ML20028G357
| ML20028G357 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 07/31/1982 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20028G351 | List: |
| References | |
| PROC-820731, NUDOCS 8302080476 | |
| Download: ML20028G357 (5) | |
Text
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DEC 3 01982 ANNEX A GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION, OF LICENSES FOR BYPF0 DUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL l
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U. S. Nuclear Regulatory Commission Division of Fuel Cycle and Material Safety Washington, D.C.
20555 P
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July 1982 0302000476 830201 DR ADOCK 07001 s..
The instructions in this guide, in conjunction.with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior
.to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radio-activity for which the radiological considerati~ons pertinent to their use may be different. The release of such facilities or items from regulatory contro'l is considered on a case-by-case basis.
1.
The licensee shall make a reasonable effort to eliminate residual contamination.
2.
Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contam-ination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrcp which are likely to be contaminated but are of such size, constrt:cion, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
4.
Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified.
This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status.
Such requests must:
Provide detailed, specific information describing the premises, a.
equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.
b.
Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
5.
Prio~ to release of premises for unrestricted use, the iicensee shal s make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of the survey report shall be filed with the Division of Fuel Cycle and Material Safety, USNRC, Washington, D.C.
20555, and also the Administratur of the NRC Regional Office having jurisdiction. The report shou 14 be filed at least 30 days prior to the planned date of abandonment.
The curvey report shall:
a.
Identify the premises.
b.
Show that reason'able effort has been made to eliminate f
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residual contamination.
c.
Describe the scope of the survey and general procedures followed.
d.
State the findings of the survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting the facilities to confirm the survey.
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t TABLE 1 ACCEPTABLE SURFACE CONTAMINATION LEVELS NUCLIOESa AVERAGEbcf MAXIMUMbdf REMOVABLEbef 2
2 U nat, U-235 U-230, and 2
15,000 dpm a/100 cm 1,000 dpm e/100 cm associated decay products 5,000 dpm a/100 cm Transuranics, Ra-226. Ra-228 2
20 dps/100 cm2 2
300 dpm/100 cm Th-230. Th-228, Pa-231, 100 dpm/100 cm Ac-227, 1-125, I-129 Th'-na t Th-232, Sr-90, 2
- Ra-223, Ra-224 U-232, 1-126, 1000 dpm/100 cm2 3000_sipm/100 cm2 200 dpm/100 cm I-131, I-133 Deta-garna emitters.(nuclides 2
2 1000 dpm sy/100 cm2 with decay r. odes other than alpha emissinn or spontaneous 5000 dpm sy/100 cm 15,000 dpm sy/100 cm fission) except Sr-90 and others noted above.
aWhere surface contamination by both alpha-and beta-gamma-emitting nuclides exists, the limits established for a'lpha-and beta-gama-emitting nuclides should apply independently.
b s used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentatio A
CMeasurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the' average should be derived for each such object.
The maximum contamination level applies to an area of not more than 100 cm2, d
2 of surface area should be determined by wiping that area with dry filter or soft
'The amount of removable radioactive material per 100 cm absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate ins f
When removable contamination on objects of less surface ar 9 is datermined, the pertinent levels should be reduced known efficiency.
proportionally and the entire surface should be wiped.
The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should no I
I cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of 0.2 mrad /hr at total absorber.
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ANNEX B DEC 3 01982 LICENSE CONDITION FOR i
PLUTONIUM ALPHA SOURCES A."
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A.
The sources when not in use shall be stored in a closed container adequately designed and constructed to contain plutonium which might otherwise be released during storage.
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l B.
At least once every three months the licensee shall test the source for loss of plutonium in one of the following ways, using radiation detection instrumentation capable of detecting 0.005 microcurie of alpha contamination:
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(1) By measurement of the source of potential alpha contamination, Y-through surveys of the storage container and areas in which the source is used; or y,
l (2) By wiping thoroughly the external surfaces of the source y
mount, other than the radioactive surface of the source, with a piece of filter paper of high wet strength and low 1-porosity moistened with a solution which will not attack the mount and, after the paper is allowed to dry, measuring
- ,7 the radioactivity on the paper.
.j, C.
If any survey or measurement performed as required by B.(1) or B.(2) above discloses the Joss of more than 0.005 microcurie of plutonium from the source, or if a source has been damaged or broken, the source shall be deemed to be losing plutonium. The licensee shall immediately withdraw it from use, and cause-the' source to be decontaminated and repaired, or disposed of in accordance with the Commission regulations. Within five (5) days after determining a
that any source has lost plutonium, the licensee shall file a report - x with the Division of Fuel Cycle and Material Safety, U.S. Nuclear "Q
Regulatory Commission, Washingcon, D.C.
20555, describing the
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source, the test results, the extent of contamination and the a
corrective action taken. A copy of the report shall be sent to
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the Director of the nearest NRC Inspection and Enforcement Office, 1
A =
listed in Appendix D of Title 10, Code of Federal Regulations, Part 20.
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D.
Records of test results shall be kept in units of microcuries and maintained for inspection by the Commission.
l E.
Notwithstanding the periodic test required by Paragraph B, any plutonium alpha source containing not more than 0.1 microcurie 1
l of plutonium is exempted from the above requirements.
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