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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





















"Redmond, Randy (RXQ)" wrote:



> Tom,

>

> I refer to statistics as "sadistics" and I'm certainly not an expert at any

> this.  I'll tell you what we do (DOE facility, NRC agreement state).

>

> 1.  We use the DOE 5400.5 surface contamination values (uranium 5000 dpm/100

> cm2 total and 1000 dpm/100 cm2 removable); at times we also use the 15000

> dpm/100 cm2 maximum depending on the value of the object.  Items are subject

> to at least one decon to get the levels down - the ALARA statement in

> 5400.5.  The state accepts these values for free release.  Of course if its

> metal, then we have to abide by the Richardson memo - no metal released if

> its been in a contaminated area.  The 5400.5 values are consistent with Reg

> Guide 1.86 values (even though some folks claim the 1.86 values are not for

> free release).

>

> 2.  I'm not familiar with any reference or regulatory standard on whether to

> use MDA or Lc; however, the EM-30 Performance Objective issued by DOE in the

> early 90's basically said to pick one and justify it (for volumetric

> release).  In my opinion (sadistically speaking) Lc is the correct value if

> your objective is not to release any radioactive material (at whatever

> confidence you choose).  Using Lc is impossible in the field due to varying

> backgrounds, each instrument has a different efficiency, each tech uses a

> different distance to the surface .. . .).

>

> 3.  See number 2.  The MDA value is what the instrument will detect with XX

> % confidence (most people use 95%).  If you have an MDA of 100 dpm and a

> sample is 100 dpm, then you'll have a distribution around your MDA - count

> the sample with exactly 100 dpm in it twenty times and statistically 50% of

> the time the value will be less than 100 dpm and 50% of the time the number

> will be more than 100 dpm 50% of the time (sometimes you'll get exactly 100

> dpm; sometimes, about 5% of the time using 95% confidence you'll get a value

> less than the Lc).  Anyway, using the MDA to state that nothing is there is

> not correct, that's where Lc comes in.  Check some of Brodsky's work and

> NUREG 1400 contains some good info on MDAs and Lc.

>

> Like I said, don't base anything on what I wrote - "sadistics."

>

> Randy Redmond (32458)

> Radiological Control Organization

> BWXT Y-12 L.L.C.

> Oak Ridge, TN

> 865-574-5640

>

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

> > From: Goff, Tom [SMTP:Tom.Goff@wipp.ws]

> > Sent: Tuesday, October 28, 2003 2:27 PM

> > To:   ''RadSafe Send Message'

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

> >

> > >     Title:

> > >

> > >     We are discussing using a critical level for free release surveys.

> > > Please provide answers to the following:

> > >

> > >     Are you using critical value or MDA for free release surveys of

> > > materials from your site?

> > >

> > >     Does anyone have a reference/regulatory standard on whether to use

> > > MDA or critical value for free release surveys?

> > >

> > >     Given that an MDA results in a 95% confidence in detecting

> > > contamination at the MDA value, what is the corresponding confidence if

> > > using the critical level?

> > >

> > >     I would welcome any other comments or thoughts on this.

> > >

> > >     Tom Goff

> > >

> > >

> > --------------------------------------------------------------------------

> > > ----------------------------------------------------------------

> > >     Let me know if you're ok with this.

> > >

> > >

> > >

> > >     Tom Goff

> > >     WIPP ALARA Coordinator

> > >     WIPP Integrated Waste Operations

> > >     (505) 234-8861

> > >     (fax)  234-8963

> > >     e-mail  Tom.Goff@WIPP.ws

> > >     page (505) 234-8850  (pager 479)

> > >     P.O. Box 2078

> > >     Carlsbad, NM 88221

> > >     Radiological Engineering: Anticipating Problems.....providing

> > > solutions!!!

> > >

> >

> > ************************************************************************

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