Document: NUREG-0800
Document ID: faf774de-7226-41f8-ba11-7cf612907af6
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1306/ML13065A119.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
. 21. IE Information Notice No. 82-43, “Deficiencies in LWR Air Filtration/Ventilation Systems,” November 16, 1982. 22. IE Information Notice No. 82-49, “Correction for Sample Conditions for Air and Gas Monitor,” December 16, 1982. 23. IE Information Notice No. 91-40, “Contamination of NonRadioactive System and Resulting Possibility for Unmonitored, Uncontrolled Release to the Environment,” June 19, 1991. 24. IE Information Notice No. 99-01, “Deterioration of High-Efficiency Particulate Air Filters in a Pressurized Water Reactor Containment Fan Cooler Unit,” January 20, 1999. 25. NEI 08-08A, “Generic FSAR Template Guidance for Life Cycle Minimization of Contamination,” Revision 0, October 2009. 26. NEI 07-09A, “Generic FSAR Template Guidance for Offsite Dose Calculation Manual (ODCM) Program Description,” Revision 0, March 2009. 11.3-46 Draft Revision 4 – August 2014 27. NEI 97-06, “Steam Generator Program Guidelines,” 1997. Nuclear Energy Institute Washington, DC. 28. NUREG-0800, Section 5, Branch Technical Position (BTP) 5-1 “Monitoring of Secondary Side Water Chemistry in PWR Steam Generators.” 29. NUREG-1430, "Standard Technical Specifications - Babcock and Wilcox Plants." 30. NUREG-1431, "Standard Technical Specifications - Westinghouse Plants." 31. NUREG-1432, "Standard Technical Specifications - Combustion Engineering Plants." 32. NUREG-1433, "Standard Technical Specifications - General Electric Plants (BWR/4)." 33. NUREG-1434, "Standard Technical Specifications - General Electric Plants (BWR/6)." 34. RG 4.21, “Minimization of Contamination and Radioactive Waste Generation: Life-Cycle Planning.” 35. RG 1.54, “Service Level l, II, and III Protective Coatings Applied to Nuclear Power Plants.” 36. RG 1.68, “Initial Test Programs for Water-Cooled Nuclear Power Plants.” 37. RG 1.97, “Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants.” 38. RG 1.187, "Guidance for Implementation of 10 CFR