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 Issue dateTitleTopic
ML20211A97920 August 1999Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2Incorporated by reference
ML20209E4369 July 1999SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
ML20196K6637 July 1999Safety Evaluation Supporting Licensee 990520 Position Re Inoperable SnubbersOperability Determination
ML20206P52014 May 1999Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated ValvesStroke time
Power Uprate
ML20205S55521 April 1999Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20205N36512 April 1999Safety Evaluation Accepting IPE of External Events SubmittalFire Barrier
Internal Flooding
Probabilistic Risk Assessment
Earthquake
ML20196J8358 December 1998Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys
ML20196C02527 November 1998SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station
ML20196A68825 November 1998Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three WeldsHydrostatic
VT-2
Unidentified leakage
ML20247M08621 May 1998SER Accepting 1997 Rev to Catawba UFSAR Submitted on 970925. Rev Added Analysis for Postulated Accident Involving Dropping of Sf Pool Weir Gate Onto Sf Assemblies
ML20216E17713 April 1998Safety Evaluation Accepting Relief Request 98-01 for Catawba Nuclear Station Units 1 & 2 from Requirements of ASME Boiler & PV Code for Second 10-year Interval Program for Inservice Testing of Pumps & Valves
ML20217M4213 April 1998Safety Evaluation Approving Request for Relief 97-04, non-code Repair Valves.Relief Granted Retroactively to Unit 1 & Expired Dec 1997.Relief for Unit 2 Will Expire at End of Cycle 9 Outage or Next Scheduled Outage Exceeding 30 DaysThrough-Wall Leakage
Operability Assessment
ML20199A55222 January 1998Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, for Cns,Units 1 & 2Safe Shutdown
Power-Operated Valves
Backfit
ML20199A64222 January 1998Safety Evaluation Accepting Proposed EALs Changes for Plant, Units 1 & 2.Concludes That Changes Consistent W/Guidance in NUMARC/NESP-007,w/variations as Identified & Accepted in Review & Meets Requirements of 10CFR50.47(b)(4)Safe Shutdown
Reactor Vessel Water Level
Ultimate heat sink
Fuel cladding
ML20198P96415 January 1998SE Granting Relief Request 97-03 for Second 10-yr Interval Inservice Insp ProgramIncorporated by reference
ML20198R99530 October 1997Safety Evaluation Authorizing Request for Approval of Alternative to Exam Requirement of Reactor Vessel Shell Weld,Per 10CFR50.55a(g)(6)(ii)(A)(5)Incorporated by reference
ML20198J76515 October 1997Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants UnitsVT-2
Incorporated by reference
ML20211F88022 September 1997Safety Evaluation Supporting Second ten-year Interval Inservice Inspection Program Plan & Associated Requests for Relief for Catawba Nuclear Station Unit 1Incorporated by reference
Unidentified leakage
ML20149K82829 July 1997SER Granting Request for Exemption from Requirements of 10CFR70.24 for Units 1 & 2
ML20141E11216 June 1997Safety Evaluation Approving Licensee Position That UFSAR Table 6-77 Be Revised to Identify SA-1 & SA-4 Instead of SA-3 & SA-6 as Containment Isolation ValvesLocal Leak Rate Testing
Excess Flow Check Valve
Exemption Request
ML20148H2505 June 1997Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp
ML20141G67020 May 1997Safety Evaluation Accepting Proposed Alternative Use of TS Requirement for Code Class SnubbersIncorporated by reference
ML20135B30527 February 1997Safety Evaluation Granting Second 10 Yr ISI Program Plan & Associated Requests for ReliefIncorporated by reference
ML20134P24220 February 1997Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications
ML20134L40819 November 1996SER Accepting Performance of Plant Standby Nuclear Svc Water PondUltimate heat sink
ML20134G5557 November 1996Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel
ML20129E4851 October 1996Safety Evaluation Recommending That Relief Request 96-02 Be Granted,Per 10CFR50.55a(g)(6)(i),per RequestIncorporated by reference
ML20056D96130 July 1993SER Accepting Licensee 930325-0429 Submittals of Technical Info to Support Continued Operation of Facility for Remainder of Fuel Cycle 7Stress corrosion cracking
Operational leakage
ML20055H91527 July 1990Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generators Tubes
ML20248C0733 August 1989Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants
ML20246L42212 May 1989Safety Evaluation Supporting Revs 15 & 6 to Pump & Valve Inservice Testing Program & Relief RequestsUltimate heat sink
Cold shutdown justification
ML20150C26528 June 1988Safety Evaluation Supporting Licensee Assessment to Fracture Toughness Requirements for Protection Against PTS Events,Per 10CFR50.61
ML20150C26128 June 1988Safety Evaluation Supporting Licensee Assessment to Fracture Toughness Requirements for Protection Against PTS Events,Per 10CFR50.61
ML20154H21718 May 1988Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program
ML20148H10022 January 1988Safety Evaluation Supporting Util 871113 Proposed Tech Spec Changes Reflecting Unit 2 Cycle 2 Refueling & Addition of Boron Dilution Mitigation Sys for Unit 2Shutdown Margin
ML20236M9636 November 1987Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec IssueAnticipated operational occurrence
ML20236D44530 September 1987SER Re Licensee 870814 & 21 Responses Re Single Failure Potential in Nuclear Svc Water Sys.Nuclear Svc Water Sys Meets Requirements of GDC 5 & 44 Re Sharing & Provisions for Suitable Redundancy in Cooling Water SysUltimate heat sink
ML20236F58829 July 1987Safety Evaluation Supporting Util 831104,841102,1231 & 851203 Responses to Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 of Generic Ltr 83-28
ML20215D27011 June 1987SER Accepting Rev 13 to Unit 1 & Rev 4 to Unit 2 Pump & Valve Inservice Testing,Per Generic Ltr 83-28,Item 2.1 (Part 2)
ML20214T4062 June 1987Safety Evaluation Supporting Util 860424 Submittal Re Turbine Sys Maint Program for Early Detection of Cracking in Low Pressure Turbine WheelsStress corrosion cracking
Turbine Missile
Coast down
Overspeed trip
ML20214M33622 May 1987Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics TestingShutdown Margin
ML20209B15128 January 1987SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing
ML20207Q58515 January 1987SER Re Generic Ltr 83-28,Item 2.1 (Part 2) Concerning Vendor Interface Programs for Reactor Trip Sys Components.Util Response Acceptable.Item Closed
ML20207N3018 January 1987Safety Evaluation on Util 830309 & 851025 Requests for Relief from 10CFR50.55a Requirements Re Pump & Valve Inservice Testing Program.Relief Granted W/Listed Exceptions
ML20207P63431 August 1986Safety Evaluation Accepting Util 851120 & 860324 Proposals to Eliminate Arbitrary Intermediate Pipe Breaks in Select List of High Energy Piping SysStress corrosion cracking
Thermal fatigue
ML20199L3942 July 1986SER Providing Final Conclusions & Recommendations from Evaluation of Tdi Owners Group Program to Validate & Update Quality of Tdi Diesel GeneratorsEddy Current Testing
Liquid penetrant
Overspeed trip
ML20211E42510 June 1986Draft SER Re Util 850624 Response to Generic Ltr 83-28,Items 4.1,4.2.1 & 4.2.2 Re Preventive Maint Program for Reactor Trip Breakers/Maint & Trending.Position on Item 4.1 Acceptable.Position on Items 4.2.1 & 4.2.2 Unacceptable
ML20207T42430 December 1985SER Re SPDS Based on Documentation & 850513-15 Audit.Spds Does Not Fully Meet Requirements of Suppl 1 to NUREG-0737. Five Listed Variables Should Be Added to Spds.Interim Implementation Acceptable
ML20138M90117 December 1985Draft SER on Util 850329 Response to 841003 Request for Addl Info Re Hydrogen Control Measures for Plant.Addl Info & Analyses Required Re Effect of Upper Compartment Burns on Air Return FanOverspeed trip
ML20128F99221 June 1985SER Based on Util 831104 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program Description & Procedures. Program & Procedures Acceptable