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| Issue date | Title | Topic | |
|---|---|---|---|
| ML19327B249 | 6 October 1989 | Forwards Justification for Extension of Applicability of 890807 SER Re Acceptance of BAW-10175, Rod Exchange Methodology Topical Rept. | |
| ML20247G499 | 30 March 1989 | Forwards Proprietary BAW-10175P, Rod Exchange Methodology, Developed for Calculating Parameters While Performing Control Rod Measurements Using Rod Exchange Technique to Be Used at Plants.Rept Withheld (Ref 10CFR2.790) | |
| ML20235M897 | 10 February 1989 | Requests Withholding of Proprietary WCAP 12125, Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue, Per 10CFR2.790 | |
| ML20205Q633 | 2 November 1988 | Forwards Revised Proprietary Pages to BAW-10164P, RELAP5/Mod2-B&W,Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis. Cso Film Boiling Correlation Replaced w/Condie-Bengston IV Correlation & Typos Corrected | |
| ML20195B609 | 21 October 1988 | Forwards Summary of B&W Fuel Co Position Re Small Break LOCA Calculations Contained in Util FSARs for Upcoming Reload Cores Which Will Contain Fuel Mfg by B&W | Loop seal |
| ML20151H938 | 25 July 1988 | Forwards Proprietary BAW-10168P, B&W LOCA Evaluation Model for Recirculating Steam Generator Plants | |
| ML20151F766 | 29 March 1988 | Forwards Updated Pages to Proprietary BAW-10171P, REFLOD3B- Model for Multinode Core Reflooding Analysis, Per ECCS Methodology for Facilities Reloads.Mod Removes Henry Quench Temp Criteria & Potential Conflict in Logic.Pages Withheld | |
| ML20234C223 | 28 December 1987 | Forwards Proprietary BAW-10164P, RELAP5/MOD2-B&W,Advanced Program for LWR LOCA & Non-LOCA Transient Analysis. Rept Describes Computer Code Used to Analyze RCS Behavior During Blowdown Phase of LOCA Transient.Rept Withheld | |
| ML20234D110 | 14 December 1987 | Forwards Proprietary BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis. Rept Describes Computer Code That B&W Will Be Using to Analyze RCS Behavior During Refill of LOCA Transient.Rept Withheld | |
| ML20236C026 | 22 October 1987 | Forwards Proprietary BAW-10165P, FRAP-T6-B&W:Computer Code for Transient Analysis of LWR Fuel Rods. Rept Describes Computer Code That B&W Will Be Using for Future Transient Analyses of LWR Fuel Rods.Rept Withheld (Ref 10CFR2.790) | |
| ML20235T974 | 22 September 1987 | Requests That Encl Proprietary Rev 2 to WCAP-11308, RTD Bypass Elimination Licensing Rept for Catawba Units 1 & 2 Be Withheld (Ref 10CFR2.790) | Affidavit |
| ML20235V381 | 16 September 1987 | Requests Proprietary Responses for Amend to Tech Specs Re Adoption of Tube Sheet Region Plugging Criterion Be Withheld (Ref 10CFR2.790).Justification & Discussion of NSHC Encl | Affidavit |
| ML20236H497 | 29 July 1987 | Forwards Draft Proprietary Topical Rept BAW-10166P, Beach Computer Code for Reflood Heat Transfer During Loca. Draft Submitted to Permit Interaction Between B&W,Nrc & Util. Affidavit for Withholding Encl.Fee Paid | |
| ML20236B414 | 13 July 1987 | Forwards Proprietary Draft 1 of BAW-10168P, ...B&W LOCA Evaluation Model for Recirculating Steam Generator Plants, to Be Used for LOCA Analysis of Catawba & McGuire Reload Fuel Cycles.Rept Withheld (Ref 10CFR2.790).Fee Paid | |
| ML20235B659 | 2 July 1987 | Forwards Part 21 Rept Re Consolidated 3787WA Safety Valve Spring Failure for Plant,Per Request | |
| ML20235Z549 | 21 May 1987 | Requests Proprietary Classification for Resistance Temp Detector Bypass Elimination Rept & Support Documentation,Per 10CFR2.790 | Affidavit |
| ML20212R471 | 15 April 1987 | Forward Proprietary Draft 1 to BAW-10171P, REFLOD3B,Model for Multinode Core Reflooding Analysis, for Review of ECCS Methodology for Plants Fuel Reloads,Per . W/Affidavit.Draft Withheld (Ref 10CFR2.790).Fee Paid | |
| ML20206E785 | 2 April 1987 | Confirms Intention to Use FOAM2 Computer Program as Part of ECCS Evaluation Model for Westinghouse Designed Plants. Review of Applicability of Code to Westinghouse Designed Plants Requested Prior to 880701 | |
| NRC-87-3194, Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted | 7 January 1987 | Documents 861231 Telcon Re Anomalous Plant Data at Callaway & Wolf Creek.Investigation Initiated.Data Specs for McGuire, Catawba & Millstone Will Be Transmitted | |
| ML20213H015 | 14 November 1986 | Forwards Proprietary Draft 1 to BAW-10165P, FRAP-T6-B&W Computer Code for Transient Analysis of LWR Fuel Rods. Rept Submitted to Permit Interaction Between NRC & B&W to Support Util Schedule Needs.Rept Withheld (Ref 10CFRF2.790) | |
| ML20203M632 | 29 August 1986 | Forwards Proprietary Draft 1 to BAW-10164P, RELAP/MOD2 - B&W.Advanced Computer Program for LWR LOCA & Non-LOCA Transient Analysis, Per 860714 Licensing Plan for ECCS Methodology.Rept Withheld (Ref 10CFR2.790).Affidavit Encl | |
| ML20198J462 | 23 May 1986 | Forwards Proposed Licensing Plans for Safety/Eccs Analysis Submittals for Facility Reloads.Comparison W/Original Licensing Plans Provided | |
| NRC-85-3081, Forwards Proprietary WCAP-10988 & Nonproprietary WCAP-10989, COBRA-NC,Analysis of Main Steam Line Break in Catawba Unit 1 Ice Condenser Containment. Proprietary Version Withheld (Ref 10CFR2.790) | 27 November 1985 | Forwards Proprietary WCAP-10988 & Nonproprietary WCAP-10989, COBRA-NC,Analysis of Main Steam Line Break in Catawba Unit 1 Ice Condenser Containment. Proprietary Version Withheld (Ref 10CFR2.790) | Affidavit |
| ML20137Z528 | 27 November 1985 | Requests Withholding Proprietary WCAP-10988, COBRA-NC, Analysis of Main Steam Line Break in Catawba Unit 1 Ice Condenser Containment, (Ref 10CFR2.790(b)(1)) | Affidavit |
| ML20134D568 | 31 July 1985 | Requests Withholding of Proprietary Main Steam Line-Break- Superheat, Per 10CFR2.790 | Affidavit |
| ML20094D162 | 20 July 1984 | Requests Withholding of Proprietary Westinghouse Setpoint Methodology for Protection Sys,Catawba Station (Ref 10CFR2.790) | Affidavit |
| ML20092N573 | 13 June 1984 | Requests Withholding Proprietary Matl,Per 10CFR2.790. Affidavit CAW-83-80 Encl | Affidavit |
| ML20091E446 | 22 May 1984 | Requests Withholding of Referenced Proprietary Info from Public Disclosure (Ref 10CFR2.790).JD Mcadoo 830926 Affidavit Encl | Affidavit |
| ML20092H681 | 4 May 1984 | Requests Withholding Proprietary Info Per 10CFR2.790. Affidavit CAW-83-80 Encl | Affidavit |
| ML20084N918 | 1 May 1984 | Requests Withholding Proprietary WCAP-10546, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Catawba Units 1 & 2 Per 10CFR2.790. Affidavit CAW-83-80 Encl | Pressure Boundary Leakage Affidavit |
| ML20083M822 | 9 April 1984 | Requests Proprietary Matl Transmitted by Util Be Withheld,Per 10CFR2.790.Affidavit CAW-76-60 Encl | Affidavit |
| ML20087M625 | 26 March 1984 | Requests Proprietary Methodology for Addressing Superheated Steam Releases to Ice Condenser Containments, Be Withheld from Public Disclosure Per 10CFR2.790 | Affidavit |
| ML20087G322 | 15 February 1984 | Application for Withholding Proprietary Rept WCAP-10487, Technical Basis for Eliminating Pressurizer Surge Line Ruptures as Structural Design Basis | Pressure Boundary Leakage Affidavit |
| ML20083F263 | 23 November 1983 | Requests Withholding Proprietary Info Re Technical Bases for Eliminating Large Primary Loop Pipe Ruptures from Public Disclosure (Ref 10CFR2.790).Affidavit CAW-83-80 Encl | Pressure Boundary Leakage Affidavit |
| ML20072B072 | 18 January 1983 | Application for Withholding Proprietary Supplemental Response to NRC Question 492.2 on Improved Thermal Design Procedures.Affidavit Encl.Response Withheld (Ref 10CFR2.790) | Affidavit |
| ML20064J383 | 7 January 1983 | Forwards Proprietary & Nonproprietary Reactor Cavity Asymmetric Loads & Requests Withholding of Proprietary Version (Ref 10CFR2.790) | Affidavit |
| ML20070C674 | 2 December 1982 | Requests Westinghouse Proprietary Matl in Util Submittal Re Improved Thermal Design Procedures Be Withheld (Ref 10CFR2.790).Affidavit Encl | Affidavit |
| ML20069B523 | 25 November 1981 | Forwards Rept Supporting Conclusion That Addl Testing of CRDM Adapter Welds That Cannot Be re-radiographed Is Unnecessary.Where First Round Radiography Deemed Not Interpretable,Second Round Revealed Acceptable Welds | |
| ML19269H439 | 16 July 1980 | Forwards Final Rept Re Potential Problem in safety-related Overcurrent Relays.Problem Was Random in Nature & Not Generic | |
| ML20126B934 | 12 February 1980 | Confirms 800207 Telcon Re Failure of Valves.Forwards Part 21 Rept | |
| ML19210E249 | 29 October 1979 | Forwards Rept Weld Matl Documentation of Eleven Reactor Pressure Vessels Fabricated by Rdm for Westinghouse, in Response to IE Bulletin 78-12.Complete Records Search Made & No Atypical Weld Matl Found | |
| ML19249B549 | 8 June 1979 | Forwards Info Requested by IE Bulletin 78-12,Atypical Weld Matl in Reactor Pressure Vessel Welds Which Addresses All Applicable Matls Used in Fabrication of Reactor Vessels. W/O Encl | |
| ML20235T986 | 1 December 1976 | Requests That Proprietary Rept WCAP-8567-P, Improved Thermal Design Procedure Be Withheld (Ref 10CFR2.790). Affidavit Encl | Affidavit |