Re: Basis for Reg. Guide 1.86 limits?

["Jimmy D. Harris" <jdharris@lanl.gov>]

> Hello Jim;
>
> Several years ago at an HPS meeting I spoke with an older gentleman who
> claimed to have worked on the original table upon which the limits in
> RegGuide 1.86 was based.  Sorry, I can't remember his name right off but
> I might be able to look it up.  He told me that the limits were based on
> contamination levels that could be found on the exteriors of aircraft at
> the height of atmospheric A-bomb testing.  My memory is a little fuzzy
> as this particular point was not the main topic of our conversation.
>
> Can anyone else disabuse or add further detail?
>
> Regards,
>
> Paul
>
> Paul R. Steinmeyer
> Health Physicist
> Radiation Safety Associates, Inc.
> RSA Laboratories, Inc.
> mailto:prstein@radpro.com
>
> Jjblute1@aol.com wrote:
> > 
> > Does anyone know what the original basis for the contamination limits in Reg.
> > Guide 1.86 was?  Some possibilities...
> > 
> > Dose Based?
> > Detectability?
> > Old Military, DOE, or DOD Standard?
> > 
> > I would love a reference that discusses this but would be glad to hear
> > qualified opinions.
> > 
> > Thanks
> > 
> > Jim Blute
> > Health Physicist
> > ************************************************************************
> > The RADSAFE Frequently Asked Questions list, archives and subscription
> > information can be accessed at http://www.ehs.uiuc.edu/~rad/radsafe.html
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> The RADSAFE Frequently Asked Questions list, archives and subscription
> information can be accessed at http://www.ehs.uiuc.edu/~rad/radsafe.html


This may or may not be helpful. From NRC Health Physics Technical positions Data base.

http://www.nrc.gov/NRC/NMSS/HP/POS/index.html

Control of Radioactively Contaminated Material


HPPOS-071                                     PDR-9111210163

Title:  Control of Radioactively Contaminated Material

See IE Circular No. 81-07 entitled as above and dated May
14, 1981.  This document specifies that the monitoring of
items and materials removed from a restricted area should
be done with instruments and techniques capable of
detecting 5000 dpm/100 cm2 total and 1000 dpm/100 cm2
removable beta / gamma contamination.

IE Information Notice No. 80-22 described events at nuclear
power reactor facilities regarding the release of
radioactive contamination to unrestricted areas by trash
disposal and the sale of scrap material.  These releases
were caused by a breakdown in the contamination control
program including inadequate survey techniques, untrained
personnel performing surveys, and inappropriate material
release limits.

The recurring problems associated with minute levels of
contamination indicated that specific guidance was needed
by NRC nuclear power reactor licensees for evaluating
potential radioactive contamination and determining
appropriate methods of control.  Thus, IE Circular No.
81-07 provides guidance on the control of radioactive
contamination.  Because of the limitations of the technical
analysis supporting this guidance, it is only applicable to
nuclear power reactor facilities.

Contaminated or radioactive items and materials must be
controlled, contained, handled, used, and transferred in
accordance with applicable regulations. Items and materials
should not be removed from restricted areas until they have
been surveyed or evaluated for radioactive contamination by
a qualified individual. (A qualified individual is defined
as a person meeting the radiation protection technician
qualifications of RG 1.8, Rev. 1.)  The only exceptions are
hand-carried personal effects (e.g., notebooks and
flashlights) that are subject to the same survey
requirements as the individual possessing them.

Contamination monitoring with portable survey instruments
or laboratory measurements should be performed with
instruments and techniques (survey scanning speed, counting
times, background radiation levels) that are capable of
detecting 5000 dpm/100 cm2 total and 1000 dpm/100 cm2
removable beta / gamma contamination.  Instruments should be
calibrated with radiation sources that have energy spectrum
and instrument response characteristics consistent with the
radionuclides being measured.  If alpha contamination is
suspected, appropriate surveys and/or laboratory
measurements capable of detecting 100 dpm/100 cm2 fixed and
20 dpm/100 cm2 removable alpha activity should be performed.

In evaluating the radioactivity of inaccessible surfaces
(e.g., pipes, drain lines, etc.), measurements at
accessible points may be used.  However, this method can be
used only if the contamination at accessible points is
representative of contamination at inaccessible locations.
If this can not be demonstrated, the items should not be
released for unrestricted use.

Draft ANSI Standard 13.12 provides useful guidance for
evaluating radioactive contamination and should be
considered when establishing a contamination control and
radiation survey program.  [Editorial Note:  Draft ANSI
Standard 13.12 was never issued in final form and it is no
longer considered to be a source of useful guidance.]

Regulatory references:  10 CFR 20.201, 10 CFR 20.301, 10
CFR 20.1501, 10 CFR 20.2001

Subject codes:  7.6, 9.7

Applicability:  Reactors

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Jimmy D. Harris
Training Specialist
ESH-13

Phone 505-665-7965
Fax 505-665-4859