertion (ARI) Sys.Util Plans for Relocating ARI Position Indication Out of Control Room to Another Location in Control Bldg Acceptable
ML20235H03523 September 1987Safety Evaluation Re Alternate Rod Injection & Recirculating Pump Trip Sys
ML20235N45810 July 1987Safety Evaluation Supporting Util 810707,820623,0730 & 831215 Submittals Re Valve Operability Info for 24-inch Isolation Valves in Purge & Vent Sys.Nrc Conclusion Subj to Valves Being Modified to Have Torque Readjustments
ML20214S87421 May 1987Supplemental Safety Evaluation Re Dcrdr.Listed Activities Must Be Finished in Order to Satisfy Dcrdr Requirements in Suppl 1 to NUREG-0737Emergency Lighting
ML20212Q97216 April 1987Safety Evaluation Accepting Util 831104 & 870121 Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2, Post-Maint Verification Testing
ML20212L1756 March 1987Safety Evaluation Supporting Util Methodology in Standby Gas Treatment Suction Analysis & Interim Operation for Fuel Cycle 11 OnlyProbabilistic Risk Assessment
Finite Element Analysis
Earthquake
ML20209A70030 January 1987Safety Evaluation Accepting Util Response to Vendor Recommended Reliability Verification Testing Per Generic Ltr 83-28,Item 4.5.1 Re Reactor Trip Sys Reliability (Sys Functional Testing)
ML20215M50227 October 1986Safety Evaluation Accepting Util Response to Generic Ltr 82-33 Re Conformance to Rev 2 to Reg Guide 1.97,except for Instrumentation Associated W/Neutron Flux Variable
ML20210K24925 September 1986Safety Evaluation Supporting Analytical Method Used by Licensee to Evaluate Critical Stresses
ML20141E92910 April 1986Safety Evaluation Supporting Amend 98 to License DPR-46Exemption Request
ML20151Y25427 January 1986Safety Evaluation Re Requests for Relief from Inservice Insp Requirements.Relief Not Granted for Surface & Volumetric Exam of Drywell Piping Spray Welds Since Requirements Not ImpracticalHydrostatic
ML20140C57617 January 1986Safety Evaluation Supporting 831104 Response to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Concerning post-maint Testing Verification of Reactor Trip Sys Components
ML20134J63021 August 1985Safety Evaluation Accepting Proposed Mods as Ensuring Safe Shutdown Capability in Event of Fire in Areas of Concern in Accordance W/Requirements of 10CFR50,App RHot Short
Safe Shutdown
Fire Barrier
ML20127E72810 June 1985Safety Evaluation Supporting Response to Generic Ltr 83-28, Item 1.2 Re post-trip Review Data & Info Capability
ML20127E1056 May 1985Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Item 1.1 Concerning post-trip Review Program & Procedure
ML20148N2351 November 1978Safety Eval Rept of Main Stream Isolation Valve Test Results. Util Request for Continuing CNS in Present Fuel Cycle for Addl mid-cycle Msltv Leak Test Is Approved
ML20147D31029 September 1978Safety Evaluation Rept Supporting Amend 52 to Facil Oper Lic DPR-46 Concludes That Installation & Use of New Fuel Racks Can Be Accomplished Safety & Health & Safety of Pub Will Not Be EndangeredSafe Shutdown
Earthquake
Fuel cladding
ML20235F1594 April 1968Safety Evaluation Re FacilitySafe Shutdown
Operating Basis Earthquake
Design basis earthquake
Earthquake
Fuel cladding