Document: NUREG-0800
Document ID: acc638c2-20fb-4686-892d-e70277acd189
Document Type: srp
Title: CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070220505.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1
CFR Part: 
CFR Title: 

Content:
ember 1986. 43. GOTHIC: Containment Analysis Package User Manual, Qualification Report and Technical manual, NAI 8907 44. Letter from Anthony C. McMurtray, USNRC, to Thomas Coutu, Site Vice President, Kewaunee Nuclear Power Plant, September 29, 2003 [ADAMS Accession Number ML0326810500] 45. Final Safety Evaluation Report Related to Certification of the AP1000 Standard Design, Volumes 1,2 and 3, NUREG-1793, US NRC, September 2004 (ML043450284) 46. Final Safety Evaluation Report Related to Certification of the AP600 Standard Design, Volumes 1,2 and 3, NUREG-1512, US NRC, September 1998 47. Ice Condenser Containment Pressure Transient Analysis Methods, WCAP-8077, Westinghouse Electric Corporation, March 1973 (Proprietary) 48. Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," July 2000 (ML003716792) 49. Regulatory Guide 1.195, "Methods and Assumptions for Evaluating Radiological Consequences of Design basis Accidents at Light Water Nuclear Power Reactors," May 2003 (ML020160023) 50. Mark I Containment Program Load Definition Report, NEDO-21888 Revision 2, General Electric Company, November 1981 51. Mark III LOCA-Related Hydrodynamic Load Definition, US Nuclear Regulatory Commission, NUREG-0978, August 1984 52. Letter to Robert Pinelli, Chairman, Boiling Water Reactor Owners Group, from Gary M. Holahan, US Nuclear Regulatory Commission, Transmittal of Safety Evaluation of General Electric Co. Topical Reports: NEDO-30832 Entitled "Elimination of Limit on BWR Suppression Pool Temperature for SRV Discharge With Quenchers," and NEDO-31695 Entitled "BWR Suppression Pool Temperature Technical Specification Limits," August 29, 1994 53. J.G.M. Andersen, et al., "TRACG Model Description," GE Energy Nuclear, NEDE-32176P, Revision 3, April 2006 6.2.1-8 Revision 3 - March 2007 54. SRP Section 3.6.2, "Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping."