Document: NUREG-0800
Document ID: 80fe9eee-2d6e-4a7e-b7dd-ec23aab2d39f
Document Type: srp
Title: STRATEGIES AND GUIDANCE TO ADDRESS LOSS OF LARGE AREAS OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1211/ML121110138.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.4
CFR Part: 
CFR Title: 

Content:
February 25, 2002.1 The NRC staff issued guidance to current reactor licensees on February 25, 2005.2 Following issuance of the guidance, the NRC staff conducted inspections at operating reactor sites using Temporary Instruction (TI) 2515/164 (Safeguards Information (SGI)) to gather information on actions taken in response to the ICM order using the February 25, 2005, guidance. The NRC staff then convened assessment panels to evaluate the adequacy of licensee actions taken to date. These assessment panels developed acceptance criteria to determine the adequacy of licensee responses to each of the 34 expectations identified in Attachment B to the February 25, 2005, guidance. On January 18 and 26, 2006, the NRC staff met with industry representatives and provided further clarifying information, including staff acceptance criteria regarding how licensees could meet Section B.5.b of the ICM Order. The NRC clarifying information for acceptance of each expectation was disseminated in Sections 05.02(c) and 05.02(d) of TI 2515/168 (SGI). This clarifying information represented acceptable methods, along with staff acceptance criteria, for satisfying the expectations. By letters dated January 24, 2006, May 15, 2006, and June 27, 2006, the Nuclear Energy Institute (NEI) proposed additional criteria for strategies and guidance to maintain or restore core cooling, containment, and SFP cooling capabilities. The NRC staff accepted these proposals along with the proposal to document the additional requirements by license condition in a letter dated June 29, 2006. The NRC staff used this clarifying information and the additional proposed strategy criteria in developing its safety evaluations, imposing conforming license conditions, and inspecting then current power reactor licensees’ compliance with Section B.5.b of the ICM Order. 10 CFR 50.54(hh)(2) made permanent and generically applicable the requirements imposed by Section B.5.b of the ICM Order and the subsequently imposed