RE: MDA vs. Critical level for DOE Free Release surveys

["Redmond, Randy (RXQ)" <redmondrr@Y12.doe.gov>]

It's been several years (1991) since I worked the power plants (14 years),

but we released items at levels equivalent to 5000 dpm/100 cm2 total and

1000 dpm/100 cm2 removable (this was at just about every plant I worked and

there were quite a few; some went with lower removable, e.g., 200 dpm/100

cm2).  Generally when using a beta-gamma frisker (RM-14 was typical in those

days) if the total and/or removable was less than 100 counts per minute the

item was released.  Assuming a typical GM probe in those days was 20 cm2 and

the efficiency was 10 percent, this equates to 5000 total and 1000 removable

(by smear).



Randy



> -----Original Message-----

> From:	William V Lipton [SMTP:liptonw@dteenergy.com]

> Sent:	Thursday, October 30, 2003 7:09 AM

> To:	BLHamrick@AOL.COM

> Cc:	redmondrr@Y12.doe.gov; Tom.Goff@wipp.ws;

> radsafe@list.Vanderbilt.Edu; oliverrw@Y12.doe.gov; wicalsa@Y12.doe.gov

> Subject:	Re: MDA vs. Critical level for DOE Free Release surveys

> 

> I can't figure out why materials licensees have it easier than power

> plants, but I stand corrected; thanx. 

> 

> The opinions expressed are strictly mine. 

> It's not about dose, it's about trust. 

> Curies forever. 

> 

> Bill Lipton 

> liptonw@dteenergy.com 

>   

> 

> BLHamrick@AOL.COM wrote: 

> 

> 	 In a message dated 10/29/2003 7:02:02 AM Pacific Standard Time,

> liptonw@DTEENERGY.COM writes: 

> 

> 		NRC licensees, especially power reactor licensees are not

> allowed to free 

> 		release any licensed material.

> 

> 	Ooo, not exactly true.  NRC materials licensees, licensed for the

> use of unsealed materials generally commit to unrestricted area limits

> pursuant to procedures contained in the NUREG 1556 series.  These limits

> are used for the release of surface-contaminated objects from the

> restricted area to unrestricted use.  These limits are similar to the old

> Reg. Guide 1.86 values that were adopted for use by materials licensees in

> �EURoeGuidelines for Decontamination of Facilities and Equipment Prior to

> Release for Unrestricted Use or Termination of Licenses for Byproduct,

> Source, and Special Nuclear Material, Policy and Guidance Directive�EUR�

> (FC 83-23, November 4, 1983). A direct quote from the current guidance

> (NUREG 1556) says: "When equipment or facilities that are potentially

> contaminated are to be released for unrestricted use, the above table

> provides the maximum acceptable residual levels.   To the extent

> practicable, it is appropriate to decontaminate to below these levels.

> Surface contamination surveys should be conducted for both removable and

> fixed contamination before these facilities or equipment are released from

> restricted to unrestricted use, to ensure that they meet these limits." In

> addition, volumetrically contaminated materials are routinely released

> from NRC licensees, after a case-by-case approval.  See, e.g., STP 03-003,

> available at:  <http://www.hsrd.ornl.gov/nrc/home.html>, which states:

> "For prospective cases or cases that are not grand-fathered - where

> proposed offsite concrete releases are not covered under an existing

> decommissioning plan, 20.2002 disposal, license termination plan, or other

> specific license condition, controlled release of concrete with volumetric

> sources of contamination may be approved under a criterion of a "few mrem"

> (pursuant to a 20.2002 procedure, decommissioning plan, license

> termination plan, or other specific license amendment) rather than use of

> license termination criteria either in Subpart E of 10 CFR Part 20 or in

> the SDMP Action Plan." Thus, BRC failed only as a GENERIC policy.  It has

> been implemented in one form or another continuously since the AEA was

> enacted in 1946. Barbara

> 

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