ML20053C361
| ML20053C361 | |
| Person / Time | |
|---|---|
| Site: | 07001193 |
| Issue date: | 04/23/1982 |
| From: | Burkhardt W, Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20053C360 | List: |
| References | |
| NUDOCS 8206010743 | |
| Download: ML20053C361 (3) | |
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g Distribution: please return original concurrence copy to FBrown SS 396 Mn, 3 b gg Docket 70-1193 PDR JEAyer NMSS R/F RTKratzke DOCKET NO.: 70-1193, Amendment 6 FCAF R/F LA File
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IERegion III (2) WBurkhardt LICENSEE:
Kerr-McGee Corporation CPeck, IE LCRouse FACILITY:
Plutonium Facility, Cinarron, Oklahoma
SUBJECT:
REVIEW OF LICENSE AhENDMENT APPLICATION FOR LIQUID WASTE VOLUME REDUCTION USING ION EXCHANGE i QUIPHENT
Background:
By application dated January 11, 1982 and supplemented March 24, 1982, Kerr-McGee requested amendment to Materials License 140. S!JM-1174 to reactivate their ion exchange equipment to provide a means of reducing their inventory of slightly contaminated liquids. The use of the ion exchange equipment by Kerr-HcGee had been previously authorized during the time they were in operation prior to the present decontauf nation activities.
Discussion:
lhe change requested by Kerr-HcGee results from the generation of contaminated liquids during the decontamination of equipment, gloveboxes and the facility.
A number of options for handling and disposing of these liquids were considered by Kerr-HcGee. The use of the ion exchange equipment was selected as the most cost-effective approach.
The ion exchange systens are located in Room 127 and Room 801. Particul ate matter will be caught on a filter prior to the liquid contacting the resin.
It is expected that most of the activity will be collected at the filter.
The effluent from the ion exchange system will be collected in existing S inch diameter stainless steel tanks. Samples will be analyzed for Americium-241 and Plutonium alpha enitters. Effluent exceeding 0.1 opc (10 CFR Part 20, Appendix B, Table 11, Column 2) will be reworked. Liquid that is 0.1 upc or less will be discharged to a previously used lagoon. Kerr-McGee does not have an llPDS permit and therefore will rely on using the lagoon as an evaporator pond.
The used ion exchange resin will be " fixed" with soda ash. The resin and prefilter contents will be packaged in accordance with Idaho Falls' TRU waste storage criteria.
Certain of the above information was obtained during a site visit April 12,1982.
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8206010 743
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"4 SURNAMEh DATEk nec e ow m nown nacu ouc OFFICIAL RECORD COPY
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- g. AP 1 2 3 1982 The present license through License Condition 140. 14 (July 15,1977) exeupts Kerr-HcGee frca the requirements of 10 CFR 70.24, Criticality Accident requiredents. An exception to this exemption was authorized for the work described in Auendment 4 dated October 6,1980. Coupliance with 10 CFR 70.24 regulation will be required for the work to be conducted under this anendcent.
The present Slim-1174 license does not provide for the administrative and technical controls for the requested activity, nor does it provide authorization to conduct this activity.
Conclusions and Recoumendationi I recomend that authorization be given Kerr-HcGee to proceed as requested subject to the following conditions:
Prior to comencing the proposed activity Kerr-licGee shall prepare A Safety Analysis Report that presents a discussion and evaluation of trie safety-related aspects of the proposed activity to include at a miniciuni a description of the proposed ion exchange systems, including feed make-up, filtration, ion exchange, eluate disposition, controls for nuclear safety, and teraperature, pressure and 1X colmn liquid level controls, as well as administrative procedures to assure safe operation. The Safety Analysis shall be, at the minisun, approved by the stealth Physics and Safety Supervisor. the Staff ticalth Physicist, the Senior Environmental and huclear Criticality Specialist and the Hanager of the Cinarron Facility.
Operating and auditing procedures shall be prepared providing the necessary details to assure that the activity is conducted in a safe and controlled uanner, including the 0.1 npc action level (10 CFR Part 20, Appendix B, Table 11, Colunn 2) for Anericium-241 and Plutonium alpha emitters for liquid discharge to the lagoon. These procedures shall be, at the minfoun, approved by the above listed personnel. The precedures shall be reasonably availabic to those personnel involved in the proposed activity.
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The exemption to the provisions of 10 CFR 70.24, that was granted under License Condition No.14 to the present license for standby operations dated July 15, 1977, is deleted during the conduct of the activities authorized by this aiaendment.
t Winston Burkhardt Advanced Fuel and Spent Fuel Licensing Branch Division of Fuel Cycle and
!iaterial Safety C:'lcinal signcd by Approved by clad C. Rouse p Leland C. Rouse, Chief Advanced Fuel and Spent Fuel Licensing Branch
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