ML19290E852
| ML19290E852 | |
| Person / Time | |
|---|---|
| Site: | 05000375 |
| Issue date: | 03/10/1980 |
| From: | Remley M ROCKWELL INTERNATIONAL CORP. |
| To: | Gammill W Office of Nuclear Reactor Regulation |
| References | |
| 80ESG-2374, NUDOCS 8003170154 | |
| Download: ML19290E852 (7) | |
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Energy Systems Group 8900 De soto Avenue s
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Canoga Park. CA 91304 Teieceone9213) 341-1 Rockwell TWX. 910-494-1237 Teiet ta1017 International March 10, 1980 In reply refer to 80ESG-2374 Mr. William Gammill Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Gammill:
Subject:
Application for an Order to Authorize Dismantling of the Facility, lisposal of the Component Parts, and Voluntary Surrender of Facility License No. R-118, Docket No. 50-375 In accord with Section 50.82 of 10 CFR Part 50, Rockwell International Corpcration hereby submits an application for authority to dismantle the L-85 Facility, dispose of its component parts, and surrender volun-tarily Facility License No. R-118.
Enclosed are three original and 19 copies of our application, together with the supporting statement to describe the current status of the facility and the dismantling plan to assure that the dismantling of the facility and disposal of the parts will be in accordance with the requirements in 10 CFR Part 50 and will not be inimical to the common defense and security cr to the health and safety of the public.
In accord with Section 170.22 of 10 CFR Part 170, we have determined that this application is for a Class IV Amendment to a research reactor facility license, and therefore requires submission of a fee of $6,000.
Enclosed is our check payable to the Nuclear Regulatory Commission in the amount of $6,000 in payment of that fee.
If you have any questions concerning the physical status of the facility or this application, please contact me at (213) 341-1000, Extension 2238.
Sincerely,
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. Renil l, Dire tbr Health, Safe (ty and,)diation Services j
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APPLICATION TO AUTHORIZE THE DISMAf1TLING 0F THE L-85 FACILITY, DISPOSAL OF ITS COMP 0NEf4T PARTS, AND VOLUNTARY SURREflDER OF FACILITY LICENSE NO. R-118, DOCKET N0. 50-375 Rockwell International Corporation, acting through its Energy Systems Group, hereby submits this Application to Authorize the Dismantling of the L-85 Facility, Disposal of the Component Parts, and the Voluntary Surrender of Facility License No. R-118.
This application is made pursuant to the Atomic Energy Act of 1954. Title 10, CFR, Part 50, Section 50.82.
Licensee applicant believes that all necessary steps with respect to disposal of radioactive material, treatment of fuel solution, necessary decontamination of the site, and other actions required have been planned and will be executed to provide reasonable assorance that the facility will be placed in a condition for release for unrestricted use. With completion of the planned activities, the facility will be in a condition which will not be inimical to the common defense and security and to the health and safety of the public.
Attached hereto is a statement in support of this application.
I certify that the information contained herein is correct to the best of our knowledge and belief.
ROCKWELL INTERNATIONAL CORPORATION Energy Systems Group
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('R. G., Jones
'-Vice' President and Controller Finance and Administration Attachment
STATE OF CALIFORf11A COUf4TY OF LOS ANGELES Subscribed and sworn to before me on this /r c /. day of r N) o - [, 1980 J,
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I, J. H. Brindley, certify that I am an Assistant Secretary of the Corporation named herein as Applicant; that R. G. Jones who signed this Application on behalf of the Applicant, was then Vice President, Finance and Administration, Energy Systems Group of said Corporation; that said Application was duly signed for and in behalf of said Corporation by authority of its governing body, and is within the secpe of its corporate powers.
SEAL T
L3 J.j Brindley Assistant Secretary
STATEMENT IN SUPPORT CF APPLICATION FOR AUTHORITY TO DISMANTLE THE L-85 FACILITY, DISPOSE OF ITS COMPONENT PARTS, AND SURRENDER VOLUNTARILY FACILITY LICENSE R-118 DOCKET 50-375
1.0 INTRODUCTION
1.1 SCOPE AND PURPOSE OF REPORT The L-85 Reactor, located at the Rockwell International Santa Susana Field Laboratory, has been licensed as an operating facility since January 5,1972.
From 1952 until 1972 it was an AEC-owned facility.
It was located at Downey, California, under the designation WBNS from 1952 until 1956, when it was moved to its present location, modified to increase the power level and redesignated as the AE-6 Reactor.
Energy Systems Group has determined that it is no longer desirable to main-tain licensed possession of the facility.
Therefore, the purpose of this report is to present a plan for dismantling the facility and disposing of the component parts and to provide supporting information for an application to surrender voluntarily Facility License No. R-118, Docket No. 50-375.
1.2 REACTOR FACILITY The L-85 Reactor is located in Building T093 of the Rockwell International Santa Susana Field Laboratory. A detailed description of the facility and reactor is presented in the Safety Analysis Report.*
1.3 REACTOR The L-85 Reactor, which is of the water boiler type, has an operational limit of 3 kW thermal. The fuel is fully enriched uranyl sulfate dissolved in
- Swanson, V., " Safety Analysis Report for the L-85 Nuclear Examination Reactor,"
AI-70-73, September 24, 1971
water, and is contained in a spherical stainless steel core.
The core is reflected by a surrounding cylinder of graphite.
Shielding is provided by ordinary concrete.
Reactor control is provided by two safety rods and two control rods, which operate horizontally in the reflector region outside the core.
The two safety rods are driven in by gravity through a cable and pulley system on a scram condition.
2.0 FACILITY STATUS The reactor has been operated as needed to perform neutron radiography and training functions. Most neutron radiography operations are 45-60 minutes in duration, at a power level of 2.75 kW.
Most of the training operations are for a few minutes at power levels of 1-5 watts.
The integrated power output for 1978 was 561 kW-hours and for 1979 was 584 kW-hours.
Values for 1972-1977 are approxi-mately the same.
Operation of the reactor was discontinued on February 29, 1980.
Except for required periodic checks, the reactor will be maintained in a shutdown con-dition, with fuel in place, until approval for dismantling has been obtained and the fuel solution has cooled sufficiently for safe drainage to shipping con-235 tainers.
The fuel solution contains 788 grams of U in the form of-93%
enriched uranyl sulfate.
All reactor instrumentation will remain in service and all periodic checks and tests will be performed until after the fuel is drained from the reactor.
3.0 DISMANTLING PLAN The L-85 Reactor will be dismantled by Energy Systems Group personnel in accordance with procedures which will have been developed and subjected to appro-priate internal review. These procedures will outline a method and schedule for removal of the fuel, reactor component parts and all contaminated or activated concrete or structural materials.
The procedures will also include any require-ments for protective clothing and precautions to prevent excess exposure of personnel to radiation fields and radioactive contamination.
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9 All equipment and materials which are to be released for unrestricted use must meet the criteria listed in Table I.
Equipment and material which cannot be decontaminated to the levels of Table I will either be disposed of at a licensed radioactive disposal site or will be stored or used at another facility where limited radioactive material is acceptable and appropriate authorization is obtained.
Possession of the radioactive material is authorized under Energy Systems Group's California Radioactive Material License No. 0015-59.
It is expected that the concrete shielding and floor immediately adjacent to the reactor will have to be removed and packaged for disposal at a licensed radio-active disposal site.
TABLE I CONTAMINATION LIMITS FOR RELEASE OF FACILITIES AND EQUIPMENT FOR UNRESTRICTED USE Total Renovable 2
Beta-Gamma Emitters 0.1 mrad /hr 100 dpm/100 cm at I cm with 2
7 mg/cm absorber 2
2 Alpha Emitters 100 dpm/100 cm 20 dpm/100 cm Note:
The above limits for release of facilities and equipment are more restrictive than the limits stated in the NRC Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors" On completion of the removal of all components of the L-65 Reactor, the facility will be surveyed to assure that no area is contaminated or activated in excess of levels which wouli' prevent release for unrestricted use.
Possession of the fuel material will be retained under our Special Nuclear Material License No. SNM-21 until appropriate disposition is made.
4.0 CONCLUSION
As described above, the reactor will be disassembled into its component parts. Those components which meet the criteria for release for unrestricted 3
use will be released to Energy Systems Group Property Management to be available for productive use in any appropriate projects.
Those items which do not meet the criteria for unrestricted use will be packaged for burial at a licensed radioactive material disposal site or used in activities where the radioactivity is duly authorized and acceptable.
Completion of this disposal activity, together with a final survey of the facility to assure that there is no radioactive contamination in excess of the criteria for unrestric-ted use, will eliminate any further requirements for facility surveillance and licensing under 10 CFR Part 50.
Therefore, it is concluded that under the above described conditions, License R-118 for the L-85 Reactor Facility can be voluntarily surrendered without undue risk to the conmon iefense and the health and safety of the public.
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