Document: NUREG-0800
Document ID: 2c839e4a-a342-4e25-9a7c-82d678a0f754
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340657.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
ry test program shall be based on conformance with the guidelines specified in Section 6, 7, and 8 of NUREG-0763 (Ref. 1d). 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. For Mark I, II, and III plants, the local suppression pool temperature should not exceed 200OF or the acceptance criteria specified in Section 5.1 of NUREG-0783 (Ref. If). 10. In meeting the requirements of General Design Criteria 13 and 64, instrumentation capable of operating in the post-accident environment should be provided to monitor the containment atmosphere pressure and temperature and the suppression pool water level and temperature following 6.2. 1. 1.C-5 Rev. 6 - August 1984 an accident. The instrumentation should have adequate range, accuracy, and response to assure that the above parameters can be tracked and recorded throughout the course of an accident. Item II.F.1 of HUREG-073;t and NUREG-0718, and Regulatory Guide 1.97, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following An Accident," should be followed. III. REVIEW PROCEDURES The procedures described below are followed for the review of BWR pressure- suppression containments. The reviewer selects and emphasizes material from these procedures as may be appropriate for a particular case. Portions of the review may be carried out on a generic basis for aspects of functional design common to a class of BWR pressure-suppression type containments or by adopting the results of previous reviews of plants with essentially the same containment functional design. Upon request from the primary reviewer, the secondary review branches will provide input for the areas of review stated in subsection I of this SRP section. The primary reviewer obtains and uses such input as required to assure that this review procedure is complete. 1.