Document: NUREG-0800
Document ID: d2f0cc81-920c-4065-b74b-67114ba68b0e
Document Type: srp
Title: through 7.9 of the SAR. Where exceptions are taken to the guidance provided by regulatory guides, and
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500493.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
in the review of Section 7.7 of the SAR. k. 50.34(f)(2)(xxiii) [TMI Action Plan Item II.K.2.10] Anticipatory Trip on Loss of Main Feedwater or Turbine Trip "Provide, as part of the reactor protection system, an anticipatory reactor trip that would be actuated on loss of main feedwater and on turbine trip. (Applicable to B&W-designed plants only)." Applicability — RTS in B&W-designed plants. Review Methods — The design should comply with the guidance of NUREG-0694 item II.K.1 and IEEE Std 279. Appendix 7.1-B item 6 and Appendix 7.1-C item 17 provide guidance on the review of auxiliary features such as anticipatory trips. The evaluation of conformance with this requirement should be addressed in the review of Section 7.2 of the SAR. l. 50.34(f)(2)(xxiv) [TMI Action Plan Item II.K.3.23] Central Reactor Vessel Water Level Recording "Provide the capability to record reactor vessel water level in one location on recorders that meet normal post-accident recording requirements. (Applicable to BWRs only)." Applicability — Information systems important to safety in BWRs. Review Methods — The capability should be provided to record water level over the range from the top of the vessel dome to the lowest pressure tap. This range of water level indication should be available in one location on recorders that meet normal post-accident recording requirements. The evaluation of conformance with this requirement should be addressed in the review of Section 7.5 of the SAR. m. 50.62 Requirements for Reduction of Risk from Anticipated Transients without Scram "(1) Each pressurized water reactor must have equipment from sensor output to final actuation device, that is diverse from the reactor trip system, to automatically initiate the auxiliary (or emergency) feedwater system and initiate a turbine trip under conditions indicative of an ATWS. This equipment must be designed to Rev. 4 — June 1997 SRP 7.1-A-7 perform its function in a reliable manner and be independent (from