Document: NUREG-0800
Document ID: ecf7a8d4-0097-4a93-8609-630545f03f70
Document Type: srp
Title: REGULATORY TREATMENT OF NONSAFETY SYSTEMS FOR PASSIVE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1308/ML13081A756.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.3
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Office of Management and Budget, approval numbers 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. 19.3-17 Draft Rev.0 – June 2013 SRP Section 19.3 Description of Changes Section 19.3 “REGULATORY TREATMENT OF NONSAFETY SYSTEMS FOR PASSIVE ADVANCED LIGHT WATER REACTORS” This SRP section reflects the staff’s disposition of public comments on the guidance previously provided in Section 19.3, Draft Revision 0, dated October 2012 of NUREG-0800. See the Agencywide Documents Access and Management System (ADAMS) Accession No. ML12128A405. A description of each comment and how it has been addressed by the NRC will be published when the SRP section is issued in final form. In addressing the public’s comments, the NRC has modified the SRP section to reflect a revised position on treatment of the high winds external hazard for certain RTNSS SSCs. This position differs from the one described in the previously issued draft Section 19.3 of NUREG-0800 and from the alternative proposed in public comments (ML12319A465) on the previously issued draft Section 19.3 of NUREG-0800, which, during a public meeting held on January 22, 2013, the staff agreed to consider. The reason for the change is as follows. The staff’s original position on treatment of the high winds external hazard is documented in a memorandum from L. Joseph Callan, USNRC Executive Director for Operations to Chairman Jackson, US NRC dated June 23, 1997 (ML003708229) and entitled: “Implementation of Staff Position in SECY-96-128, ‘Policy and Key Technical Issues Pertaining to the Westinghouse AP600 Standard Pressurized Reactor Design’, Related to Post-72 Hour Actions”. At that time the NRC was concerned with the ability of a severe hurricane to cause an extended loss of