Errata to Rev 1 to Reg Guide 4.16, Monitoring & Reporting Radioactivity in Releases of Radioactive Matls in Liquid & Gaseous Effluents from Nuclear Fuel Processing & Fabrication Plants & UF6 Production Plants| ML20212Q095 |
| Person / Time |
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| Issue date: |
08/31/1986 |
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| From: |
NRC |
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| To: |
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| References |
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| REGGD-04.016, REGGD-4.016, NUDOCS 8609030427 |
| Download: ML20212Q095 (3) |
|
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+ 0 UNITED STATES NUCLEAR REGULATORY COMMISSION
[%.', ) - ( ' -;,,g j WASHINGTON, D. C. 20S$5 O't.'.'../
August 1986 ERRATA Regulatory Guide 4.16, Revision 1 December 1985 MONITORING AND REPORTING RADI0 ACTIVITY IN RELEASES OF RADI0 ACTIVE MATERIALS IN LIQUID AND GASE0US EFFLUENTS FROM NUCLEAR FUEL PROCESSING AND FABRICATION PLANTS AND URANIUM HEXAFLUORIDE PRODUCTION PLANTS O As a result of public comment and additional staff review, the quantity 2.71 in the numerator of the expression for LLD on page 4.16-7 is being removed, and a reference to a report that explains the conditions under which the use of this quantity is appropriate is being added. Please replace page 4.16-7 (and its backup, page 4.16-8) with the attached pages.
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APPENDIX A
\ Lower Limit of Detection For the purposes of this guide, the lower limit of Y is the fractional radiochemical yield (when applicable);
detection (LLD) is defined as the smallest concentration of radioactive material sampled that has a 95% probabil- A is the radioactive decay constan; for ity of being detected. (Radioactive material is " detected" the particular radionuclide, and if it yields an instrument response that leads the analyst At is the clapsed time between the mid-to conclude that activity above the system background point of sample collection and the time of counting.
is present.)
For a particular measurement system (which may The value of Sb used in the calculation of the LLD incit.de radiochemical separation). for a particular measurement system should be based on the actual observed variance of the instrument back-4.66S b gr und counting rate rather than on an unverified LLD = theoretically predicted variance.
3.7 x 104EVY exp(- A At)
Since the LLD is a function of sample, volume, where counting efficiency, radiochemical yield, etc., it may vary for different sampling and analysis procedures. Whenever LLD is the lower limit of detection (micro- there is a significant change in the parameters of the curies per milliliter); measurement system, the LLD should be recalculated.*
Sg is the standard deviation of the instru-ment background counting rate (ccunts .,
For a more complete discussion of the LLD, see EAfL Proce.
per second)'. dures Afanual,11. L. Volchok and G. dePlanque, editors, U.S.
3.7 x 10 4 is the number of dismtegrations per Department of Enersy (revised annually); L. A. Currie," Limits for Quahtative Detection and Quantitative Determination-Application second per microcurie.* to Radiochemistry," Analytkal Chemistry, Vol. 40, pp. sS6-s93 E, is the counting efficiency (counts per (Table 11),1968; and NURII/CR-4007," Lower Limit or Detection:
disintegration).
Definitionand Effluent andEnvironmental flaboration of Measurements." a Proposed Position for Radiolofical prepared for NR by is the sample volume (milliliters); L. A. Currie (Chap. U. Sect.D.2;Oiap.W. Sect.C.8), September 1964.
V l
4.16-7
APPENDIX B Example of Format For Reporting Effluent Data'
- 1. CONTINUOUSLY SAMPLED STACKS For each release point, report the followmg informatiosa:
- a. Reportmg period
- b. Stack location (process or area)
- c. Stack flow rate (m3/sec) or total stack flow (m3) (if stack is not in continuous use)
Radoactivity (Ci)
Gross alpha Gross beta Concentration Error Estimate 3 LLD 4 Quantity Released Radionuclide 2 (p Ci/ml) (! p Ci/ml) (p Ci/ml) (Ci) To MPC U-2 M
_?. U-235
? U-238 oc I Thas table is foe illustration only and is not a complete listing of data to be reported. Supplemental and explanatory information should also be submitted. (See footnote 2 and text of guide, for instance, sections 2.I and 2.2.)
2 This list of radioactivity and raJionuclides is typical for uranium fuel fabrication plants. It is not complete for all I.censees, nor will all licensees need to report the radioactivity or radio-auctiJes shown. (For example, some licensees reay need to report natural uranium, isotopes of plutonium, etc., and some hcensees may not need to report gross beta activity.)
Estimates of ranJom errors should be calculated at the 95% confidence interval. Significant systematic error should be reported,if appropriate,in supplementalinformation.
Calculation of lower limits of detection (LLD) should be shown in supplemental information.
UNITED STATES nast etass man NUCLEAR REGULATORY COMMISSION N$taGj,D_ FEES PalD WASHINGTON, D.C. 20555 was ,D c ,,
OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. $300 1 10P 120555064215 u , t4 T 04 L DUP OC 20555 yASHINGTON I
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