Document: NUREG-0800
Document ID: 22d810e7-740f-4bf3-8bcd-8e3f969ca03f
Document Type: srp
Title: OVERHEAD HEAVY LOAD HANDLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070510.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.1.5
CFR Part: 
CFR Title: 

Content:
erials be designed in manner that ensures adequate safety under normal and postulated accident conditions. 9.1.5-7 DRAFT Rev. 1 - April 1996 The requirements of GDC 61 are imposed on SRP Section 9.1.5 because it requires that the OHLHS be designed to ensure safety under normal accident and conditions. The OHLHS is concerned with handling heavy loads in critical areas (e.g., over the open reactor vessel or over the spent fuel pool). A malfunction of the OHLHS in such areas could cause a release of radioactive materials, a criticality accident, the inability to cool fuel within the reactor vessel or spent fuel pool, prevent safe shutdown of the reactor, or could release fission products — thus potentially causing unacceptable personnel exposures. SRP Section 9.1.5 cites Regulatory Guide 1.13, position C.3, and ANS 57.1/ANSI N208 to provide guidance for meeting these requirements. Meeting these requirements provides assurance that personnel working with the OHLHS will be working under adequately safe conditions and that personnel exposure to radiation will be within safe limits.29 III. REVIEW PROCEDURES The OHLHSs are provided for handling heavy loads i.e., loads whose weight exceeds that of one fuel assembly and its associated handling device such as a reactor vessel head, internals, shield plug segments and spent fuel casks. Due to variations in plant designs, the ASBSPLB shall 30 review the analyses made of the potential consequences that could follow the dropping of each heavy load at any point along its path of travel. In those cases where the consequences are unacceptable the load is to be considered a critical load and hence subject to the acceptance criteria presented in this SRP section. The general objective of the review is to confirm that the OHLHS design precludes system malfunctions or failures that would prevent safe shutdown of the reactor, or cause an unacceptable release of radioactivity, a criticality accident or the inability to cool the fuel in