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Issue date | Title | Topic | |
---|---|---|---|
ML20211A979 | 20 August 1999 | Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 | Incorporated by reference |
ML20209E436 | 9 July 1999 | SER 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 | |
ML20196K663 | 7 July 1999 | Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers | Operability Determination |
ML20206P520 | 14 May 1999 | Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves | Stroke time Power Uprate |
ML20205S555 | 21 April 1999 | Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions | |
ML20205N365 | 12 April 1999 | Safety Evaluation Accepting IPE of External Events Submittal | Fire Barrier Internal Flooding Probabilistic Risk Assessment Earthquake |
ML20196J835 | 8 December 1998 | Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys | |
ML20196C025 | 27 November 1998 | SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station | |
ML20196A688 | 25 November 1998 | Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds | Hydrostatic VT-2 Unidentified leakage |
ML20247M086 | 21 May 1998 | SER 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 | |
ML20216E177 | 13 April 1998 | Safety 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 | |
ML20217M421 | 3 April 1998 | Safety 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 Days | Through-Wall Leakage Operability Assessment |
ML20199A552 | 22 January 1998 | Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, for Cns,Units 1 & 2 | Safe Shutdown Power-Operated Valves Backfit |
ML20199A642 | 22 January 1998 | Safety 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 |
ML20198P964 | 15 January 1998 | SE Granting Relief Request 97-03 for Second 10-yr Interval Inservice Insp Program | Incorporated by reference |
ML20198R995 | 30 October 1997 | Safety 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 |
ML20198J765 | 15 October 1997 | Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units | VT-2 Incorporated by reference |
ML20211F880 | 22 September 1997 | Safety Evaluation Supporting Second ten-year Interval Inservice Inspection Program Plan & Associated Requests for Relief for Catawba Nuclear Station Unit 1 | Incorporated by reference Unidentified leakage |
ML20149K828 | 29 July 1997 | SER Granting Request for Exemption from Requirements of 10CFR70.24 for Units 1 & 2 | |
ML20141E112 | 16 June 1997 | Safety 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 Valves | Local Leak Rate Testing Excess Flow Check Valve Exemption Request |
ML20148H250 | 5 June 1997 | Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp | |
ML20141G670 | 20 May 1997 | Safety Evaluation Accepting Proposed Alternative Use of TS Requirement for Code Class Snubbers | Incorporated by reference |
ML20135B305 | 27 February 1997 | Safety Evaluation Granting Second 10 Yr ISI Program Plan & Associated Requests for Relief | Incorporated by reference |
ML20134P242 | 20 February 1997 | Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications | |
ML20134L408 | 19 November 1996 | SER Accepting Performance of Plant Standby Nuclear Svc Water Pond | Ultimate heat sink |
ML20134G555 | 7 November 1996 | Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel | |
ML20129E485 | 1 October 1996 | Safety Evaluation Recommending That Relief Request 96-02 Be Granted,Per 10CFR50.55a(g)(6)(i),per Request | Incorporated by reference |
ML20056D961 | 30 July 1993 | SER Accepting Licensee 930325-0429 Submittals of Technical Info to Support Continued Operation of Facility for Remainder of Fuel Cycle 7 | Stress corrosion cracking Operational leakage |
ML20055H915 | 27 July 1990 | Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generators Tubes | |
ML20248C073 | 3 August 1989 | Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants | |
ML20246L422 | 12 May 1989 | Safety Evaluation Supporting Revs 15 & 6 to Pump & Valve Inservice Testing Program & Relief Requests | Ultimate heat sink Cold shutdown justification |
ML20150C265 | 28 June 1988 | Safety Evaluation Supporting Licensee Assessment to Fracture Toughness Requirements for Protection Against PTS Events,Per 10CFR50.61 | |
ML20150C261 | 28 June 1988 | Safety Evaluation Supporting Licensee Assessment to Fracture Toughness Requirements for Protection Against PTS Events,Per 10CFR50.61 | |
ML20154H217 | 18 May 1988 | Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program | |
ML20148H100 | 22 January 1988 | Safety Evaluation Supporting Util 871113 Proposed Tech Spec Changes Reflecting Unit 2 Cycle 2 Refueling & Addition of Boron Dilution Mitigation Sys for Unit 2 | Shutdown Margin |
ML20236M963 | 6 November 1987 | Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue | Anticipated operational occurrence |
ML20236D445 | 30 September 1987 | SER 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 Sys | Ultimate heat sink |
ML20236F588 | 29 July 1987 | Safety 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 | |
ML20215D270 | 11 June 1987 | SER 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) | |
ML20214T406 | 2 June 1987 | Safety Evaluation Supporting Util 860424 Submittal Re Turbine Sys Maint Program for Early Detection of Cracking in Low Pressure Turbine Wheels | Stress corrosion cracking Turbine Missile Coast down Overspeed trip |
ML20214M336 | 22 May 1987 | Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing | Shutdown Margin |
ML20209B151 | 28 January 1987 | SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing | |
ML20207Q585 | 15 January 1987 | SER Re Generic Ltr 83-28,Item 2.1 (Part 2) Concerning Vendor Interface Programs for Reactor Trip Sys Components.Util Response Acceptable.Item Closed | |
ML20207N301 | 8 January 1987 | Safety Evaluation on Util 830309 & 851025 Requests for Relief from 10CFR50.55a Requirements Re Pump & Valve Inservice Testing Program.Relief Granted W/Listed Exceptions | |
ML20207P634 | 31 August 1986 | Safety Evaluation Accepting Util 851120 & 860324 Proposals to Eliminate Arbitrary Intermediate Pipe Breaks in Select List of High Energy Piping Sys | Stress corrosion cracking Thermal fatigue |
ML20199L394 | 2 July 1986 | SER Providing Final Conclusions & Recommendations from Evaluation of Tdi Owners Group Program to Validate & Update Quality of Tdi Diesel Generators | Eddy Current Testing Liquid penetrant Overspeed trip |
ML20211E425 | 10 June 1986 | Draft 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 | |
ML20207T424 | 30 December 1985 | SER 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 | |
ML20138M901 | 17 December 1985 | Draft 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 Fan | Overspeed trip |
ML20128F992 | 21 June 1985 | SER Based on Util 831104 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program Description & Procedures. Program & Procedures Acceptable |