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:
ated 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 concluded that unstable condensation oscillation loads due to suppression pool temperatures approaching the saturation temperature are bounded by air clearing hydrodynamic loads when the "T" or "X" quencher is used. The NRC review and approval of this conclusion is documented in a August 29, 1994 safety evaluation. The staff also reviews the proposed reactor coolant system safety/relief valve in-plant confirmatory test programs or the rationale for not performing such tests. 6. The reviewer evaluates analyses of bypass leakage capability. The reviewer determines the adequacy of proposed bypass leakage tests and surveillance programs based on the results of previous reviews, operating experience at similar plants, and engineering judgment. The reviewer will advise the staff responsible for SRP Section 15.0.3 (for advanced light water reactors and operating reactors) of the bypass leakage. 7. The reviewer evaluates the conservatism of potential depressurization transients. In evaluating surveillance and test programs for vacuum relief systems, the reviewer uses the results of previous reviews and operating experience with similar systems to determine their adequacy. At the operating license or design certification stage, the reviewer responsible for SRP Section 16.0 reviews the proposed technical specifications to assure that adequate surveillance and administrative control will be maintained over the vacuum relief devices. 8. Upon request, the reviewer responsible for Standard Review Plan Section 3.9.2 will review the design of unique flow-limiting devices which are identified during the staff’s review of the containment subcompartments. 9. The staff reviews the accuracy and range of the instrumentation provided to monitor the post-accident environment. The reviewer