Document: NUREG-0800
Document ID: 919b8fa0-8b11-41bd-9694-2c62120b843b
Document Type: srp
Title: Revision 7 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600403.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
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Content:
eview of the dynamic loads associated with the actuation of one or more primary coolant system safety/relief valves has been concluded with the issuance of NUREG-0661 for Mark I plants, and NUREG-0802 for Mark II and Mark III plants. The review of dynamic loads for ABWR plants has been concluded with issuance of Appendix 3B of the ABWR SSAR. 4. For Mark III and ABWR plants, the reviewer verifies from the safety analysis report that high energy lines which pass through the containment outside the drywell are provided with guard pipes or enclosed in other types of protective structures. If guard pipes are used, the design must meet the acceptance criteria established in SRP Sections 3.6.2 and 3.8.3. For unguarded lines, the staff reviews analyses of the consequences of postulated ruptures in these lines. The reviewer bases its acceptance of the analyses on the conservatism of the methods and assumptions and on the margin provided to assure against exceeding the design pressure of the containment. If leakage detection and isolation equipment are provided, the staff responsible for SRP Section 15.0.3 (for advanced light water reactors and operating reactors) evaluates the effectiveness of the detection instrumentation and isolation devices to mitigate the consequences of a pipe rupture and to meet the electrical design criteria for these systems under SRP Section 7.3. 5. The staff reviews the analyses of the suppression pool temperature for transients involving the actuation of reactor coolant system safety/relief valves in BWR pressure-suppression plants. The reviewer evaluates the assumptions and 6.2.1.1.C-11 Revision 7 - March 2007 conservatisms employed in the analyses to assure that the acceptance criteria set forth in NUREG-0783 are met. These criteria may be eliminated provided that the SRV discharges are delivered to the suppression pool through a "T" or "X" quencher device previously approved by the staff and described in NUREG-0802 and NUREG-0978. NEDO-30832