ML20199D931
| ML20199D931 | |
| Person / Time | |
|---|---|
| Site: | 05000135 |
| Issue date: | 10/02/1996 |
| From: | Weiss S NRC (Affiliation Not Assigned) |
| To: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20199D885 | List: |
| References | |
| NUDOCS 9711210052 | |
| Download: ML20199D931 (4) | |
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,y *, UNITED STATES j j NUCLEAR REGULATORY COMMISSION e wAsHINoToN, D.C. 20066 4 001 g
s,*****/ October 2, 1996 MEMORANDUM TO: Michael F. Weber, Chief Low-level Waste and Decommissioning Projects Branch Division of Waste Management Office of Nuclear Material Sa ty and Safeguards FRON: Seymour Weiss, Director .4244 Non-Power Reactors & Decommiss oning i Project Directorate Divi:lon of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
STATUS OF TERMINATED NON-POWER REACTOR SITE In a memorandum dated July 31, 1992, from me to John H. Austin concerning the
-status of terminated non-power reactor (NPR) sites, we provided recommendations on what action to take on a number of terminated NPR sites which were identified by Oak Ridge Associated Universities (0RAU) in the 4 report " Docket File Review" as having " Low Contrnination Potential." During '
recent discussions with the Department of the Army (Army) we became aware that the information provided by the Army about the Walter Reed Army Medical e Facility L-54 Homogeneous Reactor-(Docket No. 50-135, License No. R-851 was incorrect. The information provided to NRC concerned another reactor licensed and decommissioned by the Army located at the Walter Reed Annex.
The correct location of the site is Building 40 at ;' talter Reed Army Medical Facility in Washington, D.C. The reactor aru has been remodeled and is now used for research laboratories. The Army contact is Mr. Tim DeBey, Army Reactor Program Manager, at (703) 806-7861.
At this point, we believe that contamination surveys on floor and lower wall surfaces would be meaningless considering the modification done to the building. However, based on the results of the ORAU review, radiation field surveys of the former facility and radiation field and contamination surveys of upper walls and permanent ceiling above the suspended ceiling may be warranted.
A copy of the ORAU review is attached. If you have any questions, please contact Alexander Adams of my staff at (301) 415-1127.
Attachment:
As stated
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9711210052 971114 PDR ADC0K 05000135 W PDR
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, , REVIEW OF TEST AND RESEARCH REACTOR TERMINATED LICENSES Site: Walter Reed Army Medical Facility Address: Washington, D.C. 20012 Facility: Research Reactor Site
Contact:
Billy G. Bass, Director, Walter Reed Research Reactor NRC
Contact:
None Indicated Docket No.: 50 135 License No: R 85
- 1. Summary of Operating History Walter Reed Medical Facility (WR) operated a pool type research reactor from 1962 to January 1970. The reactor, located in northwest Washiagton, D.C.,
was a homogeneous solution type, Atomic International Model L-54 nuclear reactor.
No operating history, including spills, incidents, accidents, or fuel f ailures was provided in the Docket File.
- 2. Request for Termination of the License The Decomraissioning Plan required:
- the removal and transport of 26.5 liters of aqueous homogeneous uranyl sulphate fuel solution containing 1.325 kg of U-235 to the AEC's Chemic-1 Processing Plant near Idaho Falls, Idaho,
- removal and transport of radioactive material (e.g., reactor vessel, control rod drive mechanisms, etc.) to a land burial site,
- remova' and disposal of the concrete bio.cgical shield, teactor controls, and monitoring instrumentation, and
- decontamination ci the reactor room to make it suitable for occupancy as an unrestricted access laboratory.
- 3. Dismantling Order Date The Dismantling Order was approved by the AEC on July 6,1971.
- 4. Radiological Status Inf ormation Documentation Mentifyina Primary Contaminant The Docket File does not contain any information on the primary contaminants.
Acolicable Guidelines Sucolemental Limits. Excentions The Dismantling Plan refers to the "AEC Guidelines for Decontamination of Facilities and Equipment Prior to Pelease for Unrestricted Use, April 22,1970."
Licensee's Survev WR conducted a final survey which included exposure rate measurements on all floor and wall areas, with readings taken within 2 inches of the surf ace. Wipe surveys were performed, but no locations are given.
50-135 (1) 1
.f
. - Measurement. Samolino, and Analyses Procedures The Docket File does not discuss specific procedures. However, in the close-out inspection report, 50-135/72-01, the Region I inspector (W.H. Baunack) indicated he reviewed documents and procedures concerning administrative controls, radiation monitoring, fuel transfer and shipping, reactor system dismantling and shipment, and f acility decon'tamination.
Final Survev Data The final survey was conducted by WR personnel on February 10,1972. The maximum observed exposure rate was 0.5 mR/h, using a Victorcen MD1440 ion chamber survey meter. Wipes were taken on all floor and wall surfaces.
The maximum removable activity indicated was 269 dpm/100 cm' in the exposure room. All other wipes indicated s 215 drm/100 cm'. Wipes were counted on a R/A Lab, NL & TS Br Beckman Wide Beta 11 The absolute filter in the lower level read 1 mR/h.
The final survey report recommended that the inner sub pile room be decontaminated again and the surface be painted with epoxy paint to fix the contamination; additionally, the absolute filters be changed and disposed of since they contained fission and activation products released during dismantling. The final survey report indicated that these swults did meet AEC requirements.
The Docket File does not contain any information as to whether the recommendations were carried out.
Confirmatory Survev Results On March 16-17, 1972, an AEC Region I inspector performed a close-out inspection. The inspection consisted of a review of records, documentation of dismantling and decontamination, and procedures.
No confirmatory survey is indicated in the Docket File, Future -Jse of Facility g
Unrestricted access laboratory.
- 5. License Termination Date The AEC approved termination of the license on July 26,1972.
- 6. Federal Register Noticc No Federal Register notices were included in the Docket File.
- 7. Hazardous Waste Identified at the Site No hazardous wastes were indicated in the Docket File.
- 8. Restrictions / Conditions / Concerns No restrictions, conditions, or concerns were indicated in the Docket File.
50-135 (2) 1
4 o ..
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- 9. Does the Site Meet Present Criteria?
The Final survey indicated e <posure rates were a maximum of 0.5 mR/h. It does not meet the current 5 R/hr above background criteria.
The wipe surveys indicated a maximum of 269 dpm/100 cm'. This would meet present criteria if the primary contaminant was uranium.
The final survey indicated a recommendation to paint over contamination, to reduce activity levels. This action would not be appropriate for meeting present criterie. However, there is no indication whether the recommendations were implemented.
The Docket File does not adeouately identify the extent and location of the surveys performed, does r.ot identify if the final survey recommes,dations were implemented, and does not indicate that a confirmatory survey was performed.
Additionally. no mention is made of surveying upper walls or ceilings. Since the absolute filters were contaminated during dismantling and decontamination, it would indicate that contamination may have been airborne and been spread to upper areas.
- 10. Recommendations More detailed information on implementation of recommendations and actions would need to be provided and a more detailed survey may need to be performed to verify the adequacy of the decontamination of the site. However, due to the time elapsed since termination of operations and othar uses of radioactive materials, if used, that have occucred since license termination, it would be difficult to associate the presence of residual contamination with the R 85 license.
Prepared by: Betty M. Smith Oak Ridge Associated Universities Oak Ridge, TN 37830 bate: January 29,1991 50-135 (3)
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