ML21102A388
| ML21102A388 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 07/19/2013 |
| From: | Siempelkamp Nuclear Services |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML21103A229 | List:
|
| References | |
| 2013-061, ZS-RP-I 06-002-006, ZS-2021-0010 | |
| Download: ML21102A388 (30) | |
Text
Attachment 1 Personnel Contamination Event Page 1 of2 EVENT GENERAL INFORMATION Log#,}C/3*-IJ hi ZS-RP-106-002-006 Revisioiji 1 Information Use Date/Time 7-/f-lJ
/ /02.'D Name NZe,"4()LA.S. fg:r;AiJT EID '2..l.O'/~
Unit~
Building C ??"'it Elevation
,1;,.'
Company/Group SA>S I
RWP Number 20/g* 1~ 2 005°' RWP Task Num: _.1__
Clean Area Yes ( No TaskDescription Cu7t?Alf, IN'&TII flBS, f\\N~
?tLL?:Pll6
'rVLE) l\\f"I QF Tl-IL wm-~
Worker's Supervisor }';., M:J/:kcll Phone# ________ Contacted Yes No Cal Due Date CLOTIDNG CONTAMINATION Article ofClothin..._ ________ ____ ___ _
Initial activity _____ dpm Final Activity
____ dpm Decou Successful Yes No Disposition of Contaminated Article ______ _
NIA Contaminated (Indicate Location on Figure)
Facial Contamination
/~ '5'" M (DPM)
Positive nasal contamination ___ (DPM)
Loe.
Initial (dpml area Att. I (dpml Att. 3 (dpm/
area Type of Contamination Circle One Distributed Distributed DRP Distn'buted DRP Distributed Level 2/3 PCE, date/time of contamination removal for skin dose calculations _ ___ _
Page 16 of 23 Personnel Contamination Event Page 2 of2 DECONTAMINATION METHOD(S) USED
)("°Tape D
Soap and Water Hand Cleaner Liquid Solvent {ethanol)
Other:~ __________ _
DECONTAMINATION OUTCOME NIA Shower D
Sweating NIA Decon Successfull!!Jf'es (person passes RCA exit monitors)
ZS-RP-I 06-002-006 Revisionll Information Use ON o (Complete ZS-RP-106-002-006 Attachment 3, Contaminated Individual Release Form)
No
'vidual restricted to inside RRA. Report back to RP, as directed.
Worker Signature/ Date--=-_......,,.__,c;..:;;_ _____ __,I 7 -/ ?- I ??
RPT I Date ~()
I 7-/'f ~ t.3 CAUSE OF CONTAMINATION EVENT:
Radworker Practice D PCs wet due to sweating D Tom or Failed PCs D Non-compliance D Housekeeping D Undressing Practices RP Issue 0 Inadequate RP Coverage
~
Inadequately Prescribed PCs D Inadequate Work Area D Unplanned Contamination Spread OFromPCs D Failure of Engineering Controls Accej>ted Potential for Contamination D Safety lssues.'Heat Stress D Inadequate Job Preparation D Touching exposed skin with Contaminated hands.*equipment
. /
/
Other/ Additional comments: ---""-~
e_e.-=---.,:/h--L.....+-f:;--J~<....L..
~* -=-"""--Lb....__,e-'-"'t?L-'---------
RP OPS Supervision / D...,......_Olf!G.;.....,~=---?'-,::__¥-~==-------------'I 0~/21~
Condition Report Initiat Review Sections for Completeness.
Comments:
~
/
RP OPS Manager/ Date ~"j/; 7(Z'1/JJ Dose Assessment Complete?
Yes tgf No D NIA D WBC Complete? Yes~ No D N/A D Isotopic Complete?
Yesjll No D N/A D Dosimetry / Date
________________ _;/ ___ _
RP Technical Manager/ Date ______________ / _ __ _
Copies: Original to Dosimetry for retention in dose record file Copy to ALARA/Rad Eng for trending purposes Page 17 of23
Log# 2013-061 7-19-13 A SNS worker in Unit 2 CTMT 617' was working on the BMT Bridge retrieving tools from the pool. He was sweating heavily from the heat and humidity. The worker exited the area and alarmed the RCA monitors. A whole body frisk of the worker found a 1.5 million dpm radioactive particle (1.56 uCi Co-60) was found on his left cheek bone. The particle immediately removed with tape. Worker then cleared the RCA monitors.
Shift RP Supervisor and Rad-Ops Manager were notified and an investigation and Issue Review were begun. The worker was wearing a single set of PCs with cotton/rubber shoe covers and tape seams, cotton glove liners and rubbers gloves with taped seams and one pair of plastic gloves. Follow-up survey number 2013-2469 found a 2.5 million dpm (1.7uCi) DRP on the south east canal walkway. The likely source of the PCE was from retrieving the 'L-pick" tool from the bottom of the pool then cross contaminating his cotton hood from his gloves which subsequently transferred to his face. Worker stated that his hood would not remain in place and he had to adjust it frequently while working.
Corrective action performed -
Removing particles via sticky rollers.
Coached the worker regarding work in areas with discrete radioactive particle contamination.
Initiated an Issue Review James M Kenne~ 7 7-24-23
7/22/2013 7:31 :42AM Analysis Report for 22-Jul-13-200001 Particle from PCE GAMMA SPECTRUM ANALYSIS Sample Identification Sample Description Sample Type Unit Sample Point Sample Size Facility Sample Taken On Acquisition Started Procedure Operator Detector Name Geometry Live Time Real Time Dead Time Peak Locate Threshold Peak Locate Range (in channels)
Peak Area Range (in channels)
Identification Energy Tolerance Energy Calibration Used Done On Efficiency Calibration Used Done On Efficiency Calibration Description Sample Number 22-Jul-13-200001
- Particle from PCE
- Miscellaneous Sample 1.000E+00 units
- Zion_Solutions
- 7/22/2013 7:27:30AM
- 7/22/2013 7:27:59AM
- Hot Particle 4" Shelf
- Administrator
- DET03
- 4in hp ss shelf
- 100.0 seconds 102.2 seconds
- 2.18%
, 2.80
- 120- 8192
- 120-8192
- 1.000FWHM
- 6/5/2013
- 7/22/2013
- 313 PEAK LOCATE REPORT Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak Search Sensitivity
- 7/22/2013 7:29:43AM
- 120
- 8192
- 2.80 Page 1 of9
Analysis Report for 22-Jul-13-200001 Peak No.
1 2
3 Particle from PCE Energy {keV) 719.07 1173.24 1332. 52 Centroid Channel 2874.17 4690.59 5327.90
? = Adjacent peak noted Errors quoted at 1.000sigma 7/22/2013 7 :31 :42AM Centroid Uncertainty
- 0. 2727 0.0557 0.0553 Page 2 of9 Peak Significance 3.40 56. 13 54. 57
7/22/2013 7:31 :42AM Page 3 of9 Analysis Report for 22-Jul-13-200001 Particle from PCE PEAK ANALYSIS REPORT Peak Analysis Performed on
- 7/22/2013 7:29:43AM Peak Analysis From Channel Peak Analysis To Channel Peak Energy ROI No.
(keV) start 1
719.07 2869 -
2 1173.24 4675 -
3 1332. 52 5312 -
M = First peak in a multiplet region m = Other peak in a multiplet region F ;;; Fitted singlet Errors quoted at 1.000sigma ROI end 2880 4704 5343
- 120
- 8192 Peak Centroid 2874.17 4690.59 5327.90 Net.Peak Net Area Area Uncertainty 3.55E+0l 21.26 1.11E+04 110.18 1.02E+04 102.06 PEAK WITH NID REPORT Peak Analysis Performed on
- 7/22/2013 7:29:43AM Peak Analysis From Channel
- 120 Peak Analysis To Channel
- 8192 Tentative NID Library Peak Match Tolerance Peak Energy
- C:\\Canberra\\Apex\\Root\\Zion_Solutions\\library\\Zion_LiB.NLB
- 1.000FWHM ROI ROI Peak Net Peak Net Area No.
(keV) start end Centroid Area Uncertainty Continuum Counts 2.07E+02 3.29E+02 7.19E+0l Continuum Counts 1
719.07 2869 -
2880 2874.17 3.55E+01 21.26 2.07E+02 2
1173.24 4675 -
4704 4690.59
- 1. 11E+04 110.18 3. 29E+02 3
1332.52 5312 -
5343 5327.90
- 1. 02E+04 102.06 7.19E+0l FWHM (keV) 0.96
- 1. 92 2.01 Tentative Nuclide EU-152 CO-60 CO-60
7/22/2013 7:31:42AM Page4 of9 Analysis Report for 22-Jul-13-200001 Particle from PCE M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma NUCLIDE IDENTIFICATION REPORT Nuclide Library Used
- C:\\Canberra\\Apex\\Root\\Zion_Solutions\\Library\\ZION_LIB.NLB IDENTIFIED NUCLIDES
- ------------- ----- ----------***,--------*---~-----.. ----
Nuclide Name Id Confidence C0-60 1.00 Energy (keV) 1173.22
- 1332.49 *
- = Energy line found in the spectrum.
- = Manually added nuclide.
? = Manually edited nuclide.
@ = Energy line not used for Weighted Mean Activity Energy Tolerance : 1.000FWHM Nuclide confidence index threshold = 0.30 Errors quoted at 1.000sigma Coincidence correction performed.
free = No coincidence correction required.
Yield(3/4) 10 0.00 100. 00 miss = Nuclide energy was not found in the coincidence library.
Activity Activity (uCVunits)
Uncertainty 1.56E+OO 6.42E-02 1.56E+OO 6.44E-02 INTERFERENCE CORRECTED REPORT Caine Corr 0.991 0.991 Nuclide Name Nuclide Id Confidence Wt mean Activity (uCilunits)
Wt mean Comments Activity Uncertainty
Analysis Report for 22-Jul-13-200001 Particle from PCE Nuclide Nuclide Name Id Confidence C0-60
- 1. 000
?
= nuclide is part of an undetermined solution X
= nuclide rejected by the interference analysis 7/22/2013 Wt mean Activity (uCilunits) l.56E+0O
@ = nuclide contains energy lines not used in Weighted Mean Activity Errors quoted at 1.000sigma 7:31:42AM Page 5 of 9 Wt mean Comments Activity Uncertainty 4.54E-02
7/22/2013 7:31:42AM Page 6 of9 Analysis Report for 22-Jul-13-200001
+
+
+
+
+
+
+
Particle from PCE Peak Locate Performed on Peak Locate From Channel Peak Locate To Channel Peak No.
Energy (keV) 1 719. 07 M = First peak in a multiplet region m = Other peak in a multiplet region F = Fitted singlet Errors quoted at 1.000sigma UNIDENTIFIED PEAKS
- 7/22/2013 7:29:43AM
- 120
- 8192 Peak CPS(%)
Peak Size {CPS)
Uncertainty 3.55487E-01 59.8 1 NUCLIDE MDA REPORT Nuclide Library Used
- C:\\Canberra\\Apex\\Root\\Zion_Solulions\\Library\\ZION_LIB.NLB Nuclide Energy Yield(3/4)
Activity NuclideMDA Name
{keV)
(uCi/units)
(uCi/units)
K-40 1460.81
- 10. 67
-1.14E-03
- 1. 41E-02 MN-54 834.83 99.97 2.08E-03 8.89E-03 CO-60 1173.22 100.00 1.56E+00 7.73E-03 1332.49 100.00 1.56E+00 NB-94 702.63 100.00
-1.4 1E-0 3 6.81E-03 871.10 100.00
- 1. 72E-03 SN-113 255.12
- 1. 93 l.06E-02 6.28E-03 391.69 64.90
-2.33E-03 CS-134 47 5.35
- 1. 46
-8.9 9E-02 6.09E-03 563.23 8.38 2.83E-02 569.32 15.43 3.06E-03 604.'70 97.60
-1.07E-03 795.84 85.40 1.49E-03 801. 93 8.73 2.45E-02 1038.57 1.00
-2.13E-01 1167. 94
- 1. 80
-6.89E-01 1365.15 3. 04
-l.55E- 02 CS-137 661. 65 85.12 2.BSE-03 7.53E-03 Peak Type Tol.
Tolerance Nuclide EU-152
-~
LineMDA Coinc (uCi/units)
Co" l.41E-02 miss 8.89E-03 miss 1.52E-02 0.991 7.73E-03 0.9 91 6.81E-03 0.991
- 1. 0lE-02 0.991 2.14E-01 free 6.28E-03 free 3.45E-01 miss 6.78E-02 0.983 3.SlE-02 0.981 6.09E-03 0.988 l.03E-0~ 0.989 1.05E-01 0.983 1.02E+00 0.990 4.98E-01 1.015 3.64E-02 1.024 7.53E-03 miss
7/22/2013 7:31:42AM Page 7 of9 Analysis Report for 22-Jul-13-200001 Particle from PCE Nuclide Energy Yield(3/4)
Activity Nuclide MDA LineMDA Coinc Name (keV)
(uCilunits)
(uCilunits)
(uCilunits)
Corr
+
EU-152 121.78 28.40 4.66E-04 8.23E-03 l.36E-02 0.990 244.69 7.49 2.51E-02 6.26E-02 0.989 295.94 0.45 2.90E-01 9.31E-01 miss 344.27 26.50
-8.85E-03 l.49E-02 0.993 367.79 0.86
-2.64E-02 4.70E-Ol 0.981 411.11 2.21
-2.52E-02 2.25E-Ol 0.935 443.98 3.11 2.49E-02 l.54E-01 0.989 488.68 0.42 1.09E-01 l.28E+OO miss 563.99 0.49 8.46E-01 l.17E+OO 0.989 586.26
- 0. 46 2.44E-01 1.19E+OO 0.991 678.62 0.47 9.94E-01 l.48E+OO 0.981 688.67 0.86 4.34E-Ol 8.17E-01 0.996 719.35 0.28 1.70E+OO 2.65E+OO miss 778.89 12.74 l.lOE-02 6.25E-02 0.991 810.45 0.32 1.09E+OO 2.87E+OO 1. 009 867.32 4.16
-4.42E-02 2.34E-01 0.988 919.33 0.43 7.23E-01 2.73E+OO 0.996 964.01 1'1.40
-2.94E-02 7.41E-02 1. 004 1085.78 10.00
-5.lSE-02
- 1. OOE-01 1. 003 1089.74
- 1. 73
-1. 05E-02 6.03E-Ol 0.992 1112. 02 13.30
-4.64E-03 7.89E-02 0.998 1212.95
- 1. 42
- 1. 54E-Ol 3.98E-01 0.988 1249.94 0.19 4.03E-01 2.17E+OO 1.016 1299.14
- 1. 62
-3.39E-02 2.65E-01 0.991 1407.95 20.70
-2.39E-03 8.23E-03 0.997 1457.64 0.50 4.08E-02 2.83E-Ol 1.013 1528.10 0.28 O.OOE+OO
- 1. 61E-01 1. 001
+
EU-154 123.07 40.79 l.29E-03 9.33E-03 9.33E-03 0. 990 247.93 6.95
-2.15E-02 6.31E-02 0.988 591.76
-1.99 5.33E-02
- 1. 25E-01 0.986 692.42
- 1. 80
-2.40E-01 3.54E-Ol 0.989 723. 30 20.22 l.45E-02 3.66E-02 0.989 756.76 4.57 3.13E-02
- 1. 68E-01 0.986 873.19 12.27
-3.65E-02 7.88E-02 0.988 996.26 10.64
-2.39E-02 9.37E-02 0. 996 1004. 72 18.01
-1.46E-02 5.65E-02 0.996 1274.44 35.19
-3.32E-03 l.14E-02 0.997 1596.49
- 1. 80
-7.0lE-03 8.68E-02 1. 031
+
EU-155 45.30
- 1. 33 3.17E-01 1.54E-02 9.86E-01 1. 000 60.01 1.13 8.05E-02
- 1. 09E+00 1. 000 86.54 30.70 2.96E-03 l.54E-02 free 105. 31
- 21. 20
- 6.70E-03 1.84E-02 1.000
+
Tl-208 583.19 84.50
-3.35E-03 7.21E-03 7.21E-03 0.988
+
BI-211
- 72. 87
- 1. 20 8.0lE-02 3. 48E-02 5.70E-Ol mis s 351.10 12.20 3.20E-03 3.48E-02 mi ss 404.80 4.10 4.50E-02
- 1. llE-01 miss 426.90
- 1. 90 9.44E-02 2.65E-01 miss 831.80 3.30
-5. 72E- 02 2.53E-01 miss
+
PB-211 404.80 3.00 6.lSE-02
- 1. 51E- 01 1.SlE-01 miss 427.10
- 1. 40 4.59E-02 3.54E-Ol miss 831.80 2.80
-6.74E-02 2.98E-01 miss
7/22/2013 7:31:42AM Page g of9 Analysis Report for 22-Jul-13-200001 Particle from PCE Nuclide Energy Yield(%)
Activity Nuc/ideMDA LineMDA Coinc Name (keV)
(uCi/units)
(uCi/units)
(uCi/units)
Corr ____
+
BI-212 39.86 1.10 2.21E-02 4.68E-02
- 1. 18E+OO 1.000 727.17
- 11. 80
-2.32E-02 5.57E-02 0.997 785.42 2.00
-4.40E-03 4.12E-Ol 0.991 1620.56 2.75 7.95E-04 4.68E-02 1.001
+
PB-212 74.81 9.60 7.SlE-04 1.09E-02 6.61E-02 miss 77.11
- 17. 50 5.68E-04 3.34E-02 miss 87.20 6.30
-l.18E-02 7.30E-02 miss 89.80
- 1. 75
-3.49E-02 2.48E-Ol miss 115.19 0.60 1.09E-01 6.24E-Ol miss 238.63 44.60 4.65E-04 1.09E-02 free 300.09 3.41
- 1. 81E-02
- 1. 22E-01 free
+
BI-214 609.31 46.30
-2.06E-03 l.lOE-02 1.33E-02 0.991 768.36
- 5. 04 5.66E-02 1.57E-01 0.990 806. 17
- 1. 23
-5.70E-01 6.76E-01 0.987 934.06 3.21 l.26E-01 3.58E-01 0.991 1120.29 15.10
-1.09E-03 6.19E-02 0.991 1155.19
- 1. 69
-6.02E-02 4.78E-01 0.990 1238.11 5.94
-1.80E-02
- 7. OlE-02 0.991 1280.96
- 1. 47 2.85E-02 3.33E-01 0.991 1377.67 4.11 4.70E-04 4.51E-02 1. 005 1385. 31 0.78
-l.51E-02 1.87E-01 0.991 14 01.50 1.39 -6.95E-02 l.23E-01 0.991 1407.98 2.48
-2. OlE-02
- 6. 91E-02 0.991 1509.19 2.19 O.OOE+OO 2.07E-02 0. 992 1661.28 1.15 O.OOE+OO
- 1. 14E-01 1. 000 1729.EO 3.05 l.97E-03 5.48£-02 1.021 1764.49 15.80 3.93E-04 l.lOE-02 1.000 1847.44 2.12 2.69E-02 9.66E-02 1. 011 2118. 54
- 1. 21 O.OOE+OO O.OOE+OO 1. 007
+
PB-214 74.81 6.33 l.14E-03 1. 12E-02
- 1. OOE-01 miss 77.11
- 10. 70 9.29E-04 5.46E-02 miss 87.20 3.70
-2.00E-02
- 1. 24£-01 mi ss 89.80 1.03
-5.94£-02 4. 21E-01 miss 241.98 7.49
-7.08E-04 6.22E-02 1.000 295.21 19.20 3.81£-03 2.14E-02 1. 000 351. 92 37.20
-3.83E-03 l.12E-02 free 785.91 1.10
-2.80E-02 7.47£-01 1.000
+
RA-226 186.21 3.28 6.09E-03
- 1. 31E-01 l.31E-01 free
+
AC-228 89.95 2.10
-2.91E-02
- 3. 72E-02
- l. 05E-02 l.35E-01 0.991 209.28 4.40 3.39E-03
- 1. llE-01 0. 996 270.23 3.60 3.50E-02
- l. 15E-01 0.993 327.64
- 3. 20
-9.08E- 02 l.21E-01 0.993 338.32
- 11. 40 5.02E-03
- 3. 72E-02 0.999 409.51 2.13
- 1. llE-01 2.38E-01 0.989 463.00 4.40 l.02E-02 l.21E-01 0.989 794.70 4.60
-l.21E-02
- 1. 88E-01 0.991 911. 60
- 27. 70 2.52E-03 3.90E- 02 0.998 964.60 5.20
-3.20E-02 2.08E-01 0.997 969.11 16.60
-3.48E-02 6.19E-02 0.998
Analysis Report for 22-Jul-13-200001
+
+
+
+
Particle from PCE Nuclide Energy Yield(%)
Activity Name (keV)
(uCilunits)
--~.--------- - ----- --
AC-228 1587.90 3.71 1.86E-02 PA-234M 766.36 0.29
-1. 00E+00 1001. 03 0.34 3.03E-01 TH-234 92.38 2.81
-6.52E-03 92.80
- 2. 77
-2.20E-02 112. 81 0.28 4.47E-0l U-235 89.96
- 1. 50
-4.07E-02 93.35 2.50
-9.41E-02 105.00 1.00
-2.57E-0l 109. 14 1.50
-4.93E-02 143.76 10.50 l.26E-02 163.35 4.70 2.26E-02 185.71 54.00 5.58E-03 202.12
- 1. 00 2.82E-0 l 205.31 4.70
-2.00E-02 AM-241 59.54 36.30 5.67E-03
+
= Nuclide identified during the nuclide identification
= Energy line found in the spectrum
= MDA value not calculated
= Half-life too short to be able to perform the decay correction 7/22/2013 NuclideMDA (uCi/units)
- 3. 72E-02
- 1. 28E+00 1.52E-01 8.19E-03 3.48E-02
?
CAUTION: MDA value is inconsistent with Currie MDA at 95% confidence level Coincidence correction performed.
free = No coincidence correction required.
miss = Nuclide energy was not found in the coincidence library.
, ___________ ---- ~- - ----- -- --
7:31:42AM Page 9 of9 LineMDA Coinc (uCi/units)
Corr 5.58E-02 1.0 00 2.48E+00 miss 1.2BE+00 1. 000
- 1. 52E-0l free l.54E-01 f ree
- 1. 45E+00 free 2.89E-01 miss l.68E-0l miss 3.BSE-01 mis s
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DATE: 7-/ 9-/3
0 External Dose Assessment from Skin Contamination Page 1 of2 ZS-RP-102-004-004 Revision 0 Information Use
~Personnel Contamination Event Information Form A.he AS Name: Fcra.fl-t, SS#(Last4) ____
RWP# ~013 -;2-~005 PCE #: ~013-~ I Affected Location: Skin ofWB _x_Extremity __
Date of Detection: *r - l C) - L '3 Length of Exposure: '3 #? *Z hours Type of x_Point-Skin
_Point-Scrubs
_Point-Clothing/PC-Equivalent Contamination:_Plane-Skin
_Plane-Scrubs _Plane-Clothing/PC-Equivalent Point-Shoes _Other (Specify) ______________ _
Point Source Plane Source
';YS- -,-¥-*15 Activity per unit area (dpm/cm")
Activity~ I, f.;6,,,1.C ;
= IJ/A dpm/ V/4 probe area(cm2)
~c:...,
kl/A dpm/cm 2
=
Dose Assessment (Manual Calculations only) See. c~:tf"C2Cned. \\fo.rsi<-rn prrtJ,1"Dc,)'P,;_
Point Source Activity per Unit Area Plane Source Activity per Unit Area
/
dpm/2220=
nCi/cm2 (dpm/cm2)/2220 =--~
/
Nuclide(s)
I""
Fractional Abundance
)
/
Corrected Activity = Activity per Unit Area x Fract. iy
/
Abund. = (nCi/cm2)
/
For particles, record isotopic activity (nCi)
SHALLOW DOSE EOUIV ALENT
/
Aoolicable Dose Factor (mrem-cm'/nCi-hr)
./
II Dose Rate - Corrected Activity x Dose Factor - (~)
I--!.
Nuclide Dose= Dose Rate x Lenlrth of Time =s.l1fuem)
Shallow Dose Equivalent Total {~,%,WB or SDE,ME) (including any values from continuation sheets for additional n aes)
DEEP DOSE EOUJY ALBNT (NIA this section if not a1>1>licable.)
Nuclides
/
Annlicable Dose &!for (mrem-ll,lll~/nCi-hr)
Dose Rate= Cd"rrected Activity x Dose Factor= (mrem/hr)
Nuclide~se = Dose Rate x Lenirth of Time= (mrem) rose Total (mrem DDE) (including any values from continuation sheets for additional des) 17 of 18 External Dose Assessment Page2 of2 Dose Assessment (Varskin Calculations)
Discrete Radioactive Particle (Point Source Model)
Shallow Dose (7 mg/cm2) = ___,_( _.9......
8"--'0,:___ _____ mrem SOE Record Dose Assignment Point Source Dose Assessment Plane /Distributed Source Dose Assessment ZS-RP-102-004-004 Revision 0 Information Use Dose Assignment to NRC Fonn-5 and Comments Section ofNRC Form-5 jqiO mrem (SDE,WB) or NIA_
mrem (SDE,ME) or NIA_l{_
Dose Assignment to NRC Fonn-5
__mrem (SDE,ME) or NIA~
Deep Dose Assignment to NRC Fonn-5 "2=f.LJ mrem(DDE) or NIA __
Entered into HIS-20 By: __________ Date: ___ _
18 of 18
Page 1 oft Varskin 4 Date: 7/22/2013 Time: 12:57:24 PM
- 2013-061 Friant, Nickolas 220456 SDE calculation Beta Photon Total Point Source Geometry Irradiation Time: 1.96E+02 min Irradiation Area: l.OOE+Ol cm2 Skin density thickness: 7.00E+OO mg/cm2 Air Gap Thickness: O.OOE+OO mm Nuclide: Co-60 Half Life: 46205.59 h Average Beta Energy: 0.096426442 MeV X-99 Distance: 0.031797957 cm Source Strength: 1.56E+OO µCi Initial Dose Rate 5.87E-01 rad/h
- 1. 99E-02 rad/h 6.07E-01 rad/h Dose (No Decay)
- 1. 92E+OO rad 6.50E-02 rad 1.98E+OO rad Decay-Corrected Dose l.92E+OO rad 6.SOE-02 rad 1.98E+OO rad file://C:\\Users\\jrsmithl \\AppData\\Local\\Temp\\tmpBA36.tmp.html 7/22/2013
Page 1 of 1 Varskin 4 Date: 7/22/2013 Time: 12:59:45 PM
- 2013-061 Friant, Nickolas 220458 DDE calculation Beta Photon Total Point Source Geometry Irradiation Time: l.96E+02 min Irradiation Area: 1.00E+Ol cm2 Skin density thickness: l.OOE+03 mg/cm2 Air Gap Thickness: O.OOE+OO in Nuclide: Co-60 Half Life: 46205.59 h Average Beta Energy: 0.096426442 MeV X-99 Distance: 0.031797957 cm Source Strength: l.56E+OO µCi Initial Dose Rate O.OOE+OO rad/h 8.39E-03 rad/h 8.39E-03 rad/h Dose (No Decay)
O.OOE+OO rad 2.74E-02 rad 2.74E-02 rad Decay-Corrected Dose O.OOE+OO rad 2.74E-02 rad 2.74E-02 rad file://C:\\Users\\jrsmithl \\AppData\\Local\\Temp\\tmpE241.tmp.html 7/22/2013
Page 1 of 1 Varskin 4 Date: 7/22/2013 Time: 12:58:40 PM
- 2013-061 Friant, Nickolas 220458 LDE calculation Beta Photon Total Point Source Geometry Irradiation Time: 1.96E+02 min Irradiation Area: 1.00E+0l cm2 Skin density thickness: 3.00E+02 mg/cm2 Air Gap Thickness: S.00E-01 in Nuclide: Co-60 Half Life: 46205.59 h Average Beta Energy: 0.096426442 MeV X-99 Distance: 0.031797957 cm Source Strength: 1.56E+00 µCi Initial Dose Rate 0.00E+00 rad/h S.34E-03 rad/h S.34E-03 rad/h Dose (No Decay) 0.00E+00 rad
- 1. 74E-02 rad l.74E-02 rad Decay-Corrected Dose 0.00E+00 rad 1.74E-02 rad
- 1. 74E-02 rad file://C:\\Users\\jrsmithl\\AppData\\Local\\Temp\\tmpE462.tmp.html 7/22/2013
Plant ID 220458 lndlvldual* RWP Access Records Criteria Selected RWP Number: 2013-2-2005 Job
Description:
SIEMPELKAMP :Operate/ Maintain/ Repair/ Modify/ Decon all segmentation equipment including FAST, BMT, VRS and CH ORCE in or over the cavity pool or in the maintenance stand.
Reg. Guide 1.16 Task: JOB SPECIFIC RWP Name FRIANTNW Entry Date/Time Exit Date/Time 19-JUL-2013 07:11 19-JUL-2013 10:27 Sub-Total DOE (mrem):
ODE (mrem) 5.5 5.5 Total DOE for Selected Records (mrem):
5.5 C.. oyt1:.ccm~~+
e11Jk'y ; ¢tl-5 JC>;2-=7
- Lg; 1,M,Y\\_.
ij.JS -?.o e41+rY ar?:tt -i, 10:-,-:, = lC,6~rt'l.
WBC results I
~ -*
220458 7/22/2013 n,s 0
0 lnvest1gat1onal - Incident 4/25/2013 10:35 0
0 Annual Routine 4/25/2013 10:29 2.73 0 Annual Routine 4/25/2013 10:26 0
0 Annual Routine 5/15/2012 12:30 0
0 Routine lnvestigational Monday, July 22, 2013 Page 1 of 1
Page 1 of3 eB CA\\lncident Forms\\Condition Report CR-2013-000754 (Scope: Global)
Brief
Description:
Stage Eval Due Date PERSONNEL CONTAMINATION EVENT IN
- CAUSE UNIT2 SIG2 Details Code Class
~Date Initiated t1Brief Description iJDetailed Description
}
rimmediate Actions EVALUATION 12/31/2013 Category Age CRSCD
< 1 Day 1/17/2014 CR-2013-000764 eB CA\\Incident Forms\\Condition Report 7/22/2013 Personnel Contamination Event in Unit 2 Containment SNS worker had a hot particle on left cheek. Hot particle was 1 mR/hr gamma and 70 mrad/hr beta. He was working in U2 CTMT 617' North end of the cavity from 0711 to 1027, he was cutting with the VRS (No Blade Changes) and pulling poles (long handle tools) out of the water. The wet part of the poles were not pulled up to the level of the worker. He was wearing one set of protective clothing with hood, no face shield, and was wiping and changing gloves when pulling the poles out of the water. Worker was in the RCA for a little over 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and no improper radiation worker practices were observed. Qualitative hot particle gamma analysis results were 1.50 uCi/g Co-60. Follow up survey preformed on Cavity walkways, Bridge, and Poles. Multiple DRP's found on cavity walkways ranged from 20k to 2 million dpm with sticky roller, Poles ranged from 6k to 10k dpm, Bridge range lk to l0kdpm.
Cavity walkways were decontaminated under 1 Ok dpm with sticky roller.
Worker was locked out of RCA on HIS-20.
Preliminary dose assessment was performed: 1.91 rem SDE, 70.1 mrem DDE and 16.8 mrem LDE No Zion administrative, ES Corporate administrative or Regulatory dose limits were exceeded.
?
Issue Review to RP Recommended Quantify activity in hot particle and perform formal dose assessment for SDE, Actions DDE and LDE.
~Event Date 7/19/2013
~Date Discovered
.->issue Identified By t'Date Reviewed 7/19/2013 12:00:00 AM Initiator 7/22/2013 https :/ / ebzion.energysolutions.com/eBZion/Pluglns/CAP /ConditionReport/ConditionRepor... 7/22/2013
I Maintenance Rule No Applicable?
t>'Reportability N Applicable?
0 t! Operability Review No Required?
.->immediate N Actions Taken?
0
- ,.,Work Request No Initiated?
<S0.75G Issue No t-'72.30D Issue No t-SIG Level SIG2
~ Assigned IR Evaluation tJEvaluation 1213112013 Due Date
~Scheduled Completion 1/17/2014 Date
.!!I Responsibilities Responsibility i::e Initiator RP Organization Name ESH - Radiation Protection Shift Manager PENG Plant Engineering Person Code RCKEENE RDTHORNTON Page 2 of3 Person Name Keene, Chris Thornton, Randall (Randy)
CR Owner DCSF DCS Fuel RXHENDRICKSON He~drickson, Roxanne
.:!I Corrective Actions Number CR-2013-000764-CA00I CR-2013-000764-CA002 Event Summary CONDUCT ISSUE REVIEW - PERSONNEL CONTAMI PERFORM FORMAL DOSE ASSESSMENT
- FORSDE,
.l!.!Trend And Event Codes Trend-Event Code Description A3-B 1 SKILL BASED ERROR Start Date 7/22/2013 7/22/2013 Date Completed 03D Radiation Protection - Personnel contamination event Group Name Weight Cause Codes -1 Event Codes -1 https :// ebzion.energysolutions.com/ eBZion/Plugins/CAP /ConditionReport/ConditionRepor... 7/22/2013
Page 3 of3
.:d Related Condition Reports Number Name Start Date End Date https:/ /ebzion.energysolutions.com/eBZion/Pluglns/CAP /ConditionReport/ConditionRepor... 7/22/2013
PCB PCE Pedro X. Olguin Sent: Friday, July 19, 2013 12:09 PM To:
Deborah A. Nichols; Robert C. Keene; Pamela A. Johnson; James M. Kennedy; Patrick W. Hoppe Cc:
Chris Baker To Supers and Managers, Page 1 of 1 Nickolas Friant had a 1.5 Million dpm particle on his left cheek (70mRem Beta). He was working in U2 CTMT 617' North end of the cavity from 0711 to 1027, he was cutting with the VRS (No Blade Changes) and pulling poles (long handle tools) out of the water. Nick was wearing one set of protective clothing with hood, no face shield, and was wiping and changing gloves when pulling the poles out of the water. Nick stated that he felt some tingling in his left cheek after I removed the DRP. DRP analysis results as follows; all Co-60 1.S0E+00 UCI/G.
Follow up survey preformed on Cavity walkways, Bridge, and Poles. Multiple DRP's found on cavity walkways ranged from 20k to 2Mdpm with sticky roller, Poles ranged from 6k to 10kdpm, Bridge range lk to 10kdpm.
Cavity walkways were deconned under 10kdpm with sticky roller. Worker was locked out of RCA on HIS-20.
Pedro Olguin Sr. RP Tech Zion Solutions 101 Shilhoh Blvd.
Zion, IL 60099 224-789-4190 (W) pxolguin@energysolutions.com
~
/
ZIONSOLUrIONS~
https://esmail.energysolutions.com/owa/?ae=Item&t=IPM.Note&id=RgAAAACROykFLa... 7/23/2013
Zion Station Zion Solutions 101 Shiloh Blvd.
Unit: 2 Permit Number: 2013-2-2005 Revision Number: 4 P
1 Of
,:,/
age:
_.;z_
RADIOLOGICAL WORK PERMIT GENERAL DESCRIPTION Start Date: Ol-JAN-2013 14:35 Type: SPECIFIC R
I FWt* -
..,,.....~,
t,f
- I I I,. '.f: * - -
CONTINUOUS ALARA Review Number : 11-0006/ 13-001 Person-mrem Estimate: 6716 Dose Alarm: B 0 DAC-hrs Tracked: N Work Area
Description:
Containment DESCRIPTION OF WORK TO BB PERFORMED End Date: 31-DEC-2013 23:59 Ou':age Related: N PSE: N Authorization Type: INDIVIDUAL Primary Work Document: C077-WI-11-001 Person-Hrs Estimate: 9866 Dose Rate Alarm: 300 SIEMPELKAMP :Operate/ Maintain/ Repair/ Modify/ Decon all segmentation equipment including FAST, BMT, VRS and CHORCE in or over the cavity pool or in the maintenance stand.
RADIOLOGICAL CONDITIONS OF WORK AREA CONTAMINATION Survey No.: 2012-3324 /
by: RP 3269 Survey Information:
1 -
7 Kdpm/100 cm2 on 617 elevation No alpha detected on: 20-NOV-2012 Comment: See current survey for specific details of your work area.
RAD LEVELS Survey No.: 2012-3269 /
by: RP 3324 survey Information:
0.2 - 21 mR/hr general area on 617' elevation 0.2-1 mrem/hr around cavity and on work platforms.
on: 20-NOV-2012 Comment: See current survey for specific details of your work area.
ANTI-CONTAMINATION CLOTHING REQUIRMENTS ALL ALL ALL ALL ALL WSit3 WET WORK -
DOUBLE GLOVES COTTON LINERS, RUBBER GLOVES BOOT LINERS, RUBBER BOOTS WET WORK REQ. 0/S PLASTICS RP MAY SUB ORECKS VS RUBBER BOOTS DOUBLE GLOVES, DOUBLE BOOTS WS#4 FIRE RETARDENT OUTERWEAR FOR HOT WORK DOSIMETRY REQUIR&:MEN'l'S IED - ELECTRONIC DOSIMETER RESPIRATORY PROTECTION REQUIREMENTS Respiratory Protection:
Conditional Respirator Types:
13M -
L -
905 PAPR - Loose Fitting BRIEFING REQUIREMENTS PRE JOB ALL ALL ALL ALL WSit3 WSH TLD CLOTH COVERALLS FACE SHIELC PER RP DIRECTION SURGEONS GLOVES (AS PER RP SUPERVISOR)
HOOD DOUBLE PC'S OR PLASTIC OUTERWEAR SKULL CAP TO BE WORN UNDER PAPR
Zion Station Zion Solutions 101 Shiloh Blvd.
TRAINING REQUIREMENTS I RAD WORKER TRAINING Unit: 2 Permit Number: 2013-2-2005 Revision Number: 4 Page: 2 of RADIOLOGICAL WORK PERMIT Dose Alarm Rate Alarm Budgeted m~em 1
Operate & maintain VRS & Load Waste 80 300 2
Operate Deep End Equip. & Load waste **HRA Brief Req.**
80 300 3
Entry into an HCA 30 BO 4
Hot Work ** HRA Brie Req.**
80 300 5
RP coverage for load of waste BO 300 6
Remove bolts on DBW/ C. Barrel using long handle tools 30 80
~
Jin
--:1 1 Decontaminate work area as per RP Coverage direction 2 EXIT AREA IMMEDIATELY IF ED ALARMS AND REPORT DIRECTLY TO RP.
3 All individuals that will be performing deconning or repair work on equipment that is in the maintenance stand will require extremity dosimetry.
4 RP constant coverage and approval required when removing items from pool 5 A11 items removed from the pool shall be pressure washed underwater and/ or rinsed with water or/ and wiped down Fhen the item comes out of the water.
Extra clothing may be required to preform this activity.
6 ;:iuring the initial removal from the pool, any item found to be greater than 650 k dpm/lGOcmA2 shall be returned to the pool and re-power washed.
7 When entering a HRA, and the area is also posted C~/HCA then log into the HIS work step for the HRA and utilize the clothing requirements for the CA/HCA.
8 RP HRA BRIEF REQUIRED FOR ENTRY INTO A HRA.
9 When removing equipment inside the HCA, contact RP for survey prior to removal.
10 Perform a survey of the hot work area prior to any welding, cutting, or grinding to evaluate for engineering controls/ TEDE evaluation.
11 All welding, cutting or grinding evolutions will require a HEPA unit.
12 Verify that the CTMT purge is in operation prior to the use of a HEPA unit.
13 RPT to evaluate individual and area for hot particles after removing items from water and work area a~ close of shift 14 Glove changes required after removal of items from water, keep a supply of gloves near or on b:::-idge 15 Long handle tool shall be used for all bit changeouts @ 2 Rem/ hr.contact.
16 ED should be checked every 30 minutes while inside an RCA/RA/ RMA and every 15 minut es while inside an HRA unless di rected otherwise by RPT 17 Whole body contamination monitoring r equired when exiting RCA
Zion Station Zion Solutions 101 Shiloh Blvd.
Unit: 2 Permit Number: 2013-2-2005 Revision Number: 4 Page: 3 of -,,3.._
RADIOLOGICAL wor.K PERMIT 1 STOP WORK CRITERIA
- 1. >1 REM/hr@30cm, LHRA
- 2. > 500 kdpm/100cm2 in work area
- 3. <300:1 Beta-gamma:Alpha ratio smearable contamination:
- 4. >10:1 Alpha:Beta-gamma DAC-fraction Coverage: CONTINUOUS 2 Air sampling required during all decon, maintenance or hot work activities.
Coverage: INTERMITTENT GRAB AIR SAMPLE 3 For all bit changes that are> lRem/ hr. at 30cm but <15 Rem/ hr. at 30 cm. (shielded) requires STOP WORK and RPM approval to continue work.
Coverage: CONTINUOUS 4 Area Radiation Monitors will be set to alarm at 1 R/hr.
Security will be notified immediately upon any unanticipated alarms in association with QOC.
Anticipated alarms will be briefed prior to work.
5 Unit 1 and Unit 2 containments require continuous RP coverage of the pool when RAM QC controls are 1n effect.
6 Perform underwater survey of items, prior to removal, that have contacted milled reactor internals Coverage : CONTINUOUS
,7 The use of the shielding block will be used for all bit change outs @ greater than 2 r em
/hr on contact.
Coverage: CONTINUOUS 8 All waste being removed from the cavity pool that is >500 mrem/hr on contact shall be placed immediately into the appropriate waste container upon removal.
Otherwise, waste will be returned to the pool until the container is available Coverage : CONTINUOUS 9 All waste loading is to be done under the direction of Waste OPS and Radiation Protection.
Coverage: CONTINUOUS RADIOLOGICAL CONTROL APPROVAL Prepared by Date:
SNS Supervisor Date:
SNS ALARA Date:
ALARA Manager Date:
Te rminated by Date:
End of RWP RWP Acknowledgement Log RWP # 2013-2-2005 Rev #4 ZS-RP-104-001-001 Revision 1 Information Use I certify that I have read, understand, and will follow the requirements of this R WP. I have reviewed the radiological conditions for my work area, and that I will NOT exceed the authorized dose limit for this RWP.
Printed Name Signature Date RWP Acknowledgement Log RWP # 2013-2-2005 Rev.4 ZS-RP-104-001-001 Revision 1 Information Use I certify that I have read, understand, and will follow the requirements of this RWP. I have reviewed the radiological conditions for my work area, and that I will NOT exceed the authorized dose limit for this RWP.
Printed Name Signature Date I) JI.) tJ I.A h-rz,~_,q.:...~
Q_I_ ~
t,--2'-l *-13 f1n1i ~
C~ro'to 1\\1\\(~
1-/5*/3 y\\,_~ *- '(\\" ~ t 9 -
A<),,,_//~A-_ L 7 hr//"J f
.