This standard is prepared and modified by reference to the American standard ANSI/ANS 57.2 Design requirements for light water reactor spent fuel storage facilities at nuclear power plants.
This standard replaces EJ/T 883-1994 Design criteria for pressurized water reactor spent fuel storage device at nuclear power plant.
The following main changes have been made with respect to EJ/T 883-1994:
a) The current national standards of China are adopted as normative references;
b) For the design of spent fuel storage rack proposed in this standard, the burn-up credit may be applied;
c) The stress criterion of spent fuel storage rack is supplemented and perfected.
d) The principle requirements for the consideration of facility decommissioning are supplemented;
e) Some words are revised.
This standard was proposed by China National Nuclear Corporation.
This standard is under the jurisdiction of the Institute for Standardization of Nuclear Industry.
Drafting organization of this standard: The Second Research and Design Engineering Corporation of CNNC.
Chief drafters of this standard: Xie Liang, Li Jianqi and Gao Mingqing.
This standard was firstly issued in October 1994.
Design criteria for pressurized water reactor spent fuel storage facilities at nuclear power plant
1 Scope
This standard specifies the basic design requirements for pressurized water reactor spent fuel storage facilities at nuclear power plant.
This standard is applicable to the design for pressurized water reactor spent fuel storage facilities at nuclear power plant with independent fuel storage building; as for pressurized water reactor at nuclear power plant with spent fuel storage facilities arranged in the containment, the spent fuel storage facilities may be designed by reference to the applicable provisions of this standard.
2 Normative references
The following normative documents contain provisions which, through reference in this text, constitute provisions of this standard. For dated references, subsequent amendments (excluding corrections) to, or revisions of, any of these publications do not apply to this standard. However parties to agreements based on this standard are encouraged to investigate the possibility of applying the most recent editions of the normative documents indicated below. For undated references, the latest edition of the normative document referred to applies.
GB/T 17569-1998 Classification for the items of pressurized water reactor nuclear power pants
3 Terms and definitions
For the purposes of this standard, the following terms and definitions apply:
3.1
heavy load
loads whose weight exceeds the value used in the analytical calculation of the spent fuel storage rack
4 Operation condition classification and safety classification
4.1 Operation condition classification
According to the specific characteristics of spent fuel storage facilities, their operation conditions are divided into four categories:
——Plant condition I
PC I events are those events that are expected to occur regularly or frequently in the course of normal operation at the facility. Generally, the following shall be considered:
a) handling and storage of fuel;
b) shipping of spent fuel;
c) storage of damaged fuel that resulted in up to 10% of the technical specification limit for reactor coolant activity during power operation;
d) inspection of fuel assembly in storage facilities;
e) storage of new fuel assembly in spent fuel storage facilities.
——Plant condition II
Foreword i
1 Scope
2 Normative references
3 Terms and definitions
4 Operation condition classification and safety classification
5 Function and composition of spent fuel storage facilities
6 Design of spent fuel storage facilities
