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MEMORANDUM FOR: Karl Goller, Director Division of Facility Operations Office of Research FROM: Robert F. Burnett, Director Division of Safeguards Office of Nuclear Material Safety and Safeguards s SU" JECT: REQUEST FOR EXPERIMENTAL DETERMINATION OF SABOTAGE SOURCE TERM FOR SHIPMENTS OF SPENT FUEL FROM GAS-C001.ED POWER REACTORS AND NONPOWER REACTORS (/24-oms 5- fr3 -3) Our present rulemaking effort that modifies the protection requirements for shipments of spent fuel has been based on the characteristics of spent fuel from light-water power reactors. This approach was used because it is believed that ' successful sabotage of spent fuel from that class of reactor would set the upper limit of consequence from shipment sabotage. We expect to issue a proposed rule for public comment later this year. We now think it prudent to extend our program to explicitly address shipments of spent fuel from gas-cooled power reactors and from nonpower reactors because we expect that there will be a need to respond to public comment on these shipments. The curie content in such shipments is different from, and likely substan-tially lower than that in shipments of light-water power reactor fuel. However there is essentially no published comorehensive information on the possible consequences of sabotage of shipments of spent fuel in these two remaining categories. To provide a technical basis for response to anticipated public comments, I request that the Office of Research carry out a program for experimental quan-tification of the source term likely to result from sabotage of spent fuel shipments from gas-cooled power reactors and from representative nonpower reactors. The program could be an extension of or patterned af ter the existing research project " Shipping Cask Sabotage Source Term Investigation". The program probably should include the following elements:
- 1. Obtain from the literature or otherwise determine the kinds and quantities of biologically significant radionuclides contained in shipments of spent fuel from gas-cooled power reactors.-
- 2. For the four major types of nonpower reactors. AGN, TRIGA, pool and tank, determine which type produc'es the kinds and quantities of radionuclides that would be most significant biologically if released through sabotage of a shipment.
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- 3. Obtain samples of spent fuel from the selected type of nonpower reactor and representative samples of spent fuel from a gas-cooled power reactor.
- 4. Carry out experiments using small-scale explosives against simulated casks containing samples of the spent fuel.
- 5. Analyze the material released to determine the respirable fraction.
- 6. Scale the results upward to take into account the effect of full-scale explosives and full-scale loaded casks.
We would like to see the program scheduled so that the results would be avail-able within eight months. I have asked Carl Sawyer (ext. 74186) to act as the SG technical representative in this matter and to provide whatever detailed information you may require in considering this request.
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1 STUDY ON FISSION PRODUCT RELEASE: TRANSPORT SAB0TAGE U .ce yv A6fL ('+ >hetcL _4,,)g g j m .wtJ .J ) Tasks To Be Completed Task 1. HTGR Spent Fuel Subtask la. Source Tenn Analysis e Characterize HTGR spent fuel and shipping cask ye Obtain surrogate fuel e Plan experiments e Design lab scale cask and fuel assembly
. e Estimate respirable release from cold test e Send letter report on source term estimate Subtask Ib. Cold Tests e Build lab scale cask and fuel assembly e Conduct tests e Analyze samples e Send letter' report on cold tests Subtask Ic. Establish Need for Hot Tests
. e Compare results with LWR test results e Discuss need for hot tests with NRC technical monitor l Subtask id. Estimate Full-Scale Release ;
e Develop scaling law e Apply law to experimental results e Report on estimated full-scale release Task 2. NPR Spent Fuel Subtask 2a. Source Term Analysis ! e Characterize four types of NPR fuel (AGN, TRICA, pool, and tank) and appropriate shipping casks l
- Select most hazardous fuel / cask combination and report selection to NRC technical monitor xe Obtain surrogate fuel ( A.m L med )
e Design experiments; design model cask / fuel assembly e Estimate respirable release from cold test and send estimate to NRC in letter report g'f -w
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Subtask 2b. Establish Need for Experiments i e Compare estimates of HTGR release, actual HTGR release, and LWR release - Subtask 2c. Perform Cold Tests and Estimate Release e Build model cask / fuel assembly . e Conduct tests
. e Analyze results e Send letter report on cold tests e Develop scaling law e Apply scaling law to experimental results e Report to NRC on estimated full-scale release Task 3. HLW (Optional)
Subtask 3a. Obtain Surrogate HLW e Review previous work on HLW composition, casks, and source terms f a Plan experiments l e Fabricate surrogate HLW and model casks l Subtask 3b. Perform Cold Tests and Estimate Release e Conduct cold tests e Analyze samples ; e Report on cold tests ! e Develop scaling law e Apply scaling law to experimental results ! e Report on estimated full-scale release o Prepare final report e Revise final report i _.___ ._____ __._.._ ___ _ _ _ _ _.,.-_ ___ _}}