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
CFR Part: 
CFR Title: 

Content:
nt accident consistent with Regulatory Guide 1.3. 6. In meeting the requirement of GDC 16, provisions should be made in one of the following ways to protect the drywell and wetwell (or containment) of Mark I, II, III, and ABWR plants, and the operating deck of Mark II plants, against loss of integrity from negative pressure transients or post accident atmosphere cooldown: A. Structures should be designed to withstand the maximum calculated external pressure. B. Vacuum relief devices should be provided in accordance with the requirements of the ASME Boiler and Pressure Vessel Code, Section III, Subsection NE, to assure that the external design pressures of the structures are not exceeded. 6.2.1.1.C-7 Revision 7 - March 2007 The vacuum relief valve guidelines are set forth in Appendix A to this SRP section. 7. In meeting the requirements of GDC 50, with respect to design margin for item 6. above, the external design pressures of the structures, including the design upward deck differential pressure for Mark II plants, should provide an adequate margin above the maximum calculated external pressures to account for uncertainties in the analyses. 8. In meeting the requirements of GDC4, the acceptability of the reactor coolant system safety/relief valve in-plant confirmatory test program shall be based on conformance with the guidelines specified in Section 6, 7, and 8 of NUREG-0763. If the applicant/licensee elects not to perform the SRV in-plant tests, the acceptability of this exception shall be determined in conformance with the guidelines specified in Section 4 of NUREG-0763. 9. NUREG-0783 specifies that, for BWR pressure-suppression plants, the local suppression pool temperature should not exceed 93 C (200 F) or the acceptance criteria specified in Section 5.1 of NUREG 0783. This criterion 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