Document: NUREG-0800
Document ID: a2000868-0102-4287-8708-80ea4ff14ede
Document Type: srp
Title: Revision 6 – August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A028.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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CFR Title: 

Content:
her with a single electrical failure. The basis for the position is that an auxiliary feedwater piping break would result in tripping the unit and, in turn, might cause loss of offsite power. Standard staff assumptions for analyzing postulated accidents include the assumption of loss of offsite power if the affected unit generator is tripped by the accident. Such a circumstance would leave the plant without adequate means for removal of decay heat even though the reactor coolant pressure boundary was intact - an unacceptable result. Plant heat removal systems must, in any postulated piping break, be capable of removing decay heat to the ultimate heat sink assuming a single electrical (active) failure anywhere in the auxiliary feedwater system or in the onsite power system. BTP 7-4-3 Revision 6 – August 2016 PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50, and were approved by the Office of Management and Budget, approval number 3150-0011. 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. BTP 7-4-4 Revision 6 – August 2016 BTP Section 7-4 Description of Changes BTP 7-4, “Guidance on Design Criteria for Auxiliary Feedwater Systems” This BTP Section affirms the technical accuracy and adequacy of the guidance previously provided in BTP 7-4, Revision 5, dated March 2007. See ADAMS Accession No. ML070550093. All changes to this BTP section in this revision were editorial.