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:
4 – August 2014 38. NEI 07-09A, “Generic FSAR Template Guidance for Offsite Dose Calculation Manual (ODCM) Program Description,” Revision 0, March 2009. 39. NEI 97-06, “Steam Generator Program Guidelines,” 1997. 40. NUREG-0016, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWRs).” 41. NUREG-0017, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWRs) (PWR GALE Code).” 42. NUREG-0133, “Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.” 43. NUREG-0800, Section 5, Branch Technical Position (BTP) 5-1 “Monitoring of Secondary Side Water Chemistry in PWR Steam Generators.” 44. NUREG-0800, BTP 11-5, “Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure.” 45. NUREG-1301, “Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors.” 46. NUREG-1302, “Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors.” 47. NUREG-1430, "Standard Technical Specifications - Babcock and Wilcox Plants." 48. NUREG-1431, "Standard Technical Specifications - Westinghouse Plants." 49. NUREG-1432, "Standard Technical Specifications - Combustion Engineering Plants." 50. NUREG-1433, "Standard Technical Specifications - General Electric Plants (BWR/4)." 51. NUREG-1434, "Standard Technical Specifications - General Electric Plants (BWR/6)." 52. NUREG/CR-4653, “GASPAR II—Technical Reference and User Guide.” 53. NUREG/CR-3587, “Identification and Evaluation of Facility Techniques for Decommissioning of Light Water Reactors.” 54. RG 1.11, “Instrument Lines Penetrating Primary Reactor Containment.” 55. RG 1.33, “Quality Assurance Program Requirements (Operation).” 56. RG 1.52, “Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units