Resolution of Generic Safety Issues: Item A-28: Increase in Spent Fuel Pool Storage Capacity ( NUREG-0933, Main Report with Supplements 1–35 )

DESCRIPTION

Historical Background

This NUREG-0371² item involves the development of consistent and formalized acceptance criteria regarding the conversion to higher density storage racks (increased storage capacity) in existing spent fuel storage pools.

Safety Significance

The safety significance of this issue is that damage to spent fuel, primarily from a lack of adequate cooling, could result in the release of radioactivity. Because of radioactive decay, the quantity of radioactivity potentially available for release is substantially less than from a core-melt accident initiated while the reactor is at power. Engineered safety features are also provided to confine and filter any radioactivity that might be released from fuel in the storage pool. Therefore, the risk from damaged spent fuel is only a small fraction of the risk from core-melt accidents.

Possible Solution

The resolution of this issue is contained in an NRC letter⁶⁷ issued on April 17, 1978 to all power reactor licensees. This letter contains in a single document the criteria used by the staff in evaluating applications for spent fuel pool modifications and has been formally transmitted to appropriate licensees and applicants.

CONCLUSION

This item has been RESOLVED.

REFERENCES

0002. NUREG-0371, "Task Action Plans for Generic Activities (Category A)," U.S. Nuclear Regulatory Commission, November 1978. 0067. Letter to All Power Reactor Licensees from B. Grimes, "OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications," April 14, 1978. [7910310568]