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Issue date | Title | |
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ML20010A232 | 30 July 1981 | Significant Deficiency Rept SD 413-414/81-14 Re Linear Indications in Base Metal of 1-inch Socket Welds,Initially Reported on 810630.Defective Piping Will Be Replaced.Pipes Will Be Evaluated for Higher Pressure & Temp Svc |
ML20042F761 | 31 October 1989 | 1989 10CFR50.59 Rept, Consisting of Mods,Exempt Change Verification Notices,Procedure Changes,Tests & Experiments Completed for Jan-Oct 1989.W/900501 Ltr |
ML20059L065 | 26 January 1994 | Summary of 931201 Meeting W/Util in Rockville,Md Re Presentation by Licensee on SG Replacement Project. Attendees Listed in Encl 1 |
ML20065M797 | 6 December 1990 | Forwards Recalculated Wear Prediction,Per NRC Bulletin 88-009 Re in-core Instrument Guide Thimble Wear Exam.New Prediction Indicates Thimbles Should Be Reexamined at End-of-Cycle 6 Instead of End-of-Cycle 5 |
ML20070V110 | 1 April 1991 | Forwards Summary of Mods,Exempt Change Variation Notices, Procedure Changes,Tests & Experiments for Nov 1989 - Sept 1990 |
ML20071M351 | 18 May 1983 | Informs of Plans to Perform Mods to Westinghouse Model D2/D3 Steam Generators Per SER (NURE-0966) Issued on 830316.Plant-specific Mod Details Encl |
ML20073J915 | 19 September 1994 | Replacement Steam Generator Topical Rept |
ML20078F657 | 8 November 1994 | Responds to Violations Noted in Insp Repts 50-413/94-17 & 50-414/94-17.Corrective Actions:Reviews Conducted to Ensure Violation Examples Do Not Compromise Ability of Affected Structures,Sys or Components |
ML20079N423 | 25 July 1990 | Response to NUMARC Aquatic Resource Questions |
ML20080J929 | 16 February 1995 | Forwards W Topical Rept WCAP-14277, Slb Leak Rate & Tube Burst Probability Analysis Methods for ODSCC at TSP Intersections |
ML20086A849 | 26 June 1995 | Provides Unit 1 Summary Rept Re 630 Vs 610 Bobbin Probe Comparison & Analyst Error Assessment |
ML20086F471 | 30 June 1995 | Interim Plugging Criteria 90 Day Rept |
ML20087Q044 | 5 April 1984 | Forwards Description of Extended Operation Tests & Insp Plans for Diesel Generators 1A & B & Description of Generic & site-specific Problems,Per 840321 Meeting Re Resolution of Transamerica Delaval,Inc Diesel Generator Issue |
ML20090A244 | 6 July 1984 | Submits Plans for Insp of Tdi Diesel Engine 1B & Return to Svc Testing of Engine 1A Following Reassembly After Insp. Vital Engine Parameters Will Be Monitored on 15-minute Basis During 1 H Run at Power to Assure Proper Operation |
ML20091C701 | 30 July 1991 | Forwards Response to NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Reactors |
ML20093F242 | 16 July 1984 | Forwards Applicant to NRC Describing Diesel Engine 1B Insp.Ltr Also Provides NRC W/Applicant Plans for Return to Svc Testing of Diesel Engine.Related Correspondence |
ML20094P561 | 1 April 1992 | Submits 1991 10CFR50.59 Summary of Nuclear Station Mods, Exempt Change Variation Notices,Changes to Selected License Commitment Manual,Procedure Changes,Tests & Experiments from Oct 1990 to Sept 1991 |
ML20095G814 | 18 August 1984 | Testimony of Gw Hallman,Rp Muschick,Sr Ward,Ja Gorman, CA Wells,La Swanger,Sk Chen,Jo Barbour,Jm Curtis & Rc Gamberg Re Problems Encountered in Diesel Generator Qualification Program.Related Correspondence |
ML20098D634 | 19 May 1992 | Proposed TS 4.4.5.4 Re Acceptance Criteria for RCS |
ML20106A289 | 16 September 1992 | Requests That Proprietary WCAP-13494, Catawba Unit 1 Technical Support for Steam Generator Interim Tube Plugging Criteria for Indications at Tube Support Plates, Be Withheld (Ref 10CFR2.790).Affidavit CAW-92-356 Encl |
ML20106E914 | 2 April 2020 | 1 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant and Connected Systems |
ML20106E950 | 2 April 2020 | 1 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities |
ML20114B409 | 24 August 1992 | Proposed TS 3/4.4.5 Re Insp Frequencies for SG Tubes & 3/4.4.4.6 Re Operational Leakage for RCS |
ML20128E974 | 21 June 1985 | Submits Util Conclusions of Tdi Generator Owners Group Design Review/Quality Revalidation Rept for Facility Diesel Generators.Summary of Differences Between Util & Owners Group Recommendations for Unit 1 Diesels Encl |
ML20134H257 | 23 August 1985 | Discusses Util Action to Resolve Outstanding Items on Cylinder Heads for Tdi Diesel Generators.Util Developed eddy-current Test for Use W/Visual Insp to Detect Partial Penetration Plug Welds in Cylinder Heads |
ML20138L775 | 17 December 1985 | Forwards Rev 14 to FSAR to Aid in NRC Review of FSAR Re Licensing of Unit 2.Rev Will Be Submitted as Amend 36 to Application for Licenses in Jan 1986 |
ML20138P480 | 17 December 1985 | Diesel Engine 2B Component Revalidation Insp |
ML20148E687 | 18 March 1988 | Notice of Violation from Insp on 880202-04.Violation Noted: Failure to Establish Adequate Measures to Control Eddy Current Testing of Steam Generator Tubes |
ML20148F944 | 23 May 1997 | Insp Repts 50-413/97-07 & 50-414/97-07 on 970323-0426. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support |
ML20150C270 | 29 February 1988 | Monthly Operating Repts for Feb 1988 |
ML20151N729 | 14 April 1988 | Responds to Violations Noted in Insp Repts 50-413/88-09 & 50-414/88-09.Corrective Action:Violation Result of Personnel Errors Made in Interpretation of Eddy Current Test Data. Measures to Control & Accomplish NDT Adequate |
ML20151U569 | 6 February 1986 | Forwards Revised Pages of Preservice Insp Program,Reflecting Requested Insps of 20 Welds of Containment Spray Sys,Per Sser 2 (Confirmatory Issue 11) |
ML20153D294 | 25 April 1988 | Advises That Reevaluation of Unit 1 Eddy Current Testing Results Ref in Insp Rept 50-413/88-08 & 50-414/88-08 Will Be Concluded by 880531 |
ML20154M443 | 28 February 1986 | Safety Evaluation Report Related to the Operation of Catawba Nuclear Station,Units 1 and 2.Docket Nos. 50-413 and 50-414.(Duke Power Company,Et Al) |
ML20197G155 | 18 December 1997 | Application for Amends to Licenses NPF-35 & NPF-52,deleting Existing License Conditions Which Have Been Fulfilled by Completed Duke Actions,Changing Other Sections Which Have Been Superseded by Current Plant Status |
ML20198B570 | 28 February 1985 | Rev 1 to Tdi Diesel Generator Design Review & Quality Revalidation Rept, Vols 1-4 |
ML20198C577 | 14 May 1986 | Transcript of 860514 Discussion/Possible Vote on Full Power OL for Catawba 2 in Washington,Dc.Pp 1-86.Viewgraphs Encl |
ML20198J407 | 30 April 1986 | Rev 1 to Catawba Nuclear Station Diesel Engine 2A Component Revalidation Insp |
ML20199L394 | 2 July 1986 | SER Providing Final Conclusions & Recommendations from Evaluation of Tdi Owners Group Program to Validate & Update Quality of Tdi Diesel Generators |
ML20203L630 | 9 February 1998 | Insp Repts 50-413/97-15 & 50-414/97-15 on 971123-980110. Violations Noted.Major Areas Inspected:Operations,Maint & Plant Support |
ML20234C624 | 9 September 1987 | Insp Repts 50-413/87-25 & 50-414/87-25 on 870709-0825. Violations Noted.Major Areas Inspected:Plant Operations, Containment Integrity Verification,Surveillance Operation, Maint Observation & LERs |
ML20235V427 | 31 August 1987 | Nonproprietary Tubesheet Region Plugging Criterion for Duke Power Co,Catawba 1,Nuclear Station Steam Generators |
ML20236A224 | 25 February 1989 | Resident Insp Repts 50-413/88-38 & 50-414/88-38 on 881127-890204.One Strength,One Weakness & One Apparent Violation Identified.Major Areas Inspected:Plant Operations, Surveillance Testing,Maint Observation & Procedures Review |
ML20246E758 | 31 December 1988 | Summary of Nuclear Station Mod Reportable Under 10CFR50.59 During 1988 |
ML20246L826 | 16 March 1989 | Responds to NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Reactors. Thimble Wear Does Not Appear to Be Problem at Facility |
ML21116A066 | 22 April 2021 | C2R24 Relief Request Pre-Submittal Slides Call 2 |
ML21253A082 | 20 September 2021 | Proposed Alternative Request RA-21-0145 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method |
ML21266A011 | 5 October 2021 | Staff Evaluation Related to Aging Management Program and Inspection Plan of Reactor Vessel Internals Per MRP-227, Revision 1-A |
ML21327A211 | 23 November 2021 | December 7, 2021, Pre-submittal Presentation Regarding Embedded Flaw Repair Relief Request |
ML21336A142 | 7 December 2021 | December 7, 2021, Pre-submittal Presentation Slides Regarding Embedded Flaw Repair Relief Request - Revised |