ML20093N463
| ML20093N463 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/03/1994 |
| From: | Kokosky E DETROIT EDISON CO. |
| To: | Nirodh Shah NRC |
| Shared Package | |
| ML20093M863 | List: |
| References | |
| FOIA-IN95-349 NUDOCS 9510270249 | |
| Download: ML20093N463 (5) | |
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Date:
March 3, 19981'
. Tot Nick Shah.
l USNRC From:
.Ed Kokosky Detroit Edloon Fermi 2 4
Subject:
Immer Limit of Detection on Fermi 2 Radial, ion Protection Gamma Spectroscopy System i
'Per recent discussion, attauhed is a lower limit or detection l
(LLD) verification to Perai 2's 0!Of required criteria for l
radiosotive liquid waste sampling and analysis program.
I The veritioation has been completed in the past as A Priori count and was used to establish the present count time of 1000 seconds.
This was discussed with Al Junuska, in past inspections, and also with Dr. Currie who authored NUREG 4007.
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The first attachment is the verification. The remaining pa6es are the actual documentation of the two (2) counts and LLD reports.
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If you have any further questions, please contact as at 313-586-4933 J
Attachments i
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D'Usse ce S. Bartaan l
R. DeLong J. Tibai l
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9510270249 951023 PDR FOIA DEER.IN95-349 PDR
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Attachment j N
THRIFICATION ISOf0PR 00CM LLD'S 1000 3800ND COUNT 2000 man COUNT MN-54 SE -7 4.88E -8 3 12E -8 FE-59 5E -7 8.67E -8 7.08E -8 4
C0-60 SE -7 8.53E -8 4.26E -8 00-58 5E -7 3 782 -8 2.76E -8 ZN-65 5E -7 1.23E -7 7 14E -8 MD-99 5E -7 9.822 -8 2.18E -7 CS-134 SE -7 2.88E -8 1.44E -8 i
CS-137 SE -7 1 31E -8 1 798 -8 CE-141 SE -7 3 90E -8 1.78E -8 CE-144 SE -7 1.65E -7 8.76E -8 I-131 1E -6 2.22E -8 2.24E -8 XE-133 1E -5 4.10E -8 4.16E -8 i
XE-135 1E -5 1.88E -8 1.42E -8
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UNITS ARE NICR0 CURIE PER HILLI LITER i
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Offcite Dose Catoulation Nantal Revision 6' I
Page 3 0..19 a
I TAEJE 4.11.1.1.1-1
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RADIDACTIVE LIQUID WASTE SAW1,ING AND ANALYSIS PROGRAW i
1 f
Lower Limit Miniasm of Detection e
Liquid Release sempling Analysis Type of Aotivity (LLD)a Tyne h w3 R: may Aaalysis (uC1/s1)
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A. Entoh y te F
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Belasse Baeh Ratch Each Batah Prinolpagcomma 5 x 10-7 s
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mitt.rs i
Tanks (3) 1 Y 10 1-111 P
W Dissolved and 1 1 10-5 l
One Satch/N Entrained Gases (Canna taitters)
P N
5-1 1 1 10-5 l
l E_sch Satch 8'- ^^=1te Geoss Aisha 1 I 10*I d
P Q
Sr-49,Se-90 5 I to i.
Bech Batch Composite Fe-55 1 2 10~0 d
l 5 Contt Releases N
PrincipegGanna 5 1 104 Circulating NA Smitters d
i Unter Composite Systes (if I-tit i I 10 3
contaminated)
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V N
Dissolved and 1 I 10-5 i
Grab sample Entrained Gases (a
amatters) l N
s 1 10-5 n
composite oro alg.
1 x 10-7 8
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3r-89. Se-90 5 I to EA Composite Fe-55 1 1 10-6 d
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NuclearProduction-Fermiht 00G5-3 0 j,
Offsite Dose Calculation Manual Revision'6 Page 3 0-30 i
TABLE 4.11.1.1.1-1 (Continued)
I TABLE WTATION i'
"The 11D'is defined, for purposes of these controls, as the smallest eenoentration of radioactive material in a easple that will yield a act sount, above system background, that will to detected with 955 probability vita caly j.
$$ probability of falsely concluding that a blank observation represents a
- real" signal.
j For a particular sensurement systes, tich any tacaude regiochemical asperations q
4.66 ab t
11D a-g
- V
- 2.22 s 100
- I
- esp (- At) j lineret' LLD is the "a priori" lower limit of detection as defined soove, as alcrocuries per unit mass or volume, e is the standard deviation of the background counting rate or of the scounting rate of a blank sample as appropriate, as counts per minute, l
E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 6 is the number of disintegrations per minute per microcurie, I
2.22 x 10 I is the fractional radiochemical yield, when applicable, l
Aistheradioactivedecayconstantfortheparticularradionuolide,and l
t for plant effluents is the elapsed time between the midpoint of semple collection and time of counting.
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' Typical values of E, f. Yi and t should be used in the calculation.
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It should be recognised that the 11D is defined as an g gri.ori (before the fact) limit representing the capability of a seaswesent system and act as sa a sosteriori (after the fact) limit for a particular esasurement.
l bA batch release is the discharse of liquid unstes of a discrete volume.
i Prior to sampling for analyses, each batch shall be isolated, and then tharoughly mixed by a method described in the 00CN to assure representative easpling.
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Nuclear Production - Fermi 2 CDCH-3 0 Offsite Dose Calculation Manual Revision 6
- Page 3 0-21 I
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.i TABLE 4.11.1.1.1-1 (Continued)
TABLE IO7ATION l
cthe principal saama esitters for which the LLD spooifloation applies esclusively are: Its-54. Fe-59. Co-58. Co-60. 2n-45. No-99 Cs-134. Cs-137, Co-141, and Co-144. This does not mean that only these nuclides are to be eensidered. Other peaks that are identifiable, tesother with those of the above nuclides, shall also be analysed and reported la the Annual Radioactive Effluent Release Report pursuant to Control $.9.1.8.
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dA compesite anaple is one in which the quantity of 11guld samples is proportional to the quantity of 11guld waste discharged and in uhleh the method i
of sampling employed results in a specimen that is representative of the
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liquids released. This any be socomplished through composites of grab staples i
obtained prior to diacharge after the tanks have been recirculated.
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'A continuous release is the discharge of liquid unstes of a nondiscrete voluse; e.g., from a volums of a system that has an input flow during the continuous release.
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