Document: NUREG-0800
Document ID: e1169529-d2cb-4947-9efe-b23d927f4aa9
Document Type: srp
Title: NUREG40800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350520.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8
CFR Part: 
CFR Title: 

Content:
NUREG40800 (Formerly NUREG-75/087) U.S.U NUCLEAR REGULATORY COMMISSION ;os~t STANDARD REVIEW PLAN OFRlCE OF NUCLEAR REACTOR REGULATION Appendix 8-A BRANCH.TECHNICAL POSITIONS (PSB) The PSB Branch Technical Positions (BTPs) represent guidelines intended to supplement the acceptance criteria established in Commission Regulations, guide- lines presented in Regulatory Guides, and recommendations presented in applicable IEEE standards. As technical problems or questions of interpretation arise in the detailed reviews of plant designs, the staff must determine an acceptable resolution for each such case to complete its review of a particular application. Where the same technical problem or question of interpretation arises in several cases, the staff's determination on the point at issue is formalized in a BTP. The BTP is primarily an instruction to staff reviewers that outlines an accept- able approach to the particular issue and ensures a uniform treatment of the issue by staff reviewers. The approaches taken in the BTPs, like the approaches taken in regulatory guides, are not mandatory, but do provide defined, acceptable, and immediate solutions to some of the technical problems and questions of inter- pretation that arise in the review process. In some instances, regulatory guides may be developed from BTPs after sufficient experience in their use has accumu- lated. All PSB BTPs applicable to Chapter 8 of the Standard Review Plan have been included in this appendix for convenience. They are listed below: BTP ICSB (PSB)* Branch Technical Positions of the PSB 2-- - Diesel-Generator Reliability Qualification Testing (Deleted) 4 Requirements on Motor-Operated Valves in the ECCS Accumulator Lines 8 Use of Diesel-Generator Sets for Peaking 11 Stability of Offsite Power Systems 15 Reactor Coolant Pump Breaker Qualification (Deleted) 17 Diesel-Generator Protective Trip Circuit Bypasses (Deleted) I 18 Application of the Single Failure Criterion to Manually- Controlled