NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 2
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3.7.B.2-27 Through 3D-17
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 1.0 - Introduction and General Description of Plant
L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 04; Appendix a, Safety Evaluation Report Compliance
ST-HL-AE-1940, Forwards marked-up FSAR Pages Re Cumulative Usage Factor for Accumulator Safety Injection Lines & Pressurizer Surge Lines.Changes Support Preparation of SER & Will Be Incorporated Into FSAR Amend 59
ST-HL-AE-1879, Forwards marked-up FSAR Pages Reflecting Revs Resulting from Update & Consistency Check.Modeling Techniques & Assumptions Used by Westinghouse for Reactor Internals Analysis Updated. No Impact on Conclusions of SER Noted
NSD-NRC-97-5110, Forwards Set of SSAR Markups for Subsection 3.6.3 & App 3B to Address Open Items Re leak-before-break.SSAR Rev 12 Includes Changes
DCL-04-057, Response to NRC Request for Additional Information Regarding License Amendment Request 03-16. Revised Wedge Region Exclusion Zones for Steam Generator Tube Alternate Repair Criteria
NSD-NRC-96-4873, Forwards Responses to Open Items to leak-before-break Open Items,Dser Section 3.6.4.Westinghouse Needs Info from NRC Evaluation of Waterhammer Loads
RC-94-0141, Forwards Response to NRC 940425 RAI for SG Replacement (Sgr) Review.Rev to Pages Xiv & 3.2-3 of 931029,submittal Supporting Sgr TS Changes.Informs That Minor Rev to LOCA Hydraulic Loads on Core Barrel Made