Text

Calculation of Gamma Skin Dose for Na-24 Skin Contamination Incident
	ML20034C758
Person / Time
Site:	FitzPatrick
Issue date:	04/04/1990
From:	Sykes J; PORTER CONSULTANTS, INC.
To:	;
Shared Package
ML20034B797	List: ML20034B796; ML20034B801; ML20034C758;
References
	PCI-TR-323, NUDOCS 9005090114
	Download: ML20034C758 (61)
	v • d • e

{{#Wiki_filter:~ b= D : PHONE, t15 896 5353 ^ RORTER CONSULTANTS,iInc.- ^ Radiological Protection and Environmental Services 125 ARGYLE ROAD AR DMORE, PA. 19003 - PCI-TR-323 CALCULATION OF GAMMA SKIN DOSE FOR MNa SKIN. CONTAMINATION INCIDENT. April 4,1990; q Prepared for:. i George J. Vargo, Ph.D., CHP Radiological and Environmental Services Superintendent James A. FitzPatrick Nuclear Power Plant, New York Power Authority. Lycoming, New York 13093-Prepared by: John Sykes III Consultant Health Physicist 1 i Reviewed by: I ' Sydney,' W. Porter, Jr., CHP President y l, i

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cAtCut4 TION 08 oAMMA stiN oOsE FOR 24N. stiN CONTAMINATION INCIDENT 1.0 EXECUTIVE

SUMMARY

1.1 On March 8,1990 at 16:05 a skin contamination incident occurred at' the James -A. Fitr. Patrick Nuclear Power Plant in Lycoming. NY. The incident occurred when a technician inadvertently contaminated a small area on his left thumb pad with a concentrated solution 24 of Na. The contaminated area was determined to be roughly a 2 cm x 2 cm square on the affected digit. De technician was appropriately decontaminated, and the activity ast;.yed. Preilminary calculation indicated that the skin on the thumb may have been overexposed to' (primarily)p radiation. D 1.2 The dose assessment to the individual consists of three parts: 1.2.1 Determining the actMty on the finger. 1.2.2 Determining the'p dose component. .l 1 1.2.3 Determining the y dose component.- This report was prepared to evaluate the y component of the dose to the tissue below the contaminated area. It should be noted that since each of the three parts of the dose O assessment were performed independently, this report calculates the y dose relative to a unit 24 activity (1 yCl) of Na.' i 1.3 The dose calculations performed for this assessment were performed primarily using the- }" shielding code QAD. COOP, a point kernel, combinatorial geometry shielding code using a geometric progression buildup modeli This code is the latest version of the QAD-P5 code,. which has been in wide use since 1%7 [Ma 1%7]. The current version of the code was last - revised in October,1988 and the documentation updated in March,1989 [RSIC 1989]. 1.4 A very conservative (high) dose rate conversion factor for the skin was' calculated to be 165 mradpCI.hr at a tissue depth of 0.004 cm (4 mgem ),,156 mrad /gCl hr at 0.007 cm 2 (7 mg/cm ) 91 mrad /gCi.hr at 0.064 cm (64 mg/cm ): and 27 mrad /gCl.hr at' O.500 cm 2 2 (500 mg/cm ), all averaged over 1 cm. The input data is enclosed as Attachment 5.1 and the i assumptions used and limitations of this model are discussed in Section 2.3, below. i

2.0 DESCRIPTION

OF DOSIMETRY MODEL 2.1 SOURCE - RECEPTOR GEOMETRY The contamination was modeled as a 2 x 2 cm square source located at one vertex of a 3 cm ' diameter cylinder of water (see Attachment 5.2). The precise geometry is unimportant for - a point kernel model as long as the material and geometry between the source and receptor are accurate. The source was originally organized as a 20 x 20 array, for a total of 400 input points. However, the resulting dose rates were found to be very dependant upon the grid coordinates of the receptors' due to the small source to receptor distances invoh'ed. Therefore the model was changed to a 100 x 100 array with 10,000 input points. The dose was then calculated to a point on the axis of the cylinder at several depths (0.004,0.007, Page 1 of 3 q

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4.0 REFERENCES

Malenfant, R.E.11%7. QAD: A series of point kernel general purpose shielding programs. LA 3572.. les Alamos Scientific Laboratory. Available from: NTIS, Springficid, VA. l Radiation Shielding Information Center.1989.. QAD-COOP: A mmbinatorial geometry version of - QAD PSA, a point kernel mde system for neutron and gamma ray shielding calculations using the GP buildup factor. Oak Ridge National Laboratory, Oak Ridge,'IN. - 5.0 ATTACHMENTS 5.1. Input Data for QAD-CGGP Runs 5.2 Geometric Model used for QAD COOP Input l. i-5.3 Dose Rafc Matrix for 0.004,0.007,0.064 & 0.500 cm Depths l 5.4 Oraph of Dose Rates vs. Skin Depth 5.5 Preliminary Results of non Charged Particle Equilibrium Dose Rate Calculations Performed C by the University of Wisconsin Medical Physics Department Using the EOS-IV Nonte-Carlo = Computer Code l t .{ \\ i-

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1,V Y pdeterL Conouttante, Inc. 1as AnCYL.E COAO AROMORE. PA.19003. ra.eu.in PCI TR-323 '~ g1.1-L INPUT DATA FOR QAD-CGGP RUNS 5.1.1 0.004 cm RUN Na-24 Gamma Skin Dose @ 0.004 cm Depth 100 In 100 2 -I '1 2' 9.1 1 2 - 0 0 -- -1 1000 0 3.7E4 0. O. O. O.- 0. O. 1.0 : -0.98 4% ^-0,94 0.92 0.90 ~ 0.88 - -0.86 0.84 - 0.82 4 80 -0.78 ' 0.76 ' 0.74. 0.72 -0.70 - 0.68 466 -0.64 -0.62 -0.60 ' 0.58 0.56- -0.54 -0.52 0.50 -0.48. -0.46 - 0.44 - -0.42 ' c 0.40. =-0.38 0.36 0.34 ' 0.32 0.30 -0.28 0.16 0.241 -0.22 0.20 - 0.18 -0.16 0.14 -0.12 -0.10 0.08 -0.06 - 4 04 0.02 - 0.00 ' O.02 : 0.04 x 0.06 0.08 0.10 0.12 0.14 0.16 - 0.18 - 0.20 ' O.22 0.24 0.26 0.28 0.30 0.32 10.34 0.36 -- 0.38 0.40 ' O.42 ' O.44 0.46 0.48 0.50 0.52 - 0.54, 0.56-0.58 0.60 0.62 0.64 0.66 - 0.68 0.70 0.72 0.74-0.76 - 0.78 ' O.80 0.82 0.84 0.86 0.88 _ 0.90 - 0.92 0.94. 0.%. 0.98-1.00 0.0 0.0002 1.0 -0.98 -0.% -0.94 -0.92-0.90 0.88 -0.86 ~.. -0.84 0.82 0.80 0.78 0.76 ' 0.74 -0.72 0.70 ' -0.68 0.66 4 64 -0.62 0.60 -0.58 -0.56 - 0.54 -0.52 0.50 0.48 0.46 0.44 0.42 -0.40 0.38 ~ 0.36 0.34 -0.32 -0.30 4 28' 0.26 0.24 ' 0.22 -0.20 0.18 0.16 -0.14 -0.12 -0.10 - -0.08. '-0.06 -0.04 .0.02 .0.00-0.02 0.04 0.06 0.08 ' O.10 : 0.12 0.14 0.16 0,18 0.20 0.22. 0.24. 0.26 0.28' O.30 0.32 0.34 0.36 0.38 0.40 t - 0.42 0.44 0.46 0.48 0.50 0.52 0.54 0.56-0.58 - 0.60 0.62 0.64 ' O.66 0.68 0.70 0.72 0.74 - 0.76 0.78 0.80 0.82 0.84 0.86 0.88 0.90 - 'i O.92 0.94 0.% 0.98 1.00 1. 1. 1. 1. 1. 1. 1. 1. 1, 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1, 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. i i; 1. 1. 1. 1. 1. 1. 1, 1. 1. 1. 1. 1. 1. 1. 1. 1. 1 1. 1. 1. 1. 1. 1. 1. 1. I 1. 1. 1. 1. 1. 1. 1. 1. i 1. 1. 1. 1. 1, 1. 1, 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1, 1. 1. 1. 1. 1. 1. 1. 1. Page 1 of 10 l tt

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e'. 1. P5rter.Ccnouttantes Inc. 125A03YLCCOAD AR DMOR E. PA.19003 .. ass en sus PCI TR 323 Q-.1' INPUT DATA FOR QAD-CGGP RUNS 0.3 0.0041 0.2 1- 0 0 0.4 0.0041 0.2 1 0 0 0. 0.5 0.0041 0.2 ' 1 -0 0 0 0.0 0.0041 0.3 ' 1 0 0 0 0.1 - 0.0041 0.3 '1 0 0 0 0.2 0.0041 0.3 1 00 0 0.3 0.0041 ' O.3 1 0 0 0 0.4 - 0.0041 0.3 1 0 0 0 0.5 0.0041 0.3 1 0 0 0 0.0 0.0041 0.4 1 00 0 0.1 0.0041 0.4 1 0 0 0 0.2 0.0041 0.4 1 0 0 0 0.3 0.0041 0.4 1 00 0-0.4 0.0041 0.4 1

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j 1 z, P$rter. Coneuttante. Inc.- '886 A%$YLE COAD. ' ARDMORE PA.19003 l m en nan PCI TR 323 Q . Attachment'5.1 l INPUT DATA FOR QAD-COOP. RUNS g i l 5.1.3 - 0.064 cm RUN 1 = Na 24 Garama Skin Dose @ 0.064 cm Depth 100-!! 100-2 1 : l' 2

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1.5 END Z1 1 1 END ~ i i-1- 1 11 1 8 WATE EXP O.1119 0.8881 1.37 2.75 1.3685 ' 2.7503 't 0.00154 0.00182 1 1 4 1.0-3.0 o 1.0 1.74 2.53.0 McV/cm'2-sec mrad /hr w/g 0.0 0.0641 0.0 1 00 0 0.1 0.0641 0.0 1 00 0 0.2 - 0.0641 0.0 1 0 0 0 l 0,3 0.0641 0.0 1 00 0 j 0.4 0.0641 0.0 1 0.0 0 0.5 0.0641 0.0 1 0 0O 0.0 0.0641' O.1 1'0 0 0 3 0.1 0.0641 0.1 1 0- 0 0 >e O.2 0.0641 0.1 1 -0 0 0 0.3 0.0641 0.1 1 0 0 0 0.4 0.0641 0.1 1 0 0 0-0.5 0.0641 0.1 1 0 0 0 ~! 0.0 0.0641 0.2 ' 1 0 0 0 1 0.1 0.0641 0.2 1 0 0 0 0.2 0.0641 0.2 1 0 0 0 s Page 7 of 10 1 rp

-.I4 4. .l r . P rter Constitants. Inc.. 18s A40YL.E ROAD A* DMORE, PA.1D003 ' PCI-TR-323 - t'N s.enina-l .U.-.1 INPUT DATA FOR QAD-CGGP RUNS- ] i 0.3 0.0641 0.2 1 00 0 ,t 0.4 0.0641 0.2 ' I OO O 0.5 0.0641 0.2 1 0 0' O 0.0 0.0641 ' O.3 1 0 0. 0 ' O.1 0.0641 0.3 1 0- 0 0 l 1 000 l 0.2 0.0641 0.3 4 0.3 0.0641 0.3 1 00 0 i I' O.4 - 0.0641 0.3 1 00- 0 0.5 0.0641 0.3 1 00 0 0.0 ' 0.0541: 0.4 1 00 0 0.1 0.0641 ~ 0.4 1 0 0 0 l 0.2 0.0641 0.4 1 00 0' 0.3 0.0641 0.4 1 0 0 0-0.4 0.0641 0.4 1 00 0 I 0.5 0.0641 0.4 1 0 0 0 [ l 0.0 0.0641 0.5 1 0 0 0 0.1 0.0641 0.5 1 0 0 0 0.2 0.0641 0.5 1 0 0 0 0.3 0.0641 0.5 1 0 0 0 0 0.4 0.0641.0.5 1.0 0 0 O.5 0.0641 0.5 1 0-0 0 7 0.0 0.0 0.0 -1 O0 0 5.1.4 0.500 cm RUN Na.24 Gamma Skin Dose @ 0.500 cm Depth 100 1 100 2 1 1 2 9 1-1 2 0 0 1 1000 0 3.7E4 0. O. O. O. O. O. 1.0 0.98 0.% -0.94 0.92 -0.90 -0.88 -0.86 0.84 0.82 0.80 -0.78 -0.76-0.74 -0.72 0.70 0.68 -0.66 0.64 0.62 0.60 -0.58 0.56 -0.54 0.52. 0.50 -0.48 0.46 -0.44 -0.42 -0.40 -0.38 f 0.36 -0.34 0.32 0.30 0.28 -0.26 0.24 -0.22 -0.20 : 0.18 -0.16 -0.14 0.12 -0.10 0.08 0.06 0.04 0.02 0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14-0.16 0.18 0.20 0.22' O.24-0.26 0.28 0.30 0.32 0.34 0.36 0.38 0.40 0.42 O.44 0.46 0.48 0.50 0.52 0.54 - 0.56 0.58 0.60 0.62 0.64 0.66 0.68 0.70 0.72 0.74 0.76 0.78 0.80 0.82 0.84 0.86 0.88 0.90 0.92 0.94 0.% 0.98 1.00 0.0 0.0002 1.0 -0.98 -0.% 0.94 -0.92 -0.90 0.88- -0.86 0.84 0.82 -0.80 0.78 0.76 0.74 -0.72 0.70 /G- -0.68 -0.66 -0.64 -0.62 -0.60 0.58 -0.56 -0.54 (/ -0.52 0.50 -0,48 -0.46 -0.44 0.42 -0.40 0.38. Page 8 of 10 r

4 1 herter Comoultants. Inc. 3 4 3 SYLE ROAD PCI TR-323 0;E. PA.19003 ' s.m.1: l INPUT DATA-FOR QAD-CGGP RUNS l i 0.36 0.34 0.32 0.30 0.28 0.26 ' 0.24 -0.22 0.20 '. 0.18 ~ 0.16 0.14-0.12 -0.10 ' 0.08 -0.06 1 0.04 0.02 0.00 0.02 0.04 0.06 0.08 0.10-0.12 - 0.14 0.16' O.18 0.20 0.22 0.24 0.26 0.28 0.30 0.32 0.34 0.36 : 0.38 0,40 0.42 0.44 : 0.46 0.48 0.50 0.52 0.54 0.56 0.58 r 0.60 0.62 - 0.64 0.66 0.68 0.70 0.72-0.74 0.?6 0.78 0.80 0.82 0.84 0.86 0.88 0.90 0,92 0.94. 0.% 0,98 - 1.00 1. 1. 1. 1. 1. 1. 1. ' 1. { 1. 1. 1. 1. 1.- 1. 1. 1. 1. 1. 1. 1. 1. 1. 1' 1. 1. 1. 1. 1. 1. 1. 1, 1. 1. 1. 1. 1. 1. 1. - 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1, 1. 1. 1. 1. 1. 1.' 1, =I 1. 1. 1. 1. 1. 1. 1. . l. l 1. 1. 1, 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. . 1. 1. 1. 1. 1. 1. 1. 1. 1, 1. 1. 1, 1, 1. 1, 1. 1. 1. 1. 1. 1. 1, 1. 1. 1. 1. - 1. - 1, 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1, 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. - 1. 1. 1, 1. 1. 1. 1. 1. ' 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. - 1. 1. 1. 1. 1. 1. 1. 1. 1. 0 0 Square Source on Cylinder RCC1 0. O. O. O. O. 3.0 1.5 END Z1 1 1 END 1 1 11.1 8 WATE EXP 'l Page 9 of 10 m-.m,s m +ww-ry-

_s* i' Porter Comoultote,Inc. ' Its AEGYLE ROAD AROMORE PA.19003 n.. usa PCl TR 323 : h.1 INPUT DATA FOR QAD-COOP RUNS-0.1119 0.8881 1 1.37 2.75 1.3685 2.7503 0.00154 0.00182 1 1 1.03.0 1.0-1.74 l 2.5 3.0 - McV/cm*2-sec - mrad /hr _ w/g 0.0 0.5001 0.0 1 0 0 0 0.1 0.5001 0.0 1 0 00 0.2 ' O.5001 0.0 1 00 0 0.3 0.5001 0.0 1 0 0 0 0.4 0.5001 -0.0 1 00 0 l 0.5 0.5001 0.0 1 0 0O I 0.0 - 0.5001 0.1 1.0 0 0 0.1 0.5001 0.1 1 0 0 0 0.2 0.5001 0.1 1 00 0 0.3 0.5001 0.1 1 -0 0 0 0.4 0.5001 0.1 1 0 0 0.5 0.5001 0.1 1 0 0 0 1 0.0 0.5001 '0.2 1 0 0~O' O.1 0.5001 0.2 1 0 0 0-0.2 0.5001 0.2 1 0 0 0 0.3 0.5001 0.2 1 0 0 0 0.4 0.5001 0.2 1 0 0 0 0.5 0.5001 0.2 1 0 0 0 0.0 0.50011 0.3 1 0 0 0 0.1 0.5001 0.3 1 0 0 0 0.2 0.5001 0.3 1 0 0 0 0.3 0.5001 0.3 1 0 0 0 1 0.4 0.5001 0.3 1 0 0 0 i 0.5 0.5001 0.3 1 0 0 0 0.0 0.5001 0.4 1 0 0 0 l 0.1 0.5001 0.4 1 0 0 0 0.2 0.5001 0.4 1 0 0 0 0.3 0.5001 0.4 1 0 0 0 0.4 0.5001 0.4 1 0 0 0 0.5 0.5001 0.4 1 0 0 0 l 0.0 0.5001 0.5 1 -0 0 0 O.1 0.5001 0.5 1 0 0 0 0.2 0.5001 0.5 1 0 0 0 0.3 0.5001 0.5 1 0 0 0 0.4 0.5001 0.5 1 0 0 0 0.5 0.5001 0.5 1 0 0 0 0.0 0.0 0.0 1 0 0 0 0 Page 10 of 10 m

i inacensul<as.1u ISS ARGYLE ROAD

= A RDedORE. PA.19003. h m.. .Sn3 PCI TR-323'.2 GEOMETRIC MODEL USED FOR QAD CGGP INPUT t 1 Central /ais. 2 x 2 cm Source. ? D UO /b Yd \\ SoufCe* ] ,\\\\ j/ Receptor ' \\ / / i b -Distance - (variable) ] 3cm tj gi _ f,j 'I 1 x I cm i

Receptor.

--y - _ _, Grid s y k l M' i ~ ! - i 3cm q l / !O Page 1 of 1 i k

E O~> O O sr

?;r: SEO 83
5 E.

O h ) i - Average Gamma Dose Rate (mrad /uCi-hr) @ 0.004 cm Depth f' U- - Receptor Coordi-X "'I> nates (cm) -0.5 -0.4 -03 42 -0.1 -0.0 0.1 0.2 03 0.4 03 0.5 157.0 1583 159.5 160.2 160.5 160.6 -160.5 160.2 159.5-1583 157.0 M 0.4 1583 160.0 161.0 161.7 162.1 162.2 162.1 161.7 161.0 160.0 1583 C5 03 159.5 161.0 162.1 162.8 163.2 1633 163.2 162.8 1162.1 '161.0 159.5 . E >1 N 0.2 160.2 161.7 - 162B 163 3 ' 163.9 164.1 163.9 1633 162.8 -161.7 -1601 T 'Wl$ 0.1 160.5 162.1 163.2 163.9 1643 164.5 1643 163.9 1632 -162.1 -160.5 7 -- Y -0.0 - 160.6 162.2 1633 164.1 1643 164.6 1643 164.1. 1633 : '162.2 160.6L -0.1 160.5 160.0 163.2 163.9 1643 164.5 1643 163.9 = 163.2 160.0 1603 - N o 2 -0.2 160.2 161.0 : 162.8 163.5 - 163.9 163.9-1633 162.8 161.0 1602

T1 *3 163.2 ' -164.1 1633 163 2 : 162.8 162.1- ' 161.7 159.5

%~' - -03 159.5 '161.7 162.1' 162.8 O[ -0.4 1585 162.1 161.0 161.7 '162.1 162.2 162.1 161.7 161.0 162.1 158.5 -0.5 157.0 162.2 1593 160.2 1603 160.6 160.5 160.2 - 159.5 162.2 157.0 E- -O . Column y Average . 1593 161.1 161.9 162.6-163.0 - 163.1 163.0 162.6 161.9 - 161.1 ~ 1593 0 = b-Overall ~ Average / Corner /. g Peak-Average = : 161.7 Peak 164.6 - 98.2% : Peak = 95.4 % g Reading = =

Q

%CZm '*QO

5l1

~ 4a4"...ra. i age

3a.m

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'r5mm ium.f-9'

O O O'- i i. 3 O *'S. l >$' L a' gm

", E O Pg3 1

l e O I">E-C ~ 3- ~ ~e "t Average Gamma Dose Rate (mrad /mOehrj @ 0.007 cas Depth f Reaptor t e Coordi-X y e q nates (cm) -03 0.4 -03 -0.2 0.1 -0.0 0.1 0.2 Os 0.4 03 03 151.1 152.5 153.5 154.2 1543 154.6 1543 154.2 1533 152.5 151.1 rf 0.4 1523 154.0 155.0 155.7 1%I 1%2 IMI 155.7 155.0 154.0 152.5 C 03 1533 155.0 IKI 156.8 157.2 1573 157.2 1%8 1%1 155.0 1533

/

0.2 1541 155.7 1%8 157.5 157.9 158.1 157.9 157.5 1%8 155.7 154.2 hk y cn 0.1 1543 1%I 157.2 157.9 15& 4 1583 158.4 157.9 157.2 1%1 1543 E E Y -0.0 154.6 156.2 1573 1573 1583 158.6 158.5 1'73 1573 1%2 154.6 N 0.1 1543 1%1 157.2 157.9 158.4 - 1583 158.4 157.9 157.2 1%1 1543 43 9 -0.2 154.2 155.7 1%8 1573 157.9 158.1 157.9 157.5 1%8 155.7 154.2 9Q 'i A -03 1533 155.0 1%I 1%8 157.2 1573 157.2 1%8 1%1 155R 1533 y- -0.4 1525 154.0 155.0 155.7 1%1 1%2 1%1 155.7 155.0 - 154.0 1523 OM -03 151.1 1523 1533 154.2 1543 154.6 1543 1R2 1533 1523 151.1 gW i o coi m. 1533 154.8 155.9 1%5 157.0 157.1 157.0- 1%5 155.9 154.8 153 3 9 l Average = o Peak Overall Average / Corner / O Reading 158.6 Average = 155.6 Peak 9K1% Peak = 95 3 % = = x CZ v2 'o O Y b I i .~. m-. _ _ _. _., _ .,..~ , _.,. ~.. _, _.. _ -. -. _. - _.... ~ _ - _. - _...- - _,-

D O O'> =y=,A Y

o*

I5 = = :* ' =,;o -.3 ? 8 O i,& ~ C 3ir A$erage Gamma Dose Rate (mrad /wCi-kr) @ 0.064 cm Depth Reaptor ~. x 4 nates (ced . 05 -0.4 -03 0.2 0.1 -0.0 0.1 0.2 03 0.4 03 y-US Ei 874 E6 89.2 89.6 U.7 89.6 892 E6 37.6 86.1 g 0.4 87.6 39.1 90.1 90E 91.1 913 91.1 90.8 90.1 89.1 87.6 C 03 E6 90.1 91.1 91.8 92.2 92.4 92.2 91E 91.1 90.1 E6 ggk 0.2 892 90.8 91.8 92.5 93.0 93.1 93.0 923 91.8 90.8 89.2 y to Ot 89.6 91.1 92.2 93.0 93.4 93.5 93.4 93.0 922 91.1 R6 E Y -tio 89.7 91 3 92.4 93.1 93 3 93.6 933 93.1 92.4 913 89.7 W -0.1 89.6 91.1 92.2 93.0 93.4 933 93.4 93.0 92 2. 91.1 M6 g3 k 0.2 89.2 90.8 91.8 92J 93.0 93.1 93.0 92.5 91.8 90E 89.2 O 03 E6 99.1 91.1 91.8 92 2 92.4 922 91E 91.1 90.1 R6 3 g 0.4 87.6 39.1 90.1 90.8 91.1 913 91.1 90.8 90.1 89.1 87.6 OP -0.5 86.1 87.6 88.6 89.2 89.6 89.7 89.6 89.2 E6 87.6 86.1 gW o Column E4 89.9 90.9 91.6 92.0 92.1 92.0 91.6 90.9 89.9 K4 9 Average = n Peak Overall Average / Cornet / O 96.9 % Peak = 92.0 % O O Reading 93.6 Average = 90.7 Peak = =

0

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UO Ms

O O O~>

==,: ? -e-I, =Io d, e 5' O I ?gS

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O 8 = ~ C = ~ 3 '1i ~ Average Gamma Dose Rate (mrad /uCi-br) @ 0.500 cm Depth y f' Receptor O Coordi-X nates (cm) -05 0.4 -03 -0.2 0.1 -0.0 0.1 0.2 03 0.4 05 >d 0.5 243 253 26.0 26.4 26.6 26.7 26.6 26.4 26.0 253 24.5 0.4 253 26.2 26.8 273 273 27.6 273 273 26E 26.2 253 M 03 26.0 26.8 27.5 28.0 28.2 283 282 28.0 27.5 M8 26.0 C 0.2 26.4 273 28.0 28.4 28.7 28.8 28.7 28.4 28.0 273 26.4 5> N 0.1 26.6 27.5 28.2 28.7 29.0 - 29.1 29.0 28.7 283 27.5 26.6 $O tE Y -0.0 26.7 27.6 283 28E 29.1 29.2 29.1 28.8 2&3 27.6 26.7 -0.1 26.6 27.5 282 28.7 29.0 29.1 29.0 28.7 282 27.5 26.6 N# o -0.2 26.4 273 28.0 28A 28.7 28.8 28.7 28.4 28.0 273 26.4 Nh 2 -03 26.0 26.8 27.5 28.0 28.2 283 2&2 2&O 27.5 26.8 2tLO ar1 = -0.4 253 262 26.8 273 273 27.6 273 273 2ti8 26.2 253 %~ -0.5 24.5 253 26.0 26.4 26.6 26.7 26.6 26.4 26.0 253 24.5 K[ O Column o> i Average 25E - 26.7 27.4 27.9 28.1 28 2 2&I 27.9 27.4 26.7 25.8 O = O Peak Overall Average / Cornur/ g Reading 29.2 Average = 273 Peak = 93.4 % Peak = 83.9 % = g

ti

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UO4

n k!

w

O O ~ =:=,- v o-.. w= Gamma Dose Rate vs. Depth for Na-24 incident !.!.P,o (for 4 cm ^2 source - assuming CPE) f!! i S 165 ... = i l lI j-l,;,l-160 l 'Q E 155 .4-N i t-j'! j i - i i I 150 M. i i(* i i ! l t 145

y,',
F 140

-4 N, ' i i .i 135-Ny, 3 ; i 130 'i j j, - 125 ^ 120 4.,- p-j ! !'I J: 08% I 115 i*i i j ij { j i l i i ,i i

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p, 100 go i i; i g g o E 95 ,i g 1 j . 3';' ;5 ~. 90 = ~ I I !- ~ e 85 f 1-omih. ,! ' f f'I,, j,!I I A x 80- . b' e 75 i-i ! X', e 4 5 i i r i o 70 q ,;j; y'

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P4eter Consulta:te, Inc. Its AGOYLE CCAD ARDMoRE. PA.19003 aise n sasa PCI TR 323 O ~ Attecament 5.5 PRELIMINARY RESULTS OF NON-CHARGED PARTICLE EQUILIBRIUM DOSE RATE CALCOLATIONS PERFORMED BY THE UNIVERSITY OF I WISCONSIN MEDICAL PHYSICS DEPARTMENT USING THE EGS4 MONTE-CARLO COMPUTER CODE l l 1.0 In the body of this report it is acknowledged that the do6e rates calculated represent consenative estimates of the l actual y dose received. This is mainly due to the fact that the computer code used to perform the calculations assumes that charged particle equilibrium exists in the absorber materials. In fact, due to the extremely short source to receptor i distances involved in the subject incident. this is not a valid assumption. A review of current literature revealed that there was no simple approach to correcting this limitation. 2.0 As part of the review effort, PCI contacted Dr. Herbert Attix, author / editor of several noted texts on dosimetry. Dr. Attix, who is currently on the faculty of the University of Wisconsin (UW), referred us to one of his associates, Dr. Thomas R. Mackie to provide asssistacc. Dr. Mackie, a medical health physicist, is actively engaged in work related j this problem. Dr. Markle indicated that they had a computer code available, EOS4, that could be used to perform the l desired calculations. 3.0 EGS4 is a Monte Carlo code developed at the Stanford Linear Accelerator Center which can be used to describe the transport of y rays and the resulting scattered electrons through material. The code has been ported to a Sun' workstation at UW and required run times in the neighborhood of 12 hrs. to perform the desired calculations. .0 The preliminary results of the UW calculations indicate that the dose at 0.005 cm depth is ~15% of the dose at 0.200 cm dep2th (13.32 mradlyCl.hr at 0.005 cm vs. 68.6 mrad /yCi hr at 0.200 cm). Table 1 is a printout of the output 2 data (in 10' Oy/cm / dis.) and Figure 1 is a plot of the resultant data. These preliminary results indicate that the y i dose rate calculated by QAD COOP at 0.004 and 0.007 cm may be high by a factor of 10 when charged particle equilibrium is accounted for. l l O Page 1 of 3 w

}4rter Cent.ultants. Inc.

~ m ancm i ono A S4 DMOH F, l'A l9003 ris **uu AmclMENT 5.5 <<q e S ,i o__-n n sd S b I} E5 E 3 lEkk$gggfg$h h ls$ss h 8 a j {y $ f 45$$ 4sdee'O6ds$ci I 3-e is e 1 aw 0g g f $g p g g $ 30 N g gggRg e 3 EN.E-EE889 898 8 j o o o o o o o o o o o o. 6 @o o o o

o o 8 j" sC

q o

j" km o ;k i amesssagkangangggggsil N m nns---- o j 66ooo6o66666666do6d6 l RA E w C 2] @ 4 C $= I~Rg? 23 SRR P 8RR*] [- Ah8nR 85 588 $E

3}

g e o - - - c4 e n n n n n, - 88,8,238 5} g + oe ,e, aI al El la r72 ) $ !$h655E0llEf$50$5l$2 kk 'S6$5cSNoodo$$5:$ EMS $ lL j d l'j F x I s i s s t-R a a s a s i s t a s s a i s . l i n-c--- $---e: m jE- -ec-e .g 66oeeooe6od66ooo6c6e ! I-E E ]l 52 Ek!!!!5S$!!kbkkfE!$k3!:s:::";<$;s~ IE3 - is -I:*:: 2 6 2 ill ~~Emti.estil!egggg!ee9 j$$ 0 e < a sa s =_--- m u E* od6od666666666666odo ff; Paga 2 of 3 i m

Porter Cenoultants. Inc. FCI-TR-32 3 til ARGvLE ROAD i ARDMOR E. PA.19003 ,i.......... O - - s.s FIGURE 1 Na.24 Depth Dose (EGS4) 6 .E I{ g 5-a. 9 M 1 I 3-O 1

<7.

1-p 2a C h 1-2.0cm a 2.0ctn conwnitwlen area 2.7srn a 2,?cm x 3.0cm wasar phantom 4 100,000 photon histories for each photon energy, 0 0.0 0.1 0.2 Depth (cm) 4 4 O Page 3 of 3

W PHONE, t15 89815353 S,. PORTER CONSULTANTS, Inc. -Q' 4 1 Realiological Protection and Enviroansadal Services i 1 125 ARGYLE ROAD 1 ARDMOR E. PA. 19003 i i ) i i PCI-TR-324 ) REPORT OF BETA GAMMA DOSIMETRY ASSOCIATED WITII CONTAMINATION OF A WORKER'S TIfUMB AT THE j JAMES A. FITZPATRICK NUCLEAR POWER FIANT April 3,1990 j Prepared for: George J. Vargo, Ph.D., CHP Radiological and Environmental Services Superintendent James A. FitzPatrick Nuclear Power Plant New York Power Authority Lycoming, New York 13093 ? j-Prepared by: Sydney W. Porter, Jr. CHP President

Reviewed by:

John Sykes III I Consultant Health Physicist NOTE: Identification of Worker's names and Social Security Numbers are available to authorized personnel from NYPA 4 l lO i= _ _ _ _ _ - - _ _ _ _ _. _ - _ _. _ _ _ _ _ - _. _ _ _ _ _. _ _..... _ _. ~... _ _.,_- .-....-...w.......

... N'eter comovitatte, Inc. . * *. 336 ARGYLE ROAo AR DMO R E. P A.19003 25.. * **$8 PCI TR 324 REPORT OF BETA GAMMA DOSIMETRY ASSOCIATED WITH CONTAMINATION OF A WORKER'S THUMB AT THE JAMES A. FITZPATRICK UCLEAR POWER PLANT TABLE OF CONTENTS

1.0 INTRODUCTION

Page 1 of 6 2.0 EXECUTIVE

SUMMARY

Page 1 of 6 3.0 REVIEW OF THE CIRCUMSTANCES CONCERNING THE CONTAMINATIONINCIDENT Page 2 of 6 4.0 PREPARATION OF CALIBRATION STANDARDS AND SURVEY INSTRUMENT ASSAY FOR LEFT THUMB CONTAMINATION OF WORKER Page 3 of 6

5.0 CONCLUSION

S Page 4 of 6

6.0 REFERENCES

Page 4 of 6 7.0 ATTACHMENT 3 Page 5 of 6 7.1 PCI Debriefing, and Time & Motion Study of Worker P 1page .O. 7.2 Statement of Health Physics Technician (BA) Who Assayed Worker P 4 pages 7.3 Determination of Contamination Area of Worker P's I.4ft Thumb Pad -1page 7.4 Dose Assessment Work Sheet 5pages 7.5 Initit! 24Na Assay of TW Special Calibration Sources 1page 7.6 Reassay of Two Special Calibration Sources at 10 cm from Detector 1page M 7.7 Certificate of Na 2 cm x 2 cm Special Sources Calibration of RSO 50 1page 24 7.8 Certificate of Na 2 cm x 2 cm Special Sources Calibration - of RO 5 1page 24 7.9 Certificate of Na 2 cm x 2 cm Special Sources Calibration HP 210 + Ludlum 177 1 page 7.10 1.etter of David D. O'Brien, Jr., M.D. concerning March 13,1990 examination of Worker P 1page Page 1 of 2 .j

** Porter Consultante, Inc.

e lts Am0VLt 20A0 AR DMC A E. P A.19603 til 696 5863 KI-M 324 REPORT OF BETA GAMMA DOSIMETRY ASSOCIATED WITH CONTAMINATION OF A WORKER'S THUMB AT THE JAMES A. FITZPATRICK UCLEAR POWER PLANT TABLE OF CONTENTS 7.11 hic Body Count of Worker P on March 9,1990 2 pages 7.12 hie Boey Count of Worker P on March 13,1990 2 pages 7.13 Radioactive Bionssay of Worker P's Urine 4 pages 7.14 James A. Fitzpatrick Nuclear Power Plant Training Records for Health Physics Technician Worker P 3 pages 7.15 Done to Right Hand of Worker P 1page 7.16 Done to Gonads from "Na Contamination on left Thigh of Worker P 1page O t i F i O Page 2 of 2

--s.,._,u e O s Petter Consultants. Inc. Its ARGYLE ROAD A R dmo R E. PA.1900s an.en sa PCI TR 324 Q-REPORT OF BETA-GAMMA DOSIMETRY ASSOCIATED WITH CONTAMINATION OF A WORKER'S THUMB AT THE JAMES A. FITZPATRICK NUCLEAR POWER Pl. ANT

1.0 INTRODUCTION

On March 8,1990, Worker P inadvertently contaminated his right glove and cross contaminated a 2 24 4 cm area of the skin (pad) of the left thumb with Na. Porter Consultants, Inc. (PCI) was requested on 3/12/90 to perform an independent, in depth evalue. tion of the dose to the worker's left thumb due to the 24 Na contamination incident. On 3/13/90 Mr. " Sykes of PCI performed a preliminary review of the initial on. site dose calculation. Mr. S.W. Porter, Jr., CHP, was requested to personally assess the situation and arrived in Oswego late on 3/13/B0. > Early on 3/14/90 Mr. Porter initiated an independent time and motion review of the circumstances before, during, and following the March 8,1990 contaminating event. Mr. Porter then coordinated 24 the preparation of special Na calibration standards for recalibration of all instrumentation utilland d - in the dose assay. Mr. Porter personally calibrated the specific survey instruments utilized for the - dose assessment. All documents generated by J.A. FitzPatrick Plant associated with this contamina. tion incident (through 3/15/90) were carefully reviewed by Mr. Porter. 2.0 EXECUTIVE

SUMMARY

2.1 Our most accurate dose assessment for Worker P is 16.335 rads p and.728 rads y (total ef o ~ 2 17.06 rads per cm ) to the live tissue of the skin of the left thumb his is the highest square - 2 centimeter dose to an area just under 64 mg/cm of stratum corneum (dead skin). A special series of computer runs were performed to determine the gamma portion of the donev (Reference 1). The beta dose was calculated by both the Cross (Reference 2) and the VARSKIN (Reierence 3) methods and indicated agreement to within a few percent. 2.2 The NRC on site inspection team (O'Connell and Chawaga) requested that the dose be cal-2 culated at a depth of 0.007 cm (7mg/cm ). His dose is 48.2 rads p + 0.57 rads y to yield a to-2 tal of 48.8 rads per cm. For this contamination incident, it is biologically and anatomically inapproorlate to calculate the dose to an area below only 7 mg/cm of stratum corneum. 2 2.3 This dose to the skin of the left thumb is well below the threshold for any observable skin ef. fects (Ref. 4). Medical personnel verified this by observing no first or second wave crythema (reddening of the skin)on Worker P. 2.4 De best estimate of the thicisness of the dead layer of the skin is ~64 mg/cm for the reasons 2 given in Paragraph 3.5. 24 2.5 Dere was no significant absorption of Na through the stratum corneum as demonstrated 24 by the lack of Na in both the whole body counts and the urine radiobioassay (Attachments 7.11,7.12 and 7.13) Refer to paragraph 3.5 of this document for further information con-24 cerning penetration of Nano ttrough thestratiumcorneum. 3 2.6 The most probable cause of this incident is a combination of worker error (not strictly follow-ing procedures), and incomplete worker training (failure to instruct workers concerning ntag-nitude of hazards involved with the procedure). O i i Page 1 of 6 i ii

4 ' * * ' Porter Consultete, Inc. lll AmOYLE ROAD cmDuomE. PA. 3 9003 n s.s*"" PCI TR 324 REPORT OF BETA-GAMMA DOSIMETRY ASSOCIATED WITH CONTAMINATION OF A WORKER'S THUMB AT THE .IAMES A. FITZPATRICK NUCLEAR POWER PLANT 2.7 RECOMMENDATIONS 2.7.1 Review lessons learned from this inddent with all operational and appropriate sup-port personnel._ (his includes a W of what should have been covered in the ALARA Pre Plan Meeting for the '*Na Feedwater Flow Test.) 2.7.2-All Health Physis and Chemistry Professionals and Senior Tochalcians should at. tend a Professional Enrichment course concerning g hasards and associated assay and dosimetry. 2.7.3 The Skin Decontamination Procedurt (Personnel Decontamination RPP.2 of 3/6/89) should be revised to include the rquirement to obtain medical permission to utilize agents other than soap, wate and +4ral scrubs (l.c. Potassium Permanganate/ Sodium Bisulfate or stronpr solu..ac.). De ' Medial Assistance" section should encourage the person having dimculty in decoutaminating to obtain medical assistance. 3.0 REVIEW OF THE CIRCUMSTANCES CONCERNING THE CONTAMINAL TION INCIDENT 3.1 TIME AND MOTION STUDY Mr. Porter interviewed Worker P, and then performed a time and motion study of the con-taminating event to indyndently verify all of the times involved associated with the ex. posure of Worker P. A Na NO solution vial, identical to that utilized on 3/8/90, was given to Worker P for the time and Mo! ion Studies. The results of this debriefing are contained in.1. 3.2 INTERVIEW OF H.P. TECHNICIAN (WORKER B.A.) PERFORMING ASSAY AND CHEMICAL DECONTAMINATION OF WORKER P's LEFT*ITIUMB A lengthy interview of the H.P. Technician who performed the assays brought out many facts that were not completely documented at that time. At Mr. Porter's request, this Technician (Worker BA) documented all the points discussed in Attachment 7.2. his document in-cludes two very helpful diagrams. 3.3 AREA OF CONTAMINATIOM ON LEFTTHUMB i The determination of the total area of contamination was performed by Workers JS and MM..3 resulted from debriefing these men. This documents the method and results of this survey (a 2 cm by 2 cm area of contamination on Worker P's left thumb pad). O Page 2 of 6 l

. -. ~... _. - - (* 's. Porter Conovita:ts, Inc. Its AmOYLE ROAo AR DMO R E. PA.1 D004 m... uis PCI TR 324 .t REPORT OF BETA-GAMMA DOSIMETRY ASSOCIATED WITH CONTAMINATION OF A WORKER'S THUMB AT THE l JAMES A. FITZPATRICK NUCLEAR POWER PLANT l l 3.4 DOSE ASSESSMENTWORK SHEET -l i De Dose Assessment Work Sheet (Attachment 7.4) reflects all of the dose assays discussed l In Attachments 7.1 and 7.2. His work sheet has been revised many times as better informa-l tion became available. De most signifiant amendmer.ts were the survey meter speciSc i-24 calibration constants for a 2 cm x 2 cm Na source and the point kernal calculation of the. gamma dose. - 3.5 ESTIMATING THE STRATUM CORNEUM THICKNESS OF WORKER P's LEFT THUMB AND DISCUSSION OF UPTAKE VIA SKIN ABSORPTION. 3.5.1 Dr. David D. O'Brien, Jr. estimated that the stratum Corneum for Worker P to be 2 I between 60 and 67.3 mg/cm gIgg decontamination efforts. Refer to Attachment 7.10 for a copy of his letter, l 24 3.5.2 De lack of any. detectable Na in the bloodstream (whole body counts) i 24 demonstrates that there was no significant absorption of Na through the stratum corneum. The minimum detectable quantity of 'Na with a whole body count is 2 24 nanocuries. This is less than 1/1500 of the original Na on the left thumb. Refer to Attachments 7.11 and 7.12. l 24 3.5.3 Delack of Na absorption through the stratum corneum to the blood stream is fur-j 24 ther demonstrated by the lack of any Na in Worker P's urine. The urine sample was a composite taken from 2100 hours on 3g to 0600 hours on 3/9/90 and in-4 cluded the early morning voiding. De MDA for Na is approximately 2 x 10 pCi/cc of urine for the 25 minute count utilized in the Liquid Bloassay count of Worker P's l urine (Refer to Attachment 7.13). 24 3.5.4 Another fact that reinforces this point is that virtually all the Na was removed within 2H days. The total stratum corneum exfoliation time for the thumb pad is in 24 2 excess of 20 days (Ref. 5). If significant penetration of the Na into the 64 mg/cm of the stratum corneum had occunen, then the demptamination could not have been mmplete in only 2% days. 3.5.5 he horny layer of the thumb pad is practically impervious to low molecular weight l electrolytes such as NANO (acmrding to Dr. A. Kleegman, Professor of Research 3 Dermatology, University of PA Medical School) (Reference 11). i t 4.0 PREPARATION OF CALIBRATION STANDARDS AND SURVEY INSTRU-1 MENT ASSAY FOR LEFT THUMB CONTAMINATION OF WORKER P 4.1 SPECIAL CALIBRATION STANDARDS 24 It was necessary to prepare two special Na calibration sources that closely approximated the geometry of the contaminated left thumb. (Refer to Attachment 7.3.) One source was 2 prepared on a round 2.5 cm diameter thin filter paper (4.9 cm ). The other source was Page 3 of 6

4 t Potter Consultants. Inc. I tas AmovLc noAo l An ouo ms., PA.1900s l 3 5.m.ssu PCI TR-324 rs REPORT OF BETA GAMMA DOSIMETRY ASSOCIATED WITH U CONTAMINATION OF A WORKER'S THUMB AT THE JAMES A. FITZPATRICK NUCLEAR POWER Pl. ANT prepared on a 2 cm x 2 cm square thin filter paper. A thin filte.r paper standard is preferable to a metal planchet because it more closely resembles the backscatter properties of the skin. The sources were given a preliminary y spectrometry assay using an HPOe detector splem on their day of preparation (3/14/90). Refer to Attachment 7.5. It became apparent that a spe-cial assay geometry needed to be established at a reasonable distance away from the samgle. nus, a 10 cm distance from the detector geometry was established on 3/15/90. Both Na calibration standards were then counted, and the activity corrected for decay back to the time that all the assay instruments were calibrated with each of these two sources. he assay of 24 both sources is 2.06pCiof Na on 1900 hours of 3/14/90. Refer to Attachment 7.6. 4.2 Calibration of Survey Instruments Utilized to Assay numb Since the actual geometry of ti.e 2 cm x 2 cm 24Na contaminated area was somewhere be. tween a square and a circle, it was decided to manufacture two sourms (one round and one square), and to calibrate all assay instruments with both sources. The calibration of both the RSO-50 and the RO 5 lon Chamber Survey Meters was performed on 3/14/90 by S. W. Porter, Jr. and O. J. Vargo together. Subsequent counting of the two Calibration Standards (Attachment 7.6) showed both sources to be 2.06 pCi at 1900 hours on 3/14/90, his data al. lowed accurate calculation of the sper3c response of the RSO 50 (Attachment 7.7) and of the RO 5 (Attachment 7.8) ne diglM response of the RO 5 open window was averaged over 20 measurements, and the closed wc, tow (which fluctuated less) was averaged over 10 measurements. The response of the two lon Nmber survey meters utilized in the initial as. - says of Worker P, are as follows: RSO-50 = 34.0 mrad /pCi hr. at 1/8* open window RO5 = 41.6 mrad /pCl-hr, at 1/2' open window The GM Tube Frisker (HP 210 Probe r Ludlum 177 Ratemeter)was calibrated on 3/14/90 with excessive dead time (>100,000 c/m) at the distances needed (contact and 0.5 inches). Thus, this calibration was delayed until 3/20/90 to allow enough decay for a reasonable calibration, unaffected by detector dead time. The calibration factor for the HP 210 Frisker is approximately 600,000 c/m/ CI(calculated on the basis of Attachment 7.9).

5.0 CONCLUSION

S 1. The effects of 17 (or even as much as 49) rads to a small area (4 cm )to the live skin of the 2 thumb is radiobiologically insignificant. This was demonstrated by the lackpf any medically observable effects (as per Dr. O'Brien's observations). The threshold for skin erythema is 200 to 300 rads for a human with very radiosensitive skin (Reference 4). 2d 2. There was no systemic uptake of Na into Worker P's body as demonstrated by both the Whole Body Counts and the Urine Radiobioassay (Attachments 7.11,7.12 & 7.13). 3. The most likely dose to the live skin of Worker P's left thumb is 17.03 rads (beta and 2 2 2 gamma)/cm at 64 mg/cm depth. The choice of a target area of,LctI1 for averaging dose to the skin, although current as to regulatory guidance, is highly ouestionable biologically. The O Page 4 of 6 1

e 4 P:rter Consultants. Inc, las ARGYLE ROAO A R DMO R e. PA.19003 n s.e.5 sm PCI TR-324 -Q-REPORT OF BETA GAMMA DOSIMETRY ASSOCIATED WITH CONTAMINATION OF A WORKER'S THUMB AT THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT newest (February,1990) draft recommendations of ICRP (Reference 6), which is a revision 2 to ICRP 26, recommends averaging dose over J.(Q.gg of skin for non stochastic effects. For stochastic effects, ICRP recommends averaging done over the entire skin (Reference 6). 2 4. The choice of measuring dose at 64 mg/cm cornes from both the observations of Dr. O'Brien (Attachment 7.10) and the statement of a research dermatologist who specializes in skin ab-sorption (Paragraph 3.5.5). 5. The beta dose calculations at 0.064 cm depth (64 mg/cm ) from 24 2 2 Na deposited over 4 cm og skin agree very well between the Cross methodology (Reference 2) and the Varskin Code (Reference 3). The gamma dose calculations at depths less than electronic equilibrium (~0.5 cm) are subject to some of interpretation. The assumption of electronic equilibrium in the - QAD COOP Code (Reference 1) yields a conservatively high dose at depths less than 0.5 cm. The PCI dose calculations were run utilizing a source of 200,000 point kernals to smooth out point to point variations. The SLAC cale EGS-4 was run rio that lack of electronic equilbrium is taken into account.

6.0 REFERENCES

1. PCI Technical Report 323, Calculation of Gamma Skin Dose for 24Na Skin Centamination incident. March 27,1990. O 2. Cross, W. O., Tables of Beta Dose Distribution. Atomic Energy of Canada Limited, Report AECL 2793,1%7. 3. Traub, R. J., Recsc, W. D. et al, Dose Calculation for Contamination of Skin Usine the Computer Code (VARSKIN)., NUREG CR-4418, August,1987 NRC, Washington, D. C. 4. C. S. Potten, Radiation and Skin. Published by Taylor and Frances, Philadelphia,1985. 5. International Commission on Radiation Protection, Report #23, Report of the Task Group on Reference Man.1974, published by Pergamon Press. 6. International Commission on Radiological Protection. Recommendations of the Commis-sion February, Draft,1990,ICRP/90!O 01k,1990-02 09, 7. NYPA,JAFNPP. Radiologicalincident Report. RIR# 90-019. Dated: 3 8-90,16:25, 8. NYPA,JAFNPP. Draft. Chronology of events for sodium 24 contamination incident. 9. NYPA,JAFNPP. Radiation Protection Operating Procedure. Personnel Decontamination. RPP 2 Rev 7. 3/6/89. 10. NYPA, JAFNPP. Memo dated 3/15/90. From: George J. Vargo. To: File.

Subject:

Ex-tremitydose assessment OR 90-057/RIR.9019. O 3 Page 5 of 6 j

. p:rter Consultante. Inc. les ARQYLE ROAD A R DMO R E. PA.1 003

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REPORT OF BETA-GAMMA DOSIMETRY ASSOCIATED WITH CONTAMINATION OF A WORKER'S THUMB AT THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT A 11. Prbste communication between Dr. Kleegman and S. W. Porter, Jr. on 3/22/90. O O Page 6 of 6

I s. P rter Cone:lta:to, Inc. 4tl ARGYLE ROAD Ah DMOR E. PA. 3 D003 n s..*-sn* PCI TR 3M j ..1 3/14/90 SWP Notes DEBRIEFINO OFWORKER P (H.P. Tech,63 ears of H.P. experience at FitaPatrick Plant, Nuclear Navy ELT for 6 yrs.) Contaminating Ewat 16:05 hours on 3/&90 I Personnel Dosimetry . j Ring TLD on inner ring fingers of both hands, plus a Panasonic 4 element TLD on chest acrt to a direct reading dosimeter (DRD). j I TLDleft hand 51 mR (chip wet) dried in dessicant for 1.5 days i TLD right hand 1.2 mR7 (chip wet) dried in dessicant for 1.5 days i chest TLD (30 mR prior) 50 for job (Total of E). DRD was 5 mR (De walls of the DRD absorb essentially allp radiation from # a. j N Time and Motion Study F.C19.lts for Cannine Procedure 4 sec at 1.5 R/hr M gives approx.1.2 mR while capping Na vialwith right hand Overall Timina After Contaminatine Event 3/8/90 16:05 (within 1 min. of contaminating event) exit work area, i 16:10 went through portals alarm 16:11 finished with HP 210 probe alarmed for 1gfi hand. 16:13 shower (pocket of pants contaminated, socks contaminated), minor mntamination at hand fingers l 16:25 st.ower, hand decon,, i l 17:15 decon numbers at %* from detector j l 06:15 Frisked RO-5 S/N69 byself(WorkerP) 10:00 Frisked RO-5 S/N 69 by H.P. Supvsr J.S. 12:05 Frisked RO 5 S/N69 byself(Worker P) i. 15:00 Frisked RO.5 S/N69 byself(WorkerP) 3/1Q90 all measurements by self Worker P Decons with #1 Ivory bar soap. U.h&, Page1of1 P [

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WORKER P'S CONTAMINATION INCIDENT of 3M/90 incident Recall by Worker B.A. (x6738) Incident began 16:25 hrs. j Commenced initial survey and encountered several problems; De cross contamination of my left hand from the frisker handle. My left hand palm was con-taminated to 1900 cpm at this time. I just put gloves on to continue the survey and deconned the handle, i NOTE:At this time the H.P. shift technician N. S. and the H.P. technician covering the job, P.D., commenced a detailed survey of all applicable areas involved in this event. De level of contamination required that I utillae an RSO 50 (serial number 616) instead of the hand held frisker to complete the survey. Surveyed the clothing and found multiple contsmination locations (See attached figure). Instructed Worker P to remove pants, shoes, and socks. Performed a survey of the skin on Worker P's left thlyh. i ne dose rate on the skin exceeded the dose rate on his pants. Instructed Worker P to remove all of his clothing. Finger rings taken for decon 16251630 hrs. Performed a survey on the skin of his whole body using the hand held ft(sker, excepting those areas where the frisker was off r,cale, ne RSO 50 was used for those cases where the frisker t was off scale. The results are as follows to the best of my recall: Area 1 Worker P's left thumb 120 mrad /hr open window uncorrected,4.0 mr/hr closed win-dow. To about 50,000 cpm on the finger tips of the left hand. l Area 2 Worker P's right finger tips and thumb were contaminated to about 12,000 epm. Area 3 Worker P's left thigh 20 mrad /hr open window (uncorrected),1.7 mr/hr closed win-dow. l Area 4 Worker P's left waist about 4,000 cpm.- Area ! Worker P's left mid chest about 6,000 cpm. Dere was no facial contamination. i Page 1 of 4

s' 'e L., Porter Comoultanto, Inc. tas Anovte noto An DMO R E. PA.19003 -Oawow-sna PCI TR 324.2 This survey was brief and only to obtain an overall picture of the total extent of the contamination. I felt that at this time (1630 to 1635) that an initial decon should begin immediately. Dese initial con-tamination readings were taken at about 1/8' from the zor.e of contamination. While Worker P was in the shower, I deconned my left palm and verined that the decon area and frisker was not co-taminated. De first shower was completed at about 1640 (cool water and soap the decon agent) Results after the shower as follows: All main body contamination was deconned to less than 100 cpm (areas 3, 4, 5 of attached figure). His was verified by having Worker P use the portal (hands out outside the portal) with H.P. Super-visor J.S. and myself being the hands. No noticeable change on Worker P's hands at this point. . At this time 1645 to 1700 hrs, Worker P deconned his hands with soap, water, and soft nail brush. Be-tween the three washings no appreciable drop in dose rates on the hands. Major contamination (area

1) was still at about 90 mrad /hr open window uncorrected using the RSO 50. Worker P's hands prior to decon start were very reddened and chapped from working out of doors at home and still looked -

that way. The only exception was that the callused areas were softening up. At about 1810 hrs, with H.P. Supervisor J.S. reading PDP 11 (DOSE ASSESSMENT) to me, I switched the lustrument for dose rates to an RO 5 with " collar in place (serial no. 69 used) to be able to use the procedure mrrectly. To survey Worker P's thumb and verify the done rate at ", I had a second person (J.S. or T.B.) verify the distance was properly maintained. The dose rate was 48 mrad /hr open window (uncorrected) and 1.7 mr/hr closed window. De finger tips of the hands stayed about the same. But I did not think to shield Worker P's thumb so these results were questionable. From around 1830 to 1930 hrs. Worker P soaked his hands in a solution of saturated Nacl solution to attempt an ion exchange. During the process I periodically checked his hand with no evident change. The solution in the beaker did have a dose rate of 20 30 cpm by frisker when this attempt at decon stepped. At 1930 to 2030 hrs, with no evident results from previous decons on the hands,I used the unshielded probe from an E.530 to locate the main dose area of Worker P's left thumb. This area (see figure) of skin was in good condition and after discussing it with Supervisor, decided to decon the area using Potassium Permangenate and Bisodium Sulfate. After completion of this decon process, the skin was in good mndition and the dose rate of 40 mrad /hr open window (uncorrected) with the RO 5 at ". With this minor decrease, considering the half life of the isotope and the potential chemical damage to Worker P's thumb,we stopped the decon attempts. At 20:30 hours,2000 to 3000 c/m remained on tips of right finger. 3 (signed) B.A. i o Page 2 of 4 i i

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Portcr' sultrata, Inc. 175 ARG OAO Attachment 4 Anomon c. pA. i,oo3 2:Sewms DOSE ASSESSMENT: RES TECHNICIAN Na-24 CONTAMINATION EVENT t1/2 15.03 hr lambda 0.046 1/hr te 21.64 hr Dose Varskin Gannma 0 0.007 cm varskin Gamma 0 0.064 cm Constants: 2.205 0.156 rad /uci-hr O.747 0.091 rad /uci-hr DT Cum OW GM Ion Ch Instrument Date Time hr hr urad/hr cpu Act uCi uCi-hr Used-03/08 16:05 NA NA NA NA NA 03/08 16:25 0.33 0.3 120 3.531 1.18 RSO-50 03/08 17:15 0.83 1.2 90 2.649-2.21 RSO-50 03/08 18:10 0.92 2.1 48 1.154 1.06 RO 03/08 19:30 1.33 3.4 48 1.154 1.54 RO-5 03/08 20:30 1.00 4.4 40 0.961 0.96 RO-5 03/08 21:00 0.50 4.9 34 0.817 0.41 RO 03/08 22:00 1.00 5.9 0.780 0.78 03/08 23:00 1.00 6.9 0.745 0.75 03/08 24:00 1.00 7.9 0.712 0.71 03/09 01:00 1.00 8.9 0.679 0.68 03/09 02:00 1.00 9.9 0.649-0.65 03/09 03:00 1.00 10.9 0.620 0.62 03/09 -04:00 1.00 11.9 0.592 0.59 n3/09 05:00 1.00 12.9 .O.565 0.57 03/09 06:00 1.00 13.9 0.540 0.54 03/09 07:00 1.00 14.9 0.515 0.52 03/09 08:00 1.00 15.9 0.492 0.49 03/09 09:00 1.00 16.9 0.470 0.47 03/09 09:30 0.50 17.4 18 120,000 0.433 0.22 03/09 10:30 1.00 18.4 0.413 0.41 03/09 12:05 1.58 20.0 14 80,000 0.336 0.53 03/09 13:00 0.92 20.9 0.321 0.29 03/09 14:00 1.00 21.9 0.307 0.31 03/09 15:00 1.00 22.9 0.293 0.29 G3/09 16:00 1.00 23.9 0.280 0.28' Page 1 of 5

e- ~ ^onsultanta, Inc. Portcr,D eono ers na( anoweva. noos Attcchment 7.4 2154 DES 353 j 03/09 17:00 1.00 24.9 0.267 0.27 03/09 18:00 1.00 25.9 0.255 0.26 03/09 19:00 1.00 26.9 0.244 0.24 03/09 20:00 1.00 27.9 0.233 0.23 03/09 21:00 1.00 28.9 0.222 0.22 03/09 22:00 1.00 29.9 0.212 0.21 03/09 23:00 1.00 30.9 0.203~ 0.20 03/09 -24:00 1.00 31.9 0.193 0.19 03/10 01:00 1.00 32.9 0.185 0.18 03/10 02:00 1.00 33.9 0.176 0.18 03/10 03:00 1.00 34.9 0.168 0.17 03/10 04:00 1.00 35.9 0.161 0.16 03/10 05:00 1.00 36.9 0.154 0.15 03/10 06:00 1.00 37.9 0.147 0.15 03/10 07:00 1.00 38.9 4.5 60,000 0.108-0.11 03/10 08:00 1.00 39.9 0.103 0.10 03/10 09:00 1.00 40.9 0.099 0.10 03/10 10:00 1.00 41.9 0.094 0.09 'i , 03/10 11:00 1.00 42.9 0.090 0.09 03/10 12:00 1.00 43.9 0.086 0.09 03/10 13:00 1.00 44.9 0.082 0.08 03/10 14:00 1.00 45.9 0.078 0.08 03/10 15:00 1.00 46.9 0.075 0.07 03/10 16:00 1.00 47.9 0.071 0.07 03/10 17:00 1.00 48.9 0.068 0.07 03/10 18:00 1.00 49.9 -0.065 0.07 03/10 19:00 1.00 50.9 0.062' O.06 03/10 20:00 1.00 51.9 0.059 0.06 03/10 21:00 1.00 52.9 0.057 0.06 03/10 22:00 1.00 53.9 0.054 0.05-03/10' 23:00 1.00 54.9 0.052-0.05 -03/10 24:00 1.00 55.9 0.049 0.05 03/11 01:00 1.00 56.9 0.047 0.05 03/11 02:00 1.00 57.9 0.045 0.05 03/11 03:00_ 1.00 58.9 0.043 0.04 03/11 04:00 1.00 59.9 0.041 0.04 03/11 05:00 1.00 60.9 0.039 0.04 03/11 06:00 1.00 61.9 0.037 _O.04 03/11 07:00 1.00 62.9 0.036 0.04: Page 2 of 5 .. ~. .. - -,, ~. -... -

Porte >nsultsta. Inc. f *"ar,,;. ";, Attcchment 7.4-t ,,,.,m 03/11 08:00 1.00 63.9 0.034 0.03 03/11 09:00 1.00 64.9 0.6 6,000 0.014 0.01 Ultimate Decay [D(0)*1.44T] = 0.312 uCi-hr = 21.867 using ion chamber data Ion chamber calibration data l OW CW net BCF l l RO-5A #69 77.8 2.8 75.0 2.9 RO-5A #108 77.0 2.5 74.5 2.9 RSO-50 #617 44.0 2.0 42.0 4.0 RSO-50 #602 60.0 2.0 58.0 3.6 Na-24 counting standard i Counting time 03/10/90 19:25 32942.80 Sampling time 03/10/90 19:25 32942.80 i-IYf 0.00 l - Correction factor 1.00 Measured activity 2.125 uCi Corrected activity 2.125 uCi ) Page 3 of 5 y ~ or ,,,,,,,.n ,,..1_ m. e_,.______m.m_m___ m m..

Porter Cc' Itrata, Inc. s\\ Attachment (w4 ,2s naGvt.E a n ovoa t. ca. i 2l*>- W S3">) Ion chamber correction factors obtained 03/14/90 RSO-50 S/N 616 Uncorrected mR/uci-hr Source-Cham Dist OW CW ON CW 0.125 in - 70 3 34 1.5 0.500 in 55 2 27 1.0 Round source 0.5 in Square source 0.5 in RO-5 OW mR/hr CW mR/hr OW mR/hr CW mR/hr S/N 69 86.2 2.1 85.6 2.1 0.500 86.2 2.1 85.5 2.2 86.7 2.3 84.8 2.1 86.5 2.2 85.3 2.1 86.4 2.2 84.9 2.1 86.6 2.2 84.7 2.1 86.7 2.3 84.2 2.2 86.7 2.3 85.0 2.2 86.8 2.1 84.5 2.0 86.0 2.0 84.6 2.3 86.8 84.8 86.9 84.2 86.5 84.8 86.4 84.2 86.3 83.9. 87.1 83.6 87.1 84.8 87.7 84.1 87.8 85.3 87.0 84.8 87.5 X 86.8 2.2 X 84.7 2.1 2.06 uCi 2.06 uCi 42.12 mrad /uci-hr 41.11 mrad /uci-hr Average' Instrument Response 41.61 mrad /uci-hr-Page-4 of 5

N Por onsmitrata, lat. i ts an.. t E ROAD AttCC[yggnt .( A R DMOR E. PA. 19003 233-896-5333 i Cumulated activity 21.867 uCi-hr i Depth Beta Gamma Total cm rad rad rad /ca"2 3 0.007 48.216 3.411 51.628 t 1 0.064 16.335 1.990 18.324 I i i.. 1 i i i ? 4 i j 1 I i i i t Page 5 of 5 4 i- -..--...-......:-..a....-..2

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Revision O i February 15, 19811 CERTIFICATE OP: CAL 111 RATION 1 \\1 l I TEST EQUIPMENT INSTRUMENT INFORMATION Activitv t Standard Source Date~ Instrument Mfr. BICRON 'h_ '.2,Sem Round 24 a F11eer '2.06uci at Mode 1 N nm-sn Serial' No. %no r nnnem 1900 hrs Externa 1 616 t l' h 4 c5n hq. 24Na Filter 2.06uCi at Probe -NONE Seria1 No.- 3 Paner Source 1900 hrs Cal. Procedure SPECIAL INSTRUMENT CALIBRATION INFORMATION- -[ I I Instrument Calibration Instrument Response l -Range Standard Value Per uCi " Response Ca1.- Tirm of Cal. IC3 at 1/8" O W 2.06 uCi 34 y mR/hr-uCi 70 mR/hr 1900 hrs 3/14/90' 20 at 1/8" c W 1.5 mR/hr-uCi 3 mR/hr 3/5 at 1/2" O W . ' 27 mR/hr-uCi 55 mR/hr 4fi nr 1/2" C Q 1 mR/hr-uCi 2 mR/hr 5/A at 1/8 O Q ~ 34 mR/hr-uCi 70 mR/hr A 68 ar 1/8" c W 1.5 mRhir-uci 3 mR/hr. V 7i'l) at 1/2" O W in mR/hr-uci 62 mR/hr O M at 1/2" C 54 9-1 mR/hr-nri 2 mR/h 10 11 t t 13 - g -i l 4__ 15 Calculation of R9sults ADDITIONAL TESTS Type of Test Next Test i + Results Test Date -Due Date t Comments: Mnneial calibratinn en elet ot ni no t-ho renmnme,g t ho RM-9n en a 2 __ _ __ contaminated (l cm ) thumb of a worker. i 1 v nstrument Calibrated by: S.W. Porter, Jr. and Coorgo Vargo hrs. Calibration date: 3/14/90:38:30 hrs to 19:30 Next Calibration due: N/A Reviewed by: [ / Date: 3/20/90 S.W. Porter, Jr.,' CilP

4.* i. A'PUCitMr.tfl' 7.8 M -TR-324 Porter Conouttants. Inc. its anovec noao anovont.ea isoos PCI-PORM-12 ' s-aes. sis a Revision 0 February 15, 1988 CERTIFICATE OF CALIBRATION a TEST EQUIPMENT INSTRUMENT INFORMATION Standard Sourca Activity and Date Instrument;Mfr. EBERLINE -h Round 2.5 cm NA Piltar 2.06 uc'i at Model'_ D 5 Serial No. 69' Parer 1900 hrs. Externa 1 Probe NONE - Serial No. h sq t= ra a,J -~~ 24 a f $ er ?_06 mi at N Panor 1900 hrs Cal. Procedure SPECIAL INSTRUMENT CALIBRATION INFORMATION 3/14/90 Instrument Calibration Instrument Response _ Range Standard Value Per uCi response

Cal, 13 at 1/2" CW 2.06 uCi f4 a 42.1 mrem /hr-uCi 86.8 mR/hr avo of 20 w as.__

N 2G at 1/2" OW 2.06 uCi "NA 1.1 mrem /hr-uCi 2.2 mR/hr ' avg of 10 meas. ~ 3 O at 1/2" OW 2.06 uCi 24Na ,41.1 mrem /hr _uCi 84.7 mR/hr ava of 20 meas. 4[1) at 1/2" CW 2.06 uCi Na 1.0 mrem /hr-uCi 2.1 mR/hr-avg of 10 w as. 5- ~~ ~ ,O ;6 ~- i i 9 I 10 i, i1 12 13 l4 ~ ~ ~ ~ ' 15 '4 Calculation of Results ADDITIONAL TESTS Next Test Type of Test Results Test Date Due Date ~ I i 4 Comments: _jirecial Calibration to determine tiv rosponso of tho RO-5 to a j 2 1 contaminated (4 cm ) thumb of a workor. nstrument Calibrated by: S. W. Port or. Jr. and Coorno Varao hrs. Calibration date: 3/14/90: 18:30 hrs to xt] Calibration due: N/A Reviewed by: __ S.W. Portof, Jr., CitP Date: 3/20/90

44' servteos 0.portment ATTACILkDTT 7.9 FCI-TR-324' James ~A. FitsPetrick m,u..r e., n.nt RECElVED

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l r m ' ;; x :, aa w*** ATTACFD4ENP 7,10. 0; David D. O'Brien, M.D. 32 W. Oneida st. osvego, New' York 13126. March 14, 1990 i i George J. Vargo, Ph.D. New York Power Authority 1 James A. FitzPatrick Nuclear Power Plant ' P.O. Box 41:: Lycoming,-New York 13093

Dear Dr. Vargo:

I have reviewed the contamination problem of W O R K'E'R P occuring on March 8, to his left thumb. 1990, with regard to radioactive - sodium' 24' NORKER P i ,,has received considerable decontamination, according-j O, to your statement, removed. and all. evidence--of contamination,has been-a I examined WORKER i) _ on March 13, 1990.- My examination reveals i markedly highly karatenization of both palms and thumbs. is no evidence of physical injury, (including eyrethema). :The There-left thumb has obviously been scrubbed considerably with removal i of considerable amounts of keratinized layer,.- but continues to - still have a very thick stratum' corneum. j I have reviewed the reference tablestin the Renort'of Task Groun. on Reference Man, ICRP Publication No. 23, pages,46-54 It is clearly evident from the refereace table No. 6,-that WORKER P is at the high end of the stratum corneum' layer (i.e. 673) and I would estimate his layer to be'at least 600-673pm (even after decontanination efforts). If I may be of further assistance to you, please contact me. j very truly yours, i hQt) hCe. M O " David D. O'Brien Jr., M.D.ec1 > " 41c 1 c "1* "* New York Power Authority I l

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ATTACINENT 7.13 KI-TR-3244.. W t, 03/09/90 11i19:SS ~ PAGE'lof 4 E t,8WS,************************************************.** * * * * * * * * * * ** *O * ** ***0c t * * ; ! GDR/HP. P;E A K' -S E A.R C-H R E S U L T.S-Verst en 2.1' - l ~ New York. Power Authority _ - 4 J. A. Fit: Patrick Nuclear Plant

- - - - t;******************************************

' WORKER P ~ Mau!D BIO Analyzed byi BB File.ID -EXIT-Sompling-Start Dates. .03/09/90 19:53 > Sampling Step Dates 03/09/90-10:53 Sanple Duratieni. .00.' Hrs Sample Size .-i.000E+03 nli Yieldi. 100.0000 X _Corrent Datei.. .03/09/90 iiii?J Covnting StaFt-Detoi. .03/09/90 10iS3 Live Tine. .1500.sec! D cay-timei .00 Hrs Clock Times 1500.sec D3tector.4. 4 Energy (kev)= 2.SSE-Oi+9.98E-Oitch+1.06E-06*Ch*2+0.00E+00*Ch'303/09/9009i05$ FWHM(kev)- = 1. 56E+0 0 +-3. 0 9E-0T!*En +. i. 40E-03*En *2+ 0. 0 0E+0 0*En *3 'it/ 06/S9 08 : 24 (Where En=SGRT(Energy in kev)) PEAK SEARC .........................................H RESULTS'- Poak Sensitivityi. 2.00 Search Start /End i 0/2049 PK. ENERGY CENTROID NET UN-C.L, BKC_ CH'IN FWHM (kev)- COUNTS CERTAINTY COUNTS: COUNTS FLAG. O----------CHANNEL- ---- - PEAM'(kev) o ^ N 4M. AVt4rd 4 l l I l I L d 5 1

c.O 1

q d .,_m _... -..... _ ~.., .s,.,w y ,.m.,.,,,

y., _,,

.,,..-c.,y,_ _.7.-,--.r.,# y .,..g

[.*.* PCI-TR-324' 03/09/90 11:19 BB .., $$$8888888888888888888888888888888888888888888888888888888888888888888888888888; -Pago 27 GDR/HP. zL I B-R A R Y S E;A R C H 8UMMARY .Versten 2.1-8888888888888888888888888888888888888888888888888888888888888888888 f W0mTR P LIQUID-BIO Reported by: BBL File-IDi EXIT Library Filei .LWJLIB. LIB (Liq. Fil'ter & Filtrate-Isotopic-Lib )l =o m================.... .m=e me=========...========.................... LIBRARY SEARCH RESULTS a Om os s e s.s e a m m e m a m ma m e s s e m e s am m e n en e m m as a mama ssa m m a sa m m a Library. Match Resolution 2.00-PK. ENERGY NET EXPECTED % OF. % ABN.- 9-(kev) COUNTS WET CNTS PNS. FOUND F = = = = = = = = = = = = w = = =............I S O T C P E....u.======........... SCORE FLAG < l 1 a i i i 4 1 . ors l

- p, - ATTACHMENT 7.13. PCI-TR-324- 'a 93/99/08 &$iif BB .c Pcy. 3sN ',88'83i088888888882808888888383888888888888088888888888888888888888888888888888888-U -SD8/MPo NUCLIDE ANALYSIB 8 U M M-4 8 Y Version 8.1 New York Power Aetherity-

3. A.. Fit Patrisk Nuclear Plant o

.**************88888888888888888888888888888888888888888888888888888888888888888- ,ss WORKER P 1 LIGUID DIO Reported byi BB t File ID EXIT Library Filei .LWJLIB. LIB (Liq.-Filter 6 Filtrate Isotopic Lib ) MPC/LLD Filei ...LQ8LLD.MPC (Soluble Liquid Filtrate Samples ) 'Dotector 6: ~4 Efficiency Filei-. iLLLSAD04.EFF (i LITER POLY 9OTTLE ). Eff. 1/(-3.20E+008En'-i 52E+00'+ 1.07E+03*En" 9.42E-01)L05/17/89105 29; (Where En = Energy in HeV) MEASURED or MDA - CONCENTRATION Energy Concentration Less-Than Peaks LLD. LLLD Nuclide Group (kev) (vCi/n1 )_ Leve Found REQUIRED MET? l 00..................................................l Conc. CE-144 133.54 ( 8.83E-07 MDA 3.23E 0 of i 5.E-95 Yes CE-141-145.-44 ( 2.10E-07 MDA 8.96E-08 0 of i 5.E-05 Yes i 1-131 364.48 ( i.75E-07' MDA 6.2iE-08 0 of 1. 1.E-06 Yes i CS-137 661.65 ( i 5BE-07 MDA 4.84E-09 0 of i 5.E-07 Yes MO 739.58 ( i.60E-06 MDA-4,52E-07 - 0 of 3 5.E-05 Yes -134 795.85 ( 2.99E-07 MDA 8.80E 0 of 6 5.E-07 Yes . -58 810.76 ( i 70E-07 MDA 7 SiE-08 - 0 of - 2 '5.E-07 Yes -MN-54 834.83'( 2.01E MDA 1.07E-07 0 of 1 5.E-07 Yes FE-59 1099.22 ( 4.98E-07 MDA 1.65E-07 0 of 2 5 E-07 Yes ZN-65 1115.52 ( i.13E-07~ MDA 1.80E 0 of i 5.E-071Yes CD-60 1332.49 ( 2.38E-07 MDA 1.63E-07 0 of 2 5.E-07"Yes TOTAL MEAS. ACT. 0.00E+00 +- 0.00E+00 vCi/mi i 4 o i'

1 t. j-d'. ' 03/09/99 itsit 93*

Page, 4 4f f

',.i.. es s ss s ssss ss s s s s * * *

s e s s s s s ssss ss s ss s s ssss ss s ss ss sssss s sssss ss s,ss s s.

sssssssssssesl i H P C: C'H E C K MPC FILEe.LGsLLD.MPC .s*****ssssssssssssssssssssssssssssssssssssssssss****ssesss***ss***stsesessssses 'Nuclide vC1/n1 MPC % MPC 'i TOTALi-0.00E+00 0.00E+00 3 f 4 I ( I h I I l ik l l i i i L O e i ...s .-a,a

y,, _. y' - ATTAONEift 7.14 PCI-TR-324 NEW YORK POWER AUTNCRITY Page 1 of 3 JAFNPP TRA1NING DEPARTMENT F0RMAL T4A!NING NIsTCRY. AS OF: 9/E2/88 PAGE: 1 JAFS10 .'OTT WORKER R 4 y saAN: 13938.i272 TRA!N!NG CAlTGORY: RADIAT!au & EW!R0eggNTAL TECHNICIAN TRAINING DEPT: RE: ITP#: 7 RANGE: 1/01/87 70 12/31/8T' COURSE TOPIC: RADIAT!DN OVEREXPQsuRE INCIDENT. CAUSES & CORRECT!YE ACTION PREQ: '1 ~ EVAL: SAT PROG CocE 10 7.7 LE880N PLAN: UR!R 87 43 ' OBJECTIVE: SEE ADDITIONAL TEXT DATES: 3/02/87 'ATTND: 1.5 .0 .0 .0 .0 REFERENCE # SEE ADDITIONAL TEXT A88NT .0 .0 .0 .0 .0 DESCRIPTION: IEE A00!TIONAL TEXT GRAD 1 SAT INSTRUCTOR: VARICUS SRADE: - LOCATION: JAPNPP ......................................(EtAD3s COURSE TCP!C: N!aSING CONTROL ROD ROLLER GUIDE BALL FREE: 1 EVAL: N/A PROG CODE: 10 7.11 Lass 0N PLAN RES.JRE9 87 0Ad DATES: 3/0P/87 OBJECT!VE: INFORM STAFP AND IMPROVE PERPORMANCE OF JOB TASKS ATTIC: .0 .0 '0 .0 .0= REFERENCE #e MEMO JRES.87 086,' EAs 28 0387 L0ff PARTS ANAL. OF CRD BALL ASSNT: .0 .0 .0 .0 .0 s DESCRIPTION: REeu! RED READING ORAD 1: N/A INSTRUCTOR: NONE GRAD 3: LOCATION: JAFNPP ...................................... GRAD 3 COL,RSE TOPIC RES DEPARTMENT PROCEDURES AND PROGRAMS h LESSON PLAN: REs.3*5 87 FRE0: 1. EVAL: N/A PROS CODE: 10 7.11 DATES: 3/13/87 OBJECTIVE: INPORM STAFF AND IMPROVE J08 PERFORMANCE ATTMD: .0 .0 .0 .0- .0 - REFERENCE #3 RES 030 08 (REY.0) SUPERVISORY CVER$1GHT OF RADIOLOGICAL hNtK AtsN .0 .0 .0 .0 .0 m DESCRIPTION: REQUIRED READING GRAD 1: N/A-INSTRUCTOR: NONE GRAD 2: LOCATION: JAFNPP ..................................... GRAD 3: COURSE TCPIC: RES DEPARTHENT PROCEDURES & PROGRAMS ASS!GNED 410 87 4 LES$ON PLANT RES-4*10 87 PREQ: 1 EVAL: N/A PROG CODE: 10 7.11 DATES: 4/13/87 ORJECTIVE: INPNtM STAFF AND IMPROVE JOB PERFORMANCE ATTND: .0 .0 .0 .0 .0 > REFERENCE #: Af910NIA QUTGASSING CF DRYWELL INSULATION CURING STARTl)P ABSNT: .0 .0 '.0 .0 .0 DESCRIPTION: REQUIREC READING INSTRUCTOR: NONE GRAD 1: N/A GRAD 2 LOCATION: JAFNPP ......................................GRA03: t t COURSE TCP!C: ACC! CENT CHEMISTRT CONSIDERATIONS LESSON PLAN: RES*34 4 FREQ: 1 EVAL: N/A PR00 COCE: 10 7.7 DATES: 4/27/87 CSJECTIVE: PER LP RES-34 4 ATTND: 8.0 .0 .0 .0 - .0 REFERENCE #: CNEMISTti RESPONSE TO EMER0ENCY AND ABNORMAL EVENTS AR$NT: .0 .0 .0 .0- ,0 I DESCRIPT!CN GRAD 1: -N/A INSTRUCTOR: R. J. DENEVE GRAD 2 LOCATION: JAFNPP GRAD 3: COURSE TOPICS RCS CHEMISTRY TRANS!ENTS 4-= FREQ 1 EVAL: PAS $ PROG CCCE: 10 7.7 LESSON PLAN: RES.34 1 DATES: 4/28/87 OBJECTIVE: PER LP RES.34 1 ATTWD: 4.0 .0 .0 .0 .0 REFERENCE #: CHEMISTRT RESPCNSE TO IMERGENCT AND ABNORMAL EVENTS ASSNT: .0 .0 .0 .0 .0 DESCRIPTION: INSTRUCTCRs R. J. DENEVE GRA01: 92 GRAD 2: LCCATION: JAFNPP ..................................... GRAD 3:

RSE TOPIC: DOSINETRY RECORDS, CALIBRAT!cM & SPECIAL PURPOSE COS! METERS FREQ: 1 EVAL: PASS PROG C00!: 10-7.2

$30N PLAN: RES 25-3 6 DATES: 4/29/87 4/30/87 OBJECTIVE: PER L.P. # RIS.254 416 REFERENCE #: ATTND: 8.0 8.0 .0 .0 .0 DE80l!PTION: AESNT: .0 .0 .0 .0 .0 GRAD 1 N/A 96 INSTRUCTOR: J. V. W!ERcWsx! GRA02: LOCATION: JAFNPP ... GRAD 3. _.,, _e. s a m - ~ - ~

t & ~ j 'T h* ATTtCg g r 7.14

PCI-TR-324 NSW YORA: POWER AUTNORITY Page 2 of 3 JAFNPP TRAtNINs DEPARTMENT F0RNAL TRAIN!RS N15Y0RT.

. At OF: 9/II/tg PAGE: 2 JAF310 COTT K)RKER p saRN: 139 34 1272 TRAINING CATEsaT: RADIAT!au & ENVIRONMENTAL TECHNICIAN TR SEPT: RE8 ITPts ? RAmeE ' 1/01/87 TO 12/31/87 COURSE TOPIC: INSPECTION REPORT 50 333/67 07 D LE980N PLAN: R28 3 14*87 FREgg - 1 EVAL: N/A ~ PROG CODE: 10*7.5.6 DATU: 6/1$/87 QBJECTIVE: INF0lgt STAFF & tetoVE PERFoitMANCE ATTND:. .0 .0- .0 .0 .0 REFERENC88: WRC INSPECTION REPORT $0 333/87 07 AssNT: .0 .0 .0 .0 .0 DESCRIPT!aN: REeUIRB mEADING GRAD 1: N/A INSTRUCTOR: RELF STU W GRADE: LOCAfl0N JAFIEDP ..... GRAD 3: C:3JR88 TOPIC R25 OEPT PR'mws & PROGRAMS 189UED 3/25/87 Leas 0W PLAN: REs 3 35 47 preen 1. EVAL: N/A PROG CODE: 10 7.5.6 - DATES 4/15/87 l QBJECTIVE: INFORN STAFF & INPROVE PERFORMANCE ATTMD: .0 .0 -.0 .0 .0 REPERENCE9: RPOP.01 (REY.4) REFUELING FLOOR RADIATION PROTECTION CovtgA AggNT: .0 .0 .0' .0- .0 e 088CRIPT10u ResutRED READING INSTRUCTOR: sELF -ORA 011. M/A QRAbtt LOCAT!0N JAPNPP l ...................................... GRAD 3: l COUR88 TOPIC: REs DEPARTMENT PROCEDURES & PROGRAM $ ASSIGNED 3 7 87 LEt90N PLAN: RES-3-7 87 preen 1 EVAL: N/A PROC CODE: 10 7.11 DATES: 6/15/87. CBJECTIVE: INFORM STAFP AND IMPROVE JOS PERFORMANCE ATTNO: .0 .0 .0 .0 .0 j

REFERENCES:

SEE ADDITIONAL TEXT 48WT .0 .0 .0 .0 .0 - DE8CRIPTION: REGUIRED READING INSTRUCTOR: 180ME J Q1: N/A LOCATIDsta JAFNPP .ADE: .....................................GRA03: .i ' COURSE TOPIC: RES PROCEDVRES AND PROGRAMS ISSUED 6/11/87.......................... 'FREg 1 EVAL: N/A PROG CODE: 10 7.5.6 LES$0N PLAN: RE5*6*11 8FA DATEtt 6/15/67 OBJECTIVEt INFORM STAFF AND IMPROVE PERFORMANCE ATTND: .0 .0 .0- .0 .0

REFERENCES:

SEE ADDITIONAL TEXT Assert .0 .0 .0 .0 .0 DESCRIPTION: REQUIRED READING GRAD 1 N/A INSTRUCTOR: SELF STIA)T { GRAct: LOCATION: JAFNPP CAAD31 COURSE TOPIC RES PROCEDURES AND PROGRAMS ISSUED 6/11/87 j' FREQ: 1 EVAL: N/A PROG CODE: 10 7.5.6 LESSON PLAN: RES 611878 CATEst 6/15/87 OBJECTIVE: INFORM SiAFF AND IMPROVE PERFORMANCE ATTND: .0 .0 .0- .0 .0 . j REFERENCE #: SEE AD0!T!0NAL TEXT ABSNT: .0 .0 .0 .0 .0 DESCRIPTION: REQIRED READING GRAD 1: N/A INSTRUCTOR: SELF GRA32 LOCATION: JAFNPP ....................................... GRAD 3: COURSE TOPIC: RES PROCEDURES ANC PROGRAMS !sstED 6/11/87 FREQ: 1 EVAL: N/A PROG CODE: 10 7.5.6 LES$0N PLAN: RES*6 11 87C DATES: 6/15/87 3 - OBJECTIVE: INFORM *TAFF AND IMPROVE PROFICIENCY ATTMD: .0 .0 .0 .0 .0 REFERENCE #: SEE AD0!TIONAL TEXT AnsNT: .0 .0 .0 '0 .0 DESCRIPTION: REQUIRED READING GRAD 1: N/A INSTRUCTOR: SELF STUDY GRAD 2: LOCATION: JAFNPP ..................................... GRAD 3: RSE TOPIC: AUXILIARY SYSTEMS CHEMISTRT/ PLANT EFFLUENTS PRE 0: 1 EVAL: PAS $ PROG CCCE: 10 7.8 LE$$cN PLANI RES EFFLUEl(TS DATES: 7/20/87 OBJECTIVE: E0's 1 THRU 7 PROM RES.34*2, & ALL OF 485 35 2&3 AtTND 8.0 .0 .0 .0 .0

REFERENCES:

SPDES PERMIT, RETS, RES-34 2, RES 35 2. RES 35 3 ABSNT: .0 .0 .0 .0 0 DESCRIPTION: LECTURE, EXAM GRAD 1:- FE INSTRUCTOR: DENEVE GRAD 2 LOCATION: JAFNPP ...................................... GRAD 3:

x tN. I ^$ w PCI-TR-324 - 0*' ATTACHMENT *l.14 Page 3 of 3 JAFMPP TRAINING DEPARTMENT NEW YORK P0hER AUTNORITY l \\ P0tNAL TRAIN!ug NI570RT. AS OF 9/32/8B PAGE: 3 JAF310-1 I . Tirri WORKER P seam 139 3s.1ETs TRAIRING cATEoGRT: RADIATr0N 4 ENVItasefTAL TECNNICIAN TRAINING i-DEPT: RES TTP#2 7 RANW: 1/01/87 TO 12/31/87 i 4 COURSE TOPIC CNIN LAS EMPLDSION FRES: 1' EVAL: N/A PROG CIDE: 10 7.11 l LESIGN PLAN: RSS SER 10 87 DATES: 7/30/57 ATTND: ~ .1 .0 0 .0 0 l OBJECTIVE: 0' .0 0 AssNTs' 0 .0 REPsRENaps INPO SER 10 87 DESCRIPTION: REGUIRS READING MAD 1 N/A ORADRs INSTRICTOR:. ERA 03: j LOCATION: JAPNPP C MeSE TOPIC RSSIM INTRU510N INTO REACTOR 000UWT ~ -PROG 1 EVAL: N/A PROGC00d 10 7.11; LE980M PLAN: RES 55R.16 87 DATBs 7/20/87 0 .0 0 08J8CTIVIs RSC00NITION OF U stu INTRUSION VIA WAftR CHENISTRY AT115: .6 .0 0-REFERENCE # INPO BER 16*87 ABSNT: .0 .0 - 0- .0-i l# ' Of5CRIPTION: SELF.8T18Y ORAD 1 N/A GRA02: INSTRUCTOR: N/A LOCATION: JAFuPP mA03:. .................................................................l COURSE TOPIC RADIATION PROTECTION STANDARDS & REalLATIONS P FRAG: 1 EVAL: PAtt PROG CIDE: 10 7.2 4' Las9ON PLAN: RE8'17-1 DATEst 7/22/57 7/23/87 ' 0. OBJECTIVE: PER LP RSS 17-1 ~ATTND: 3.1 7.0-0 .0 REFERENCE # PER LP R89 17 1 . AggNT:. .0 ~.0 0' .0' .0 OtsCRIPfl0N: LECTURE GRADi: N/A - 100 !NarrRUCTOR: J. WIEROWsg! 3 RAD 3: I LOCAT!0N: JAFNPP QRAD3: - M CtutsE TOPIC: THERMOLUNINESCENT Dos! METER CALIBRAT10N FREen 1 RVAL: SAT PROG CtBE 10 7.2 LESSON PLAN: RE8*25 4.L1 DAfts: 7/31/87 DEJECT 1vts DEVELOP DOS! METRY OPERATION SKILLS PER LP REs-25-4 L1 ATTWD: 4.0 .0 .0 .0 .0 REFERENCE #I PER LP # RES 25 4*L1 AB8WTs. .0 .0 .0 .0 .0, j DESCRIPTION: LASORATORT ColRC!st ORAD 1: N/A t INSTRUCTOR: J. W1EROWSK! RAD 2:= LOCATION: JAFNPP GRAD 3: ] COURSE TOPICS MIS $!NG CONTROL RCC ROLLER GUIDE BALL 'FREQ 2 EVkL N/A PROC CODE: 10 7.11 LESSON PLAN: REE JRES.07*006 DAfts: 7/23/87 OBJECTIVE: INFORio STAFF AND IMPROVE PERFORMANCE OF J05 TASKS ATTND: .2 .0 .0 .0 0' I , REFERENCE # MEMO JRES-57 086, EAS 28 0357 LOST PARTS ANAL. CF CRD SALL AssNT: .0 .0 0 .c .0 DESCRIPTION: REQUIRED READING GRAD 1 N/A INSTRUCTOR: NONE GRAD 2: LOCATION: JAPNPP GRAD 3 COURSE TOPIC: REMOVAL OF PERMALI SHIELDING MATER!AL FROM N.1 AND N 2 FREQ 1 EVAL: N/A PROD CODE: 10 7.11 LES90N PLAN: RSS M00 F187009 OATES: 7/23/87 I OBJECTIVE: INFORM TECHNICIAN $ OF PLANT MODE AFFECTING RAD. PROTECTION ATTND: .3 .0 .0 <.0- .C REFERENCE # Mim PACKAGE F187009 ABSNT: .0 .0 .0 .0 .C DESCRIPTION: REQUIRED READING, DISCUSSION CRAD1 N/A INSTRUCTOR: J. WlEROWSK! GRAD 2 1

JtAD3 LOCAT!cN: JAFNPP s

COURSE TOPIC: INSPECTION REPORT $0 333/87 06 AND EW ORCEMENT ACTION FREQ: 1 EVAL: N/A PROG CCCE: 10 7.11 ~ LESSON Pl.AN: RfS*NRC 87 06 DATES: 7/23/87 OBJECTIVE: INFORM PLANT STAFF ATTND: .3 .0 .0 .0 REFtRENCEd INSPECi!ON REPORT $0 333/87 06, EAFORCBENT/ VIOLATION 87 07 ASSKT: .0 .0 .0 .0 DESCRIPTION: REGU1 RED READING GRAD 1 N/A INSTRUCTcA N/A ORAD 2: LOCAT!0Na JAFNPP GRAD 3: 6 e -s-e, ~ ,y e- -g-r

' 'l 4'* -*y... '[e r ertcr' Comoultacts. ICc.-

*
les ANGYL.E hoAD -

- (.R OMo R E. P A. 19003

s wsan.

PCI-TR-324 '.15 DOSE TO RIGHT HAND OF WORKFR P (a rouch calculation) A. General Data M 1. IAft thumb pad contamination of 3.5 pCi Na was transferred during removing right hand glove with bare left hand. IAft thumb most likely touched tip of right hand glove (thumb and right index finger) (Worker P Statement). 2. ' Highly contaminated right hand glove remained on right hand for about 5 minutes (Worker P Statement). 2 3. Worker P was wearing on right hand-cotton glove 10 mg/cm (on,) surgeon's glove 14 mg/cm (one)- 4. Worker P right thumb pad stratium corneum is about same thickness as left thumb pad (64 2 mg/cm ), B. Calculptions 1. Assume a conservative 5% transfer of contamination from right hand to left hand.. Assume > j 2 right hand thumb also had a contamination area of 4 cm,- 2. Then right hand contained 70pCl"Na for 5 minutes, or 3.5 pCl hr. 3. From above A.3 and A.4 above, the total absorption over line skin is 10 + 14 + 64 = 2 88 mg/cm, 2 2 4. At 88 mg/cm the dose rate conversation factor for beta dose is 2.95 rads /hr/pCi/cm, If this 2 2 source is distributed over 4 cm, then this conversion factor becomes 0.74 rads /hr/pCl/cm, '} 5. . 3.5 pCl.hr x 0,74 rads /hr/pCi = 3 rads of beta. If one assumes 10% additional gamma dose,: { then the beta gamma =3.3 rads to the right thumb pad (or fingertips). 2 (Note, if a dead layer thickness of only 7 mg/cm is assumed, then this rough calculation of dose to right thumb becomes 3.5gCi hr x 1.3 = 4.6 rads beta. ,l 1 l 4 ] i O q 1

g lbf 'l e l chrter conouttar.te, Inc.' 1 U 'L m AaovecnoAo An DMOa c. PA.19003 : m.ws " PCI TR-324 l ~-O'.. ~ Attachment 7.16. i i DOSE TO GONADS FTO W 24 Na CON" AMINATION QN l I FFT TE G: 4 OF WORK :R P - I A. QgeralData j p 1. Area of Contamination: 3.5 cm x 3.5 cm (thigh under front pocket) j l a p

2. -

Distana from center of contaminated area to closest external surface ^of gonad:.3 inches '~ (7.62 cm). n L 3. Contaminated measurements at 16.25 hrs.on 3/8510 was : 20 mrad /hr open window with an RSO 50 survey meter,1.7 mrad /hr closed window with an RSO 50 survey meter.L ,i 4. Time of contamination was not earlier than 16:05 ha on 3/8610 : l Time of complete decontamination was before 16:35 hrs on 3/8,90,.'. assume a 0.5 hour. residence time of the contamination on the thigh area.- y. 5. The inherent shielding of the male gonad is 300 mg/cm,. [ 2 B. Calculations 24 l 1. TotalofpCi of Na on thig'. area = 0.6 L

c 2.

0.6pCi for 0.5 hr = 0.3 G hr. l[ i 3. Oamma Dose from24 2 Na: T= 18.4 R cm Mr MCI, thus =.0.32 mR/pCi hr. : 'I l 4. Total namma dose to closest nonad =0.1 mrad + i - 5. The beta dose to the sperm is calculated by assuming a 3 inch distance plus 300 mg/cm in-2 herent shleiding. J 2 6. The beta dose constant through 300 mg.cm plus 3 inch distance' = 0.09 rad /hr/pci of 24 2 j Na/cm, 7. The total beta dose = 0.3 pCi hr x 0.09 rad /hr/ Ci =27 mrad. 8. Total beta namma dose to nonad is much less than 27 mrad (assumes all contamination is in' 3 a 1 cm area of skin which is very conservative). 2-3 i. l 1 ' O Page 1 of 1 .....}}

ML20034C758

Contents

Text

SUMMARY

2.0 DESCRIPTION

4.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

5.0 CONCLUSION

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

5.0 CONCLUSION

6.0 REFERENCES

Subject:

Dear Dr. Vargo:

REFERENCES:

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