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FOIA/PA-2005-0108 - Resp 1 - Final.
Accession Number: ML051430282
Date Released: Thursday, May 26, 2005
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- ML051430287 - FOIA/PA-2005-0108 - Resp 1 - Final. (165 page(s), 5/18/2005)
- ML020430092 - WCAP-14483-A, "Generic Methodology for Expanded Core Operating Limits Report." (58 page(s), 1/19/1999)
- ML003711228 - Reactor Vessel Closure HeadIVessel Flange Requirements Evaluation for Operating PWR and BWR Plants (36 page(s), 10/31/1999)
- ML003688479 - "Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections." (266 page(s), 2/23/2000)
- ML003721105 - Supplement 11 to CENPD-279, "Annual Report on ABB CENP ECCS Performance Evaluation Models." (11 page(s), 3/31/2000)
- ML003723720 - Revision 0 of ER-160, Supplement to Topical Report ER-80P:Basis fior Power Uprate with LEFM System (35 page(s), 5/31/2000)
- ML003756317 - Revision 1 to ER-157N "Supplement to Topical Report ER-80N: Basis for:a Power Uprate With the LEFM or LEFM CheckPlus System," (14 page(s), 5/31/2000)
- ML010510372 - Caldon, Inc. Engineering Report - 160, Rev 0 "Supplement to Topical Report ER-80P: Basisd for a Power Uprate With the LEFM System," Revision 0. (12 page(s), 5/31/2000)
- ML003733112 - WCAP-15129, Revision 3, Depth-Based SG Tube Repair Criteria for Axial PWSCC At Dented TSP Intersections. (270 page(s), 6/30/2000)
- ML003750960 - Topical Report BAW-2359, "Demonstration Project to Apply Risk-Informed Inservice Testing to Air-Operated Valves." (153 page(s), 7/31/2000)
- ML003759024 - WCAP-15578 "Description of Westinghouse LOCTA JR 1-D Heat Conduction Code for LOCA Analysis of Fuel Rods" (59 page(s), 9/30/2000)
- ML010230138 - Enclosure 3 - Caldon, Inc., Engineering Report-157N - Supplement to Topical Report ER-80N: Basis for a Power Uprate With the LEFM TM or LEFM CheckPlusTM System, Revision 2. (13 page(s), 12/31/2000)
- ML010530146 - Revision 4 to BAW-10219NP, "Electrosleeving Qualification for PWR Recirculating Steam Generator Tube Repair." (334 page(s), 12/31/2000)
- ML010370382 - Addendum to WCAP-15164, Revision 1, South Texas Unit 2 3V Alternate Repair Criteria Application of Bounding Analysis and Tube Expansions (112 page(s), 1/31/2001)
- ML010580185 - WCAP-7907-SI-NP, Revision 1, LOFTRAN Code Description Supplement 1 - LOFTRAN Thick Metal Mass Heat Transfer Models. (46 page(s), 1/31/2001)
- ML010540321 - Revision 3 to ER-157N, "Supplement to Topical Report ER-80P: Basis for Power Uprate with LEFM or LEFM CheckPlus System." (22 page(s), 2/28/2001)
- ML011870482 - Attachment E, Revision 2 to WCAP-15570, "Beaver Vally Unit 1, Heatup and Cooldown Limit Curves for Normal Operation." (107 page(s), 4/30/2001)
- ML030900046 - Westinghouse Report WCAP-15203, Rev 1, "Catawba Unit 1 Heatup & Cooldown Limit Curves for Normal Operation Using Code Case N-640." (49 page(s), 4/30/2001)
- ML050190321 - WCAP-1530, Revision 1 dated April 2001 "Surry Units 1 and 2 WOG Reactor Vessel 60-Year Evaluation Mini-group Heatup and Cooldown Limit Curves for Normal Operation." (98 page(s), 4/30/2001)
- ML012190097 - Technical Justification for Eliminating Accumulator Ruptures as the Structrural Design Basis for Point Beach Units 1 and 2 Nuclear Plants. (102 page(s), 6/30/2001)
- ML012700025 - WCAP-15676, "Evaluation of Pressurized Thermal Shock fro Beaver Vally Unit 2." (20 page(s), 8/31/2001)
- ML012700153 - Revision 1 to WCAP-15699, "Tennessee Valley Authority Watts Bar Nuclear Plant Unit 1, Containment Integrity Analyses for Ice Weight Optimization Engineering Report." (142 page(s), 8/31/2001)
- ML012700227 - WCAP-15675, "Analysis of Capsule W from FirstEnergy Nuclear Operating Co Beaver Valley, Unit 2 Reactor Vessel Surveillance Program." (221 page(s), 8/31/2001)
- ML020500569 - Revision 1 to I&C/POED(01)-206, Beaver Valley, Unit 1 FirstEnergy Nuclear Operating Co, Overpressure Protection System Setpoints for Master Curve. (44 page(s), 8/31/2001)
- ML040430156 - Appendix B Supplement to Generic Licensing Topical Report EDR-1, Summary of Plant Specific Crane Data Supplied by Ederer, Inc., Palisades Spent Fuel Pool Crane. (12 page(s), 9/5/2001)
- ML012640405 - Cooper Nuclear Station Non-Proprietary Report GE NE-E1200141-04, "Decay Heat Evaluation for CNS." (12 page(s), 9/18/2001)
- ML012640451 - Cooper Nuclear Station Non-Proprietary Report GE NE-T23-00786-00-09, "Evaluation of Steam Ingestion in the ECCS Suction Strainers for Cooper Nuclear Station." (21 page(s), 9/18/2001)
- ML013250021 - Part 1, Diablo Canyon, Units 1 & 2, Transmittal of Errata Page for WCAP-15573, Revision 1 (Proprietary) & WCAP-15574, Revision 1 (Non-Proprietary), "Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections Burst Pressure..." (194 page(s), 11/14/2001)
- ML013250033 - Part 2, Diablo Canyon, Units 1 & 2, Transmittal of Errata Page for WCAP-15573, Revision 1 (Proprietary) & WCAP-15574, Revision 1 (Non-Proprietary), "Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections - Alternate Burst ..." (195 page(s), 11/24/2001)
- ML013600277 - Rev 0 to WCAP-15770, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: North Anna and Surry Units." (87 page(s), 11/30/2001)
- ML020500558 - WCAP-15624, Master Curve Fracture Toughness Application for BVPS-1. (101 page(s), 11/30/2001)
- ML020500574 - Revision 0 to WCAP-15618, Beaver Valley, Unit 1 Heatup & Cooldown Limit Curves for Master Curve Application. (52 page(s), 11/30/2001)
- ML020250541 - Appendix - H to Revision 5 to BAW-10166, "BEACH Code Benchmark at Higher Initial Cladding Temperatures." (13 page(s), 12/31/2001)
- ML020250544 - Appendix - I to Revision 5 to BAW-10166, "Revised Flooding Rate Bounds." (27 page(s), 12/31/2001)
- ML020670146 - Topical Report A-GEN-FE-0118, Revision 00, "Isotopic Number Densities for Discharged Westinghouse 17x17 Fuel Assemblies." (82 page(s), 1/31/2002)
- ML021260551 - Framatome ANP MOX Fuel Design Report BAW-10238 (NP), Rev 0. (75 page(s), 3/31/2002)
- ML022100438 - WCAP-13515, Revision 1, "Analysis of Capsule U from Indiana Michigan Power Company D. C. Cook, Unit 2 Reactor Vessel Radiation Surveillance Program." (128 page(s), 5/31/2002)
- ML022110334 - WCAP-15047, Revision 2, "D.C. Cook Unit 2 WOG Reactor Vessel 60-Year Evaluation Minigroup Heatup and Cooldown Limit Curves for Normal Operation." (61 page(s), 5/31/2002)
- ML022110339 - WCAP-13517, Revision 1, "Evaluation of Pressurized Thermal Shock for D.C. Cook Unit 2." (30 page(s), 5/31/2002)
- ML022130458 - WCAP-15902-P, Revision 0, Entitled "Conditional Extension of Rod Misalignment Technical Specification for Indian Point, Unit 2" (Proprietary). (137 page(s), 6/27/2002)
- ML023050387 - WCAP-15848-NP, Rev 0, "Fuel Rod Cladding Development Program in Palo Verde Unit 3: Examination of Fuel Rods With Advanced Cladding Materials at End-of-Cycle 9." (51 page(s), 7/31/2002)
- ML022420103 - Westinghouse Electric Company Transmittal of Westinghouse Document, "Design Process for AP1000 Common Q Safety Systems," WCAP-15927, Rev. O, Non-Proprietary, Dated August 2002. (30 page(s), 8/22/2002)
- ML022390082 - Revision 0 to WCAP-15909-NP, "Regulatory Guide 1.121 Analysis for Indian Point Unit 2 Replacement Steam Generators." (94 page(s), 8/31/2002)
- ML022560265 - Transmittal of Westinghouse Documents, "AP1000 MAAP4 Parameter File & Input Deck for Probabilistic Risk Assessment," WCAP-15938-P, Revision 0 (Proprietary) & WCAP-15938-NP, Revision 0 (Non-Proprietary) dated September 2002. (16 page(s), 9/10/2002)
- ML022600122 - WCAP-15940, "Power Calorimetric Uncertainty for 1.4-Percent Uprating for Indian Point, Unit No. 3." (18 page(s), 9/30/2002)
- ML022910436 - Westinghouse non-proprietary version of WCAP-15932-NP, Rev. 0, Improved Justification of Partial-Length RPC Inspection of Tube Joints of Model F Steam Generators of Ameren-UE Callaway Plant. (99 page(s), 9/30/2002)
- ML022940133 - WCAP-15916, Rev. 0, "Analysis of Capsule X from the Florida Power and Light Co Turkey Point Unit 3 Reactor Vessel Radiation Surveillance Program," Appendix C, Pages C-1 - C-104. (104 page(s), 9/30/2002)
- ML022940497 - WCAP-15916, Rev. 0, "Analysis of Capsule X from the Florida Power and Light Co Turkey Point Unit 3 Reactor Vessel Radiation Surveillance Program," Table of Contents - Appendix B, Page B-17. (127 page(s), 9/30/2002)
- ML042440396 - WCAP-15950, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Point Beach Units 1 and 2." (86 page(s), 9/30/2002)
- ML042920319 - "Beaver Valley Units 1 and 2 Westinghouse Series 51 Steam Generator Sleeving Report - Laser Welded Sleeves". (179 page(s), 10/31/2002)
- ML023240543 - GE Nuclear Energy Report NEDO-33063, "Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus." (97 page(s), 11/30/2002)
- ML023370583 - WCAP-15994-NP, Rev. 0, "Structural Analysis Summary for AP1000 Reactor Coolant Pump High Inertia Flywheel." (23 page(s), 11/30/2002)
- ML023370602 - WCAP-15965-NP, Rev.0, AP1000 Subcompartment Models. (31 page(s), 11/30/2002)
- ML023510433 - Power Calorimetric Uncertainty for 1.4% Uprating for Entergy Indian Point Unit 2. (18 page(s), 11/30/2002)
- ML030020548 - WCAP-15945-NP, Rev. 1, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: St. Lucie Unit 1." (109 page(s), 11/30/2002)
- ML030270472 - Revision 0 to Topical Report WCAP-15975-NP, "NDE Inspection Strategy for the Tubesheet Region in St. Lucie Unit 2." (73 page(s), 11/30/2002)
- ML032590840 - Steam Generator Tube Repair for Combustion Engineering & Westinghouse Designed Plants With 3/4 Inch Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves. (157 page(s), 11/30/2002)
- ML023370584 - Transmittal of Westinghouse Document, AP1000 Implementation of Regulatory Treatment of Nonsafety-Related Systems Process, WCAP-15985, Rev. 0, Non-Proprietary, Dated November 2002. (112 page(s), 12/2/2002)
- ML023370619 - Transmittal of Westinghouse Document, "The AP1000 Adverse System Interactions Evaluation Report," WCAP-15992, Rev.0, Non-Proprietary, Dated November 2002. (80 page(s), 12/2/2002)
- ML023400402 - Transmittal of Westinghouse Document, Evaluation of AP1000 Conformance to Inter-System Loss-of-Coolant Accident Acceptance Criteria, WCAP-15993, Rev.0, Non-Proprietary, Dated November 2002. (35 page(s), 12/2/2002)
- ML030240319 - Transmittal of Westinghouse Document, AP1000 Instrumentation & Control Defense-in-Depth & Diversity Report, WCAP-15775, Rev.1, Non-Proprietary, Dated January 2003. (39 page(s), 1/22/2003)
- ML030240386 - Transmittal of Westinghouse Document, "Operational Assessment for AP1000," WCAP-15800, Rev. 1, Non-Proprietary, dated December 2002. (159 page(s), 1/22/2003)
- ML030270062 - Letter from M. M. Corletti, Transmittal of Westinghouse Documents, "WCOBRA/TRAC AP1000 ADS-4/RWST Phase Modeling," WCAP-15833-P, Rev. 2 (Proprietary) and WCAP-15833-NP, Rev. 2 (Non-Proprietary) dated December 2002. (202 page(s), 1/22/2003)
- ML030930068 - Engineering Evaluation of Impact on Transient & Safety Analyses of Reducing Low Pressure Isolation Setpoint Analytical Limit to 785 psig Dresden Units 2 & 3 and Quad Cities Units 1 & 2. (34 page(s), 1/31/2003)
- ML031400342 - Rev 0 to WCAP-15958, "Analysis of Capsule V from Pacific Gas & Electric Co Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program," Table of Contents Through References. (83 page(s), 1/31/2003)
- ML031400347 - Rev 0 to WCAP-15958, "Analysis of Capsule V from Pacific Gas & Electric Co Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program," Appendix A Through E. (151 page(s), 1/31/2003)
- ML030580861 - Transmittal of Westinghouse Document, "AP1000 Adverse System Interactions Evaluation Report," WCAP-15992, Revision 1, Non-Proprietary, Dated February 2003. (81 page(s), 2/25/2003)
- ML030660170 - WCAP-16012, Rev. 0, "Analysis of Capsule W-83 from Dominion Nuclear Connecticut Millstone Unit 2 Reactor Vessel Radiation Surveillance Program," Appendix A - D. (154 page(s), 2/28/2003)
- ML030710172 - WCAP-16012, Rev. 0, "Analysis of Capsule W-83 from Dominion Nuclear Connecticut Millstone Unit 2 Reactor Vessel Radiation Surveillance Program," Table of Contents - Section 8. (90 page(s), 2/28/2003)
- ML030800436 - Non-Proprietary Version of GE Report GE-NE-0000-7456-01, "Option B Scram Times for Clinton Power Station." (17 page(s), 2/28/2003)
- ML030990253 - WCAP-16001, Rev 0, "Analysis of Capsule Y from Dominion Surry Unit 2 Reactor Vessel Radiation Surveillance Program," Attachment 1, Appendix A and B. (119 page(s), 2/28/2003)
- ML031910661 - WCAP-16019-NP, Rev 0, "Technical Justification for Eliminating 10" Accumulator Lines Rupture as the Structural Design Basis for Callaway Nuclear Power Plant." (70 page(s), 2/28/2003)
- ML031910667 - WCAP-16020-NP, Rev 0, "Technical Justification for Eliminating 12" Residual Heat Removal (RHR) Lines Rupture as the Structural Design Basis For Callaway Nuclear Power Plant." (52 page(s), 2/28/2003)
- ML031910677 - WCAP-15983-NP, Rev 0, "Technical Justification for Eliminating Pressurizer Surge Line Rupture as the Structural Design Basis for the Callaway Nuclear Power Plant." (56 page(s), 2/28/2003)
- ML030870820 - Transmittal of Westinghouse Responses to US NRC Requests for Additional Information on the AP1000 Application for Design Certification. (111 page(s), 3/26/2003)
- ML030990293 - WCAP-16001, Rev 0, "Analysis of Capsule Y from Dominion Surry Unit 2 Reactor Vessel Radiation Surveillance Program," Attachment 1, Appendix C and Attachment 2, Appendix A. (141 page(s), 3/27/2003)
- ML031010518 - WCAP-15994-NP, Rev 1, "Structural Analysis Summary for the AP1000 Reactor Coolant Pump High Inertia Flywheel." (23 page(s), 3/31/2003)
- ML031150054 - WCAP-16038-NP, Revision 0, Structural Integrity Evaluation or Reactor Vessel Upper Head Penetrations to Support Continued Operation: St. Lucie Unit 2, Section 7 Through Appendix E, Figure E-7. (58 page(s), 3/31/2003)
- ML031200512 - WCAP-16038-NP, Revision 0, Structural Integrity Evaluation or Reactor Vessel Upper Head Penetrations to Support Continued Operation: St. Lucie Unit 2, Table of Contents Through Figure 6.24. (78 page(s), 3/31/2003)
- ML031270105 - WCAP-16076-NP, Rev 0, Requirements Phase Human Factors Review for Common Q Phase 3 Core Protection Calculator System Project. (69 page(s), 3/31/2003)
- ML032410177 - Rev 0 to WCAP-16005-NP, "San Onofre Nuclear Generating Station, Unit 2 RCS Pressure & Temperature Limits Report." (79 page(s), 3/31/2003)
- ML033070012 - Revision 0 to WCAP-16027-NP, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Turkey Point, Units 3 and 4." (158 page(s), 3/31/2003)
- ML041970453 - "Generic W* Tube Plugging Criteria for 51 Series Steam Generator Tubesheet Region WEXTEX Expansions." (201 page(s), 3/31/2003)
- ML030980037 - Transmittal of Westinghouse Document, "AP1000 Instrumentation & Control Defense in Depth & Diversity Report," WCAP-15775, Revision 2, Non-Proprietary, Dated March 2003. (40 page(s), 4/3/2003)
- ML031000540 - Transmittal of Westinghouse Document, "AP1000 Assessment Against NFPA 804", WCAP-15871, Revision 1, Non-Proprietary, Dated, December 2002. (75 page(s), 4/8/2003)
- ML031040322 - Transmittal of Westinghouse Documents, "Analysis of Probability of Generation of Missiles from Fully Integral Nuclear Low Pressure Turbines," WCAP-15783, Rev. 1, Non-Proprietary & Proprietary Versions. (38 page(s), 4/10/2003)
- ML031070372 - Transmittal of Westinghouse Document, AP1000 Implementation of Regulatory Treatment of Nonsafety-Related Systems Process, WCAP-15985, Revision 1, Non-Proprietary, Dated April 2003. (115 page(s), 4/15/2003)
- ML031320381 - Westinghouse Topical Report WCAP-15628-NP, Rev 0, "Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the H. B. Robinson Unit 2 Nuclear Power Plant for the License Renewal Program." (66 page(s), 4/30/2003)
- ML031320389 - Westinghouse Topical Report WCAP-15363-NP, Rev 1, "A Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings of H. B. Robinson Unit 2 for the License Renewal Program." (34 page(s), 4/30/2003)
- ML031420200 - WCAP-16067-NP, Rev 0, "RCS Flow Measurement Using Elbow Tap Methodology at Watts Bar Unit 1." (68 page(s), 4/30/2003)
- ML031570274 - WCAP-14936, Code Qualification Document for Best Estimate Small Break LOCA Analysis, Revision 0, August 2001 and WCAP-14936-NP, Revision 0, April 2003, Table of Contents Through Figure 8-34. (812 page(s), 5/7/2003)
- ML031570501 - WCAP-14936, Code Qualification Document for Best Estimate Small Break LOCA Analysis, Revision 0, August 2001 and WCAP-14936-NP, Revision 0, April 2003, Sections 9 Through 23. (790 page(s), 5/7/2003)
- ML031570508 - WCAP-14936, Code Qualification Document for Best Estimate Small Break LOCA Analysis, Revision 0, August 2001 and WCAP-14936-NP, Revision 0, April 2003, Abstract Through Section 35. (724 page(s), 5/7/2003)
- ML050560110 - Transmittal of Revision 14 to AP1000 Design Certification Documents. (15 page(s), 2/9/2005)
- ML050750282 - APP-GW-GL-700, Revision 14, "AP1000 Design Control Document." Cover through Section 7. Instrument and Controls, Page 7.7-25. (3088 page(s), 9/7/2004)
- ML050750284 - APP-GW-GL-700, Revision 14, "AP1000 Design Control Document." Table of Contents, Section 8 - Section 19. Page 19E-94. (3342 page(s), 2/9/2005)
- ML031610765 - Rev 0 to WCAP-15873-NP, "A Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casing of R.E. Ginna Nuclear Power Plant for License Renewal Program." (23 page(s), 5/31/2003)
- ML031610768 - Rev 0 to WCAP-15837-NP, "Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for R.E. Ginna Nuclear Power Plant for License Renewal Program." (60 page(s), 5/31/2003)
- ML031610789 - Revision 0, Addendum 1 to WCAP-15306-NP-A, "Addendum 1 to WCAP-15306-NP-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code." (72 page(s), 5/31/2003)
- ML032320341 - Improved Justification of Partial-Length RPC Inspection of Tube Joints of Model F Steam Generators of Ameren-UE Callaway Plant. (258 page(s), 5/31/2003)
- ML032170332 - 2003/07/31-Licensing Topical Report, Constant Pressure Power Uprate. (213 page(s), 7/31/2003)
- ML032750349 - Revision 1 to GE-NE-0000-0013-3193-01a-R1, "Pressure-Temperature Curves for TVA Browns Ferry, Unit 2." (135 page(s), 8/31/2003)
- ML032750393 - Revision 1 to GE-NE-0000-0013-3193-02a-R1, "Pressure-Temperature Curves for TVA Browns Ferry, Unit 3." (135 page(s), 8/31/2003)
- ML032930103 - Revision 0 to WCAP-15813-NP, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Millstone, Unit 2." (106 page(s), 8/31/2003)
- ML033010566 - Revision 0 to WCAP-15919-NP, "Steam Generator Tube Repair for Westinghouse Designed Plants With 7/8 Inch Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves." (145 page(s), 8/31/2003)
- ML040300702 - Revision 0 to WCAP-15919-NP, "Steam Generator Tube Repair for Westinghouse Designed Plants With 7/8 Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves." (136 page(s), 8/31/2003)
- ML032930333 - Transmittal of Revision 2 of WCAP-15860, "Programmatic Level Description of the AP1000 Human Factors Verification and Validation Plan," dated October 2003. (24 page(s), 10/16/2003)
- ML033070164 - Duane Arnold, Kewaunee, Monticello, Palisades, Point Beach & Prairie Island NQA-1 vs Non-Programmatic ANSI Standards Comparison Tables. (157 page(s), 10/31/2003)
- ML040120622 - Revision 0 to WCAP-16170-NP, "Diablo Canyon SG Alternate Repair Criteria Bases on Limited Tube Support Plate Displacement." (247 page(s), 11/30/2003)
- ML033650400 - Revision 0 to WCAP-16144-NP, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Beaver Valley, Unit 2." (99 page(s), 12/31/2003)
- ML040300636 - WCAP-15918-NP, Rev. 01, "Steam Generator Tube Repair for Combustion Engineering and Westinghouse Designed Plants with 3/4 Inch Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves." (156 page(s), 1/31/2004)
- ML043440231 - Nonproprietary Revision 0 to NEDO-33112, "Pressure-Temperature Curves For TVA Browns Ferry Unit 1." (139 page(s), 1/31/2004)
- ML041070458 - GE-NE-0000-0027-0575-01, Rev 0, "The Upper Shelf Energy Evaluation for RPV Electroslag Welds at Quad Cities Unit 2." (31 page(s), 3/31/2004)
- ML041470212 - Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Request for a License Amendment to Incorporate Approved Pressure and Temperature Limits Report (PTLR) Methodology into Technical Specifications. (282 page(s), 5/21/2004)
- ML043150406 - Topical Report WCAP-16208-NP, REV 0, "NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansion." (136 page(s), 10/31/2004)
- ML051430366 - SER Related to the Topical Report for the Foster Wheeler Modular Vault Dry Store (M.V.D.S.) for Irradiated Nuclear Fuel, Revision 1. (284 page(s), 3/31/1988)