NUREG-0360, Research Info Ltr 33:transmits Documented Results from Research Program to Design,Develop & Test PAT-1 Pu Package Per Criteria in NUREG-0360.Forwards SAND78-0724, Pu Accident Resistant Container Project & NUREG/CR-0030
| ML19212A551 | |
| Person / Time | |
|---|---|
| Issue date: | 08/03/1978 |
| From: | Levine S NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Casey Smith NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19211A068 | List: |
| References | |
| RTR-NUREG-CR-0030, RTR-NUREG-CR-30 RIL-033, RIL-33, NUDOCS 7912140522 | |
| Download: ML19212A551 (8) | |
Text
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UNITED STATES fS NUCLEAR REGULATORY COMMISSION 33 " IZ, J jl.T !3 WASHINGTON, D. C. 20555 v
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A(JG 3g MEMORANDUM FOR: Clifford V. Smith, Jr., Director Office of Nuclear Material Safety and Safeguards FROM:
Saul Levine, Director Office of Nuclear Regulatory Research
SUBJECT:
RESEARCH INFORMATION ' ETTER NO.#33 - PLUT0NIUM ACCIDENT CONTAINER PROGRAM - REi3RCH, DESIGN AND DEVELOPMENT INTRODUCTION This memorandum transmits the documented results from the completed research program which designed, developed and tested the PAT-1 plutonium package that meets the NRC qualification criteria published in NdREG-0360,
" Qualification Criteria to Certify a Package for Air Transport of Plutonium."
The program was conducted by Sanc;ia Laboratories, Albuquerque, New Mexico, for the Office of Nuclear Regulatory Researci (RES) in response to your l
research request, NMSS 77-10.
The purpose of the program was to establish that a package could be developed that meets the acceptance standards defined in NUREG-0360.
The success of this effort is documented in Enclosure 1, NUREG/CR-0030, "PARC (Platonium Accident Resistant Container Program) - Research, Design, and Development." Much of the information contained in this report has already been utilized by your staff in the publication of NUREG-0361,
" Plutonium Air Transportable Package, Model PAT-1, Safety Analysis Report."
DISCUSSION Development and design of the PAT-1 package began under a technical assistance effort by your Office in mid-1976 and continued from late 1976 through mid-1977 as a program funded by this Office. The program progressea (in parallel with your Office's efforts to finalize test and acceptance criteria) through several development design and test facility failures until the successful design was finalized in mid-1977. Testing of this design, Model PAT-1, was initiated in mid-1977 and was completed in December 1977.
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C. V. Smith, Jr. Externally, the PAT-1 package (Figure 1) resembles a 65-gallon commercial stainless steel process vessel. The package is comprised, however, of a multi-layered stainless steel outer drum containing a redwood overpack (designated AQ-1), a containment vessel (TB-1) and a product can (PC-1).
outlining the design features of this A summary report (SAND 78-0724) package, the qualification requirements, and test results is provided in Enclosure 2.
RESULTS Tables 1 throagh 4 of this memorandum summarize the package qualification requirements and the analyses of the package response to these requirements.
Table 1 illustrates that during the qualification test program, five PAT-1 packages were subjected to the required series of performance tests - impact The capability of these packages to orientation being the only variable.
meet post-test containment acceptance standards was demonstrated by measure-(1) ne loss of sJrrogate contents (to a sensitivity ments indicating:
level of 10 8 grams), and (2) very small air leakage rates across the containment vessel seals. These air leakage values were used by members loss.
of your staff to obtain bounding estimates on the potential for Pu0 2 Table 1 also indicates that the required hydrostatic test and the high and Table 2 low temperature tcsts were conducted with suc essful results.
summarizes the calculations which demonstrate PAT-1 compliance with the shielding and criticality requirements of the Qualification Criteria.
These calculations indicate that, in its intended use, potential maximum external radiation levels are well below acceptable limits and that the Table 3 potential for a criticality incident is essentially non-existent.
summarizes the tests which demonstrate compliance with the requirements of In these tests, the capability of a product can (internal to the 10 CFR 71.
containment vessel) to meet the requirements of 10 CFR 71.42 was demonstrated.
Finally, Table 4 presents analyses indicating margins of safety for containment vessel integrity under maximum credible internal and extdrnal pressure envi ronments.
1567 002
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to TABLE 1
.a r+,7 C.e Summary of Qualtftcation Tests. PAT-1 Pockege im pact Vel. A to U F8"I""
Post-Test Unytelding Crush Puncture Slash 3 to7 Air Lenhage O
Impeet Target 70.000 5000 15.000 Fire 2200*r g
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.00 pets hydrostatic:. heure - No detectable water lenhages c 10'IO em'le Indtvidual Test Other Itequiremente: Impact at -40 *F -- 2.4 x 10 em'le l
Impact at 200'F -- ? m 10' em'le l
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TABLE 2 f
Shielding and Criticality Shielding PAT-1 Package Provides Sufficient Shielding (49 CFR 173)'
Normal Trans port Required -- < 10 mrem /5r 3 ft from surface Calculated -- 2 mrem /hr 3 ft from AQ-1 Required -- < 200 mrem /hr at surface Calculated -- 33 mrem /hr at surface of AQ.1 Postacetdent
-- Containment Vessel (TB-1) Provides Sufficient Shielding (10 CFR 71) -- This permits AQ-1 overpack to be discounted Required -- < 1000 mrem /hr 3 ft from surface Calculated -- 4 mrem /hr 3 f4 from sus face of TB-1 Criticality Normal Transport -- Undamaged Infinite Array K,gg- 0.3 Postacciden!
Damaged Infinite Array K,gg - 0. 4 Single Water-Flooded and Reflected TB-1 K,gg - 0. 6 (K,gg = effective neutron multiplication factor)
- Cstng 13.5 year-old Hanford-type plutonium as a conservative source model.
1567 005
. C. V. Smith, Jr.
TABLE 3
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O Results of 10 CFR 71 Qualification Tests PAT-1 Package No mal Conditions of Transport: Beat, cold, internal pressure, vibration, water spray, drop (4 ft), penetration, compression
-- No Effect on Shielding
-- No Effect on Criticality
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-- No Release: Leaktight (leakrate < 10 cm /s) Cecitainment Vessel No Belease (<10' g) of UO Surrogate from Product Can 2
-- Double Containment (product can and containment vessel both meet requirernents)
Accident Conditions of Transport :
Drop (30 ft), puncture, fire, immersion
-- No Effect on Shielding
-- No Effect on Criticality
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-- No Release: Leaktight (leskrate < 10 cm /s) Cont est Vessel No Belease (< 10' g) of Ud Surrogate from Product Can 2
-- Double Containment (product can and containment vessel both meet
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.. C. V. Smith, Jr.
TABLE 4 Containment vesset Integrity 1'., g ' !
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Maximum Credible Accident Environment -- 1080'F,1253 psi (Bounding A Tested to: 1000*F, 3330 psi,18 hrs Many tests at ~1080 *F, ~1253 psi Analysis 18,300 psi stress 93,000 pai strength At 1080*F and 1253 psi, Margin of Safety = 4 Mszimum Normal Operating Pressure -- 215'F,34. 3 psi Analysis 455 psi stress 140,000 psi strength At 215'F and 34.3 psi, Margin of Safety. 306 External Pressure Hydrostatic Requ.tre: rent -- 600 psi Tested to: 5,000 psi: No leak 5,000 psi load produces -43.000 psi stress
~ Analysts psi strength gives Margin of Safety ~ 2.5 150,030 Margin of Safety = 20 at 600 psi 1567 007
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C. V. Smith, Jr. RECOMMENDATIONS The above results and enclosed documentation are offered for your use to support the NRC efforts to certify that a plutonium package has been developed to meet the requirements of Public Law 94-79. Any questions on the presented information, or on unpublished but documented results of development tests, should be referred to W. R. Lahs of the Systems Performance Branch of the Division of Safeguards, Fuel Cycle and Environmental Research. '
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Saul Levine, Director Office of Nuclear Regulatory Research
Enclosures:
- 2. SAND 78-0724 4
e 1567 01)B