N291-08 Requirements for Safety-Related Structures for CANDU Nuclear Power Plants

Clause 1.1 - The following interpretation regarding Clause 1.1 of CSA Standard N291-08, Requirements for Safety-related Structures for CANDU Nuclear Power Plants, has been approved by the Technical Committee on Concrete Containment and Safety-Related Structures.

  Question: Are the safety-related structures of facilities for the storage of irradiated fuel and other radioactive waste materials noted in clause 1.1 limited to those structure or components that, should they fail to perform their intended function, will impede the safety operation and shutdown of the reactor?
  Answer: Yes, but clause 1.1 also includes facilities for safe storage (wet or dry) of irradiated fuel.

Clause 6.4.3

  Question: Is Clause 6.4.3 equally applicable to Service and Abnormal/Environmental Category load combinations?
  Answer: Yes, Clause 6.4.3 is used only to calculate the seismic forces (Qed and Qes) applied to the load combinations in Table 3.
Clause 6.4.3 and Table 3
  Question: In Table 3, is the 0.5 load factor for “L” that applies to Service Category combinations that include Qes intended to reflect the 50% reduction for live load in clause 6.4.3?
  Answer: No, Clause 6.4.3 is used to calculate seismic forces only.
Clause 6.4.3 and Table 3
  Question: In Table 3, is the 1.0 load factor for “L” that applies to Abnormal/Environmental Category load combinations that include Qes and Qed intended to reflect reductions in live load noted in Clause 6.4.3?
Note: The original RFI question was amended by the TC with the agreement of the submitter.
  Answer: No, Clause 6.4.3 is used to calculate seismic forces only.
Clause 6.4.3
  Question: Is the reduction in live load specified in Clause 6.4.3 applicable to both the computation of seismic loads and the “L” in Service and Abnormal/Environmental Category load combinations?
  Answer: No, reduction in Clause 6.4.3 is used to calculate the seismic forces only, not live loads (L).