ML20004B791
| ML20004B791 | |
| Person / Time | |
|---|---|
| Site: | Wood River Junction |
| Issue date: | 05/21/1981 |
| From: | Stevenson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20004B788 | List: |
| References | |
| NUDOCS 8106010047 | |
| Download: ML20004B791 (1) | |
Text
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Distribution:..
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o Docket File 70-820
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MAY 21 1981
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SH0 NMSS r/f FCUF r/f FCUP r/f RLStevenson (2)
DOCKET NO: 70-820 LTyson WTCrow APPLICANT: United Nuclear Corporation IEHQ(2)
UNC Recovery Systems Division ACabell DWeiss FACILITY:
Fuel Recovery Plant WKinnsy, R:I Wood River Junction, Rhode Island RGregg, UNC.
SUBJECT:
REVIEW OF AMENDMENT APPLICATION DATED APRIL 24,1981, TO DELETE CRITICALITY ALARM REQUIREMENT AND REQUIREMENT FOR PERIODIC VISITS BY CRITICALITY SPECIALISTS, JOB 07000820A135 I.
Background
The Wood River Junction Plant is being decontaminated for decomissioning, and essentially all fuel processing equipment has been removed. Consequent-ly, the fissile material inventory consists. of less than 200 grams of U-235 as gama counting standards and larger amounts at very low concen-trations in lagoon solids or in packaged wastes awaiting shipment. The concentratigrs of U-235-in the wastes are extremely low compared to the minimum critical concentration of about 11 grams per liter and recovery of the U-235 from the wastes ~is not planned. The subject application requests deletion of the criticality alann requirements of Section 70.24 of Part 70 arid of the requirement for periodic on-site visits by crit-icality specialists. Appropriately revised pages in Sectiors 200 and 400 were provided with the application.
II. Discussion The amounts and distribution of U-235 on the plant site r.d site activities are such that accidental criticality is not credible. There is thus no
~ eason for maintaining a criticality accident alarm system or requiring rthat the licensee have regular on-site coverage by criticality specialists.
III.
Conclusion and Recommendation The form and quantity of special nuclear material are not sufficient to justify continued criticality alarm coverage or periodic criticality specialist coverage of the Wood River Junction site.
It is recomended that an amendment to License SNM-777 be issued to delete those requirements.
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