Document: NUREG-0800
Document ID: 6aed9d14-682e-4421-ba5e-a1fcc9263878
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190011.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
o meets the requirements of GDC 14 for assuring the low probability of abnormal leakage or failure of the reactor coolant pressure boundary and safety-related structures. We conclude that the proposed pH for emergency coolant water is acceptable. D. REFERENCES 1. D.D. Whyte and L.F. Picone, “Behavior of Austenitic Stainless Steel in Post Hypothetical Loss of Coolant Environment,” WCAP-7798-L, Westinghouse Nuclear Energy Systems, (NES Proprietary Class 2). 2. J.C. Griess and E. E. Creek, “Design Considerations of Reactor Containment Spray Systems - Part X, The Stress Corrosion Cracking of Types 304 and 316 Stainless Steel in Boric Acid Solutions,” ORNL-TM-2412, Part X, Oak Ridge National Laboratory. BTP 6-1.3 March 2007 PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.