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RE: MDA vs. Critical level for DOE Free Release surveys
- To: "'William V Lipton'" <liptonw@DTEENERGY.COM>, "Redmond, Randy (RXQ)" <redmondrr@Y12.doe.gov>
- Subject: RE: MDA vs. Critical level for DOE Free Release surveys
- From: "Redmond, Randy (RXQ)" <redmondrr@Y12.doe.gov>
- Date: Wed, 29 Oct 2003 10:37:11 -0500
- Cc: "'Goff, Tom'" <Tom.Goff@wipp.ws>, "''RadSafe Send Message'" <radsafe@list.Vanderbilt.Edu>,"Oliver, Bobby (OLV)" <oliverrw@Y12.doe.gov>, "Wical, Scott Andrew (S3W)" <wicalsa@Y12.doe.gov>
- Reply-To: "Redmond, Randy (RXQ)" <redmondrr@Y12.doe.gov>
- Sender: owner-radsafe@list.Vanderbilt.Edu
We'll let the archives speak for themselves.
Have a good day Bill.
> -----Original Message-----
> From: William V Lipton [SMTP:liptonw@dteenergy.com]
> Sent: Wednesday, October 29, 2003 10:14 AM
> To: Redmond, Randy (RXQ)
> Cc: 'Goff, Tom'; ''RadSafe Send Message'; Oliver, Bobby (OLV); Wical,
> Scott Andrew (S3W)
> Subject: Re: MDA vs. Critical level for DOE Free Release surveys
>
> I covered: 1. TN versus NRC release standards. 2. HPPOS-72. 3. (The
> need
> to specify Type 1 and Type 2 errors separately.
>
> Which of these did you cover?
>
> The opinions expressed are strictly mine.
> It's not about dose, it's about trust.
> Curies forever.
>
> Bill Lipton
> liptonw@dteenergy.com
>
> "Redmond, Randy (RXQ)" wrote:
>
> > Bill, I believe you repeated what I said.
> >
> > > -----Original Message-----
> > > From: William V Lipton [SMTP:liptonw@dteenergy.com]
> > > Sent: Wednesday, October 29, 2003 9:52 AM
> > > To: Redmond, Randy (RXQ)
> > > Cc: 'Goff, Tom'; ''RadSafe Send Message'; Oliver, Bobby (OLV);
> Wical,
> > > Scott Andrew (S3W)
> > > Subject: Re: MDA vs. Critical level for DOE Free Release surveys
> > >
> > > 1. NRC licensees, especially power reactor licensees are not allowed
> to
> > > free
> > > release any licensed material. See HPPOS 72 - I pasted in a copy,
> below.
> > > TN is
> > > known for its easygoing free release standards. It's no coincidence
> that
> > > so
> > > many radwaste, "green is clean" processors are located, there.
> > >
> > > 2. When you refer to, "The MDA value is what the instrument will
> detect
> > > with XX
> > > % confidence (most people use 95%)..." keep in mind that it is
> necessary
> > > to
> > > specify confidence levels, separately, for Type 1 (false positive) and
> > > Type 2
> > > (false negative) errors. You seem to imply that the 95% level applies
> to
> > > both.
> > > Often, the levels are the same, but this is not necessarily true,
> > > especially
> > > under MARSSIM.
> > >
> > > The opinions expressed are strictly mine.
> > > It's not about dose, it's about trust.
> > > Curies forever.
> > >
> > > Bill Lipton
> > > liptonw@dteenergy.com
> > >
> > > Guide on "How Hard You Have to Look" as Part of Radioactive
> > > Contamination C ontrol Program
> > >
> > > HPPOS-072 PDR-9111210170
> > >
> > > Title: Guide on "How Hard You Have to Look" as Part of
> > > Radioactive Contamination Control Program
> > >
> > > See the letter from R. C. DeYoung to E. D. Swartz
> > > (Commonwealth Edison Company) dated May 18, 1982. The
> > > intent of IE Circular No. 81-07 (IEC-81-07) was to give
> > > guidance on "how hard you have to look" for radioactivity
> > > when the use of portable survey equipment is necessary as
> > > part of a radioactive materials control program. The
> > > detection limits in IE Circular No. 81-07 (IEC-81-07) are
> > > not release limits. The health physics position was
> > > written in the context of 10 CFR 20.201, 20.301, and
> > > 20.302, but it also applies to the "new" 10 CFR Part 20,
> > > Sections 20.1501, 20.2001, and 20.2002. HPPOS-071 and
> > > HPPOS-73 contain related topics.
> > >
> > > The intent of IEC-81-07 (see HPPOS-071) was to provide
> > > guidance on acceptable limits of detection of portable
> > > survey equipment; thus, defining "how hard you have to
> > > look" for radioactivity when the use of portable survey
> > > equipment is necessitated as part of a radioactive
> > > materials control program. Low background, fixed
> > > laboratory counting equipment can readily detect levels of
> > > radioactivity several orders of magnitude less than the
> > > detection levels discussed in the circular. However, the
> > > use of laboratory counting equipment is not always
> > > practical for all situations and portable survey equipment
> > > may need to be employed.
> > >
> > > The circular did not establish criteria for releasing
> > > radioactivity contaminated materials from restricted areas
> > > for unrestricted use. The regulations applicable to
> > > nuclear power reactor licensees do not provide for release
> > > of materials for unrestricted use that are known to be
> > > radioactively contaminated at any level. Authorization for
> > > disposal of specific radioactively contaminated materials
> > > may be requested as specified in 10 CFR 20.302 [or 10 CFR
> > > 20.2002]. The Commission recognizes the need for "de
> > > minimis" classification of wastes and has initiated work to
> > > define "de minimis" levels on a specific waste basis. This
> > > work is continuing. [Note: The statement concerning "de
> > > minimis" classification of wastes is related to the below
> > > regulatory concern (BRC) policy, which has now been
> > > withdrawn.]
> > >
> > > With regards to your request for concurrence with release
> > > criteria in your "Radiation Protection Standards," we
> > > cannot concur since the regulations do not contain release
> > > criteria provisions as described above. The method
> > > available to you for obtaining authorized release limits is
> > > to submit to the Office of Nuclear Reactor Regulation (NRR)
> > > a request for license amendment that addresses specific
> > > release limits. Although we have sent a copy of your
> > > letter to NRR for information, the excerpt you provided
> > > from your "Radiation Protection Standards" lacks specifics
> > > which would support a request for specific release limits
> > > for radioactively contaminated materials.
> > >
> > > If you desire a specific authorization for disposal or a
> > > license amendment for specific release limits, please
> > > direct your request to the Office of Nuclear Reactor
> > > Regulation.
> > >
> > > Regulatory references: 10 CFR 20.201, 10 CFR 20.301, 10
> > > CFR 20.302, 10 CFR 20.1501, 10 CFR 20.2001, 10 CFR 20.2002
> > >
> > > Subject codes: 7.6, 9.7
> > >
> > > Applicability: Reactors
> > >
>
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