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	Issue date	Title	Topic
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
ML20210K883	29 July 1999	Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates
ML20196A625	31 May 1999	Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs	Non-Destructive Examination Probabilistic Risk Assessment Large early release frequency Flow Induced Vibration
ML20248F744	31 May 1998	Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML20248D601	31 March 1998	Suppl 9 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models	Boric Acid Fuel cladding
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
ML20199G953	31 January 1998	Non-proprietary Alternate Repair Criteria for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once- Through Sgs
ML20211N492	30 September 1997	Rev 1 to SIR-94-080-A, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements
ML20135F368	30 November 1996	Non-proprietary Final Rept Repair of 3/4 O.D. SG Tubes Using Leak Tight Sleeves	Non-Destructive Examination Safe Shutdown Earthquake Hydrostatic Nondestructive Examination
ML20112E849	28 February 1996	Suppl 7 to Annual Rept of Abb C-E ECCS Performance Evaluation Models	Fuel cladding
ML17353A434	31 October 1995	Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range.
ML17264A118	31 July 1995	Response to Part (1) of GL 92-01,Rev 1,Suppl 1.
ML20083Q926	30 May 1995	Joint Applications Rept for Safety Injection Tank Aot/Sti Extension	Boric Acid Maintenance Rule Program
ML20083Q986	30 May 1995	Joint Applications Rept for Emergency Diesel Generators AOT Extension	Safe Shutdown Mission time Maintenance Rule Program Offsite Circuit
ML20085H322	28 February 1995	Suppl 6 to Topical Rept CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models,Final Rept,Ceog Task 865, Dtd Feb 1995	Fuel cladding
ML20073D456	30 September 1994	Verification of Cecor Coefficient Methodology for Application to PWRs of Entergy Sys
ML20069D426	28 February 1994	Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46	Fuel cladding
ML20063C757	31 December 1993	Qualification of Reactor Methods for Pressurized Water Reactors of Entergy Sys	Shutdown Margin
ML20081K982	31 May 1991	Final Rept on Reactor Vessel App G Pressure-Temp Limits for Arkansas Nuclear One Unit 2 for 21 Efpys	Hydrostatic
ML20067A524	31 December 1990	Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.'	Operating Basis Earthquake Finite Element Analysis Code Reconciliation Commercial Grade Power change
ML20042F339	30 April 1990	Suppl 1 to Responses to Questions on C-E Rept CEN-386-P, 'Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for C-E 16X16 PWR Fuel.'	Fuel cladding
ML20059M448	31 March 1990	Unit 1 Pressure-Temp Limits for 15 Efpy	Hydrostatic
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
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
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
ML20155J491	31 May 1986	Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block	Anticipated operational occurrence
ML20155J505	31 May 1986	Rev 1 to Functional Design Requirements for Control Element Assembly Calculator	Anticipated operational occurrence
ML20155J523	31 May 1986	Rev 1 to Functional Design Requirement for Core Protection Calculator	Anticipated operational occurrence
ML20202B113	30 April 1986	Nonproprietary Suppl 1,Rev 3, CPC Protection Algorithm Software Change Procedure
ML20151Z052	31 January 1986	Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure
ML20151Z064	31 January 1986	Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines
ML20135A557	31 August 1985	B&W Owners Group Cavity Dosimetry Program
ML20134N302	31 July 1985	Rev 00 to Functional Design Requirement for Core Protection Calculator	Anticipated operational occurrence
ML20134N294	31 July 1985	Rev 00 to Functional Design Requirement for Control Element Assembly Calculator	Anticipated operational occurrence
ML20129F930	31 July 1985	Cycle 5 Shoulder Gap Evaluation
ML20100J155	31 March 1985	Nonproprietary Typical Data Base Constants for Arkansas Nuclear One Unit 2
ML20100J180	31 March 1985	Nonproprietary Rev 0 to Arkansas Nuclear One - Unit 2 Core Protection Calculator Sys Phase I Design Qualification Test Rept
ML20100J199	31 March 1985	Nonproprietary Rev 0 to Arkansas Nuclear One - Unit 2 Core Protection Calculator & Control Element Assembly Calculator Data Base Listing
ML20100J222	31 March 1985	Nonproprietary Rev 1 to Core Protection Calculator/Control Element Assembly Calculator Sys Phase II Software Verification Test Rept
ML20101U355	31 December 1984	Nonproprietary Revised Rod Bow Penalties for Arkansas Nuclear One Unit 2
ML20106E325	31 October 1984	Nonproprietary Once-Through Steam Generator Mechanical Sleeve Qualification	Safe Shutdown Earthquake Hydrostatic Operating Basis Earthquake
ML20107N022	31 October 1984	Nonproprietary CPC Methodology Changes for Arkansas Nuclear One Unit 2 Cycle 5
ML20094J710	31 July 1984	Analyses of Capsule AN1-A,Arkansas Power & Light Co, Arkansas Nuclear One,Unit 1,Reactor Vessel Matl Surveillance Program	Hydrostatic
ML20098F136	30 April 1984	Thermal-Hydraulic Crossflow Applications	Anticipated operational occurrence
ML20083G532	30 November 1983	Cycle 4 Shoulder Gap Evaluation
ML20087N254	30 November 1983	Nonproprietary Shoulder Gap Data Taken on Batch D Assemblies After Cycle 3. Info Deleted
ML20066D224	31 March 1982	Effects of Vessel Head Voiding During Transients & Accidents in C-E Nsss. Portions Intentionally Deleted Due to Lack of Relevancy to NUREG-0737,Item II.K.2.17.Util Did Not Participate in Development of Deleted Sections
ML20039F868	31 December 1981	Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for AR Nuclear One- Unit 2 Reactor Vessel.
ML20009F202	31 July 1981	Nonproprietary Version of Response to Questions on Documents Supporting ANO-2,Cycle 2,License Submittal, Amend 2-NP

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