RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015
RS-17-119, Braidwood, Units 1 and 2 - Full Action Request Report AR 792215, MSLB Calc. Energy Release Error, Redacted
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 6, Engineered Safety Features (Redacted)
DCL-16-057, Diablo Canyon Units 1 and 2 License Amendment Request 16-03 Application to Adopt NEI 94-01 Revision 2-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J.
DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8
NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 14 - Safety Analysis
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 14, Safety Analysis
CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)
NSD-NRC-97-4989, Requests Responses to NRC Request for Addl Info & Updates of Status for Several Areas Being Reviewed by Ecgb & Emeb for AP600
NRC-94-4237, Forwards Responses to NRC RAIs on AP600 from Ltrs of 940428, 29,0502,05,16 & 26.Revs of Responses Previously Submitted Also Provided
NSD-NRC-97-4947, Submits Refs & Changes for SSAR Chapter 7.Encl 1 Will Be Included in SSAR Rev 11.NRC Requested to Review Encl 2 & Provide Westinghouse W/Nrc Status for Item,Including 1052 & 1053 for Interlocks
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
AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1)
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