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Issue date | Title | Topic | |
---|---|---|---|
ML20199L573 | 31 October 1977 | Non-proprietary Hybrid B4C Absorber Control Rod Evaluation Rept | Shutdown Margin Fuel cladding Coast down |
ML20199L620 | 31 December 1973 | Non-proprietary Amend 1 to WCAP-8185, Ref Core Rept 17x17 Vol 1 | |
ML20202B113 | 30 April 1986 | Nonproprietary Suppl 1,Rev 3, CPC Protection Algorithm Software Change Procedure | |
ML20203H670 | 31 January 1998 | Rev 0 to non-proprietary Version of BAW-10232, OTSG Repair Roll Qualification Rept (Including Hydraulic Expansion Evaluation) | Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake Nondestructive Examination Finite Element Analysis |
ML20210K883 | 29 July 1999 | Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates | |
ML20211A103 | 30 September 1986 | Small Break LOCA Analysis for B&W 177FA Lowered Loop Plants in Response to NUREG-0737,Item II.K.3.31 | Fuel cladding |
ML20211N492 | 30 September 1997 | Rev 1 to SIR-94-080-A, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements | |
ML20215B465 | 31 January 1977 | Rev 0 to Pistar Program Verification Rept | |
ML20217L893 | 31 October 1999 | Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs | Probabilistic Risk Assessment Nondestructive Examination Large early release frequency Flow Induced Vibration |
ML20245G712 | 31 May 1989 | Submittal in Response to NRC Bulletin 88-11, 'Pressurizer Surge Line Thermal Stratification' | |
ML20246N384 | 30 April 1989 | Analysis of Capsule ANI-C,Arkansas Power & Light Co, Arkansas Nuclear One,Unit 1,Reactor Vessel Matl Surveillance Program | Hydrostatic Fuel cladding |
ML20247E323 | 30 June 1989 | Nonproprietary Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for C-E 16x16 PWR Fuel | Nondestructive Examination Fuel cladding |
ML20248D601 | 31 March 1998 | Suppl 9 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models | Boric Acid Fuel cladding |
ML20248F744 | 31 May 1998 | Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity |