ML20138C164
| ML20138C164 | |
| Person / Time | |
|---|---|
| Site: | 07000184 |
| Issue date: | 05/27/1985 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Jennifer Davis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20138C102 | List: |
| References | |
| 03851, 03899, 3851, 3899, NUDOCS 8512120487 | |
| Download: ML20138C164 (37) | |
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D 8512120487 851029 REG 1 LIC70 SNM-0182 PDR
LIST OF FIGURES Figure 1 Survey Area 3, Gamma Room Page 24 2
Survey Area 4, Neutron Room 25 3
Survey Area 7, Storage Vault 26 4
Survey Area 8, Hollow Cathode Mounting Room 27 5
Survey Area 11, Plating Room 28 6
Survey Area 12, Mounting Room and Welding Area 29 7
Survey Area 13, Company Van 30 8
Survey Area 14, Company Station Wagon 31 10 Survey Area 16, Miscellaneous Floor Areas 33 11A-1 Survey Area 18, in-Core Cable Assembly Area 34A 11A-2 Survey Area 18, in-Core Cable Assembly Area 34B 118 Survey Area 19, I & M Polishing Area 34C 11C Survey Area 20, I & M Phosphor Clean Room 340 11D Survey Area 21, Star Building 34E 11E Survey Area 22, Uranlun Electrode Test 34F 11F Survey Area 23, Uranium Electrode Firing 34G 12 Locations of Sealed Sources 39 13 Neutron Room Survey Points (0.52 Cl, 5.0 CI Pu-Be Source Box) 40 14 Neutron Room Survey Points (0.277 Cl, 2.5 CI Pu-Be Source Box) 41 15 Gama Room Survey Points (5.0 Cl Co-60 Source Box) 42 16 Detector Lab Source Survey Points (10.0 CI Pu-Be) 43 17 Location of Radiation Producing Equipment 46 18 Radioactive Shipping Labels 97 21 Location of Appreciable Quantities of Radioactive Materials for Fi re Protaction Information 104
- Iv -
Revised 6/15/84
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3.2 Uncontrolled Areas 3.2.1 No person shall create in any uncontrolled area any radiation level which:
2 3.2.1.1 Causes any individual in the area to receive a dose to the whole body from external exposure in excess of 0.5 rem in any 52 consecutive weeks; or I
3.2.1.2 If an Individual were con,tinuously present in the area, would result in his receiving a dose in ex-i cess of either two millirems in any hour or 100 t
millirems in any seven consecutive days.
i 3.3 Pregnancy i
If an employee becomes pregnant, she shall immediately notify her j O employer of that fact. No person shall knowingly permit a dose to 4
I a fetus of more than 0.5 rem during the approximately 39 week gesta-i tion period.
It is unlikely that this will be exceeded if the employee does not receive radiation exposure at a rate of greater than 2-3 rems per year, at a more or less steady rate.
I 3.4 Minimum Age An Individual must be 18 years of age or over to*be employed at the industrial and Government Tube Division, except in the case of clerical personnel where the minimum is 16 years of age.
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- Rev. 8-7-80.
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6.
SOURCES OF RADIATION AT THIS SITE i O Source of
. Type of Radiation Radiation Hazard Form Co-60 gamma, beta external sealed source irradiated tubes Cs-137 gamma, beta external sealed source i
Fe-59 gamma, beta external irradiated tubes Pu8e neutron, gamma external sealed sources Am8e neutron, gamma external sealed source i
Ra-226 ganna external sealed source I
Cd-109 ganna external sealed source Th nat alpha inte rnal unsealed U-234 alpha, gamma inte rnal
' unsealed U-235 alpha internal unsealed I
U nat alpha inte rnal unsealed U depleted alpha internal unsealed C-14 beta internal gas Kr-85 beta internal gas
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i Radiation X-rays external high voltage equipment equipment
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I Miscellaneous gamma, beta external sealed sources 9enerally Ilcensed devices f
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! Revised 6/15/84 j
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O 7.
RADIATION MONITORING 7.1 Detection Instruments 7.1.1 The Industrial and Government Tube Division is equipped with the following survey and sampling instruments:
s One (1) Eberline RM-17 alpha-beta / gamma meter.
Two (2) Eberline PAC-3G alpha meters.
i Three (3) Eberline Model E-400, G-M, gamma-beta meters.
Two-(2) Victoreen Model 440-RF/C, x-ray meter.
Two (2) Victoreen Model 491, G-M, x-ray survey meter.
One (1) Victoreen Model 488A Neutron Survey Meter.
Four (4) Pocket Dosimeters.
One (1) Johnston Lab Triton 9558, H-3, c-14, gamma detector (gas).
One (1) Staplex LV-1 air sampier.
t 7.1.2 The following survey instruments are sent out for calibration by NRC IIcensed laboratory on a 6 month schedule:
Eberline Model E-400 SN 1949 Eberline Model E-400 SN 3437 Eberline Model FN-1 A SN 142 7.1.3 The remainder of the survey Instruments, except the tm PAC-3G alpha meters, are given operational checks on a two month basis, using various check sources.
This work is done under the super-vision of the R.P.O.
Instruments that de not appear O
Revised 6/15/84
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7.2.1.9 Any employe whose assignment requires that he work with potentially externally-hazardous radioactive 1
material or radiation equipment shall wear a film badge.
7.2.2 Thermoluminescent Dosimeters 7.2.2.1 A number of thermoluminescent dosimeters are available for use by visitors who will be entering radiation areas.
7.2.2.2 Assignment of these dosimeters is handled by the Radiation Protection Officer. Exposure records are kept by the Medical Section.
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7.2.3 Pocket Dosimeters Q
7.2.3.1 A number of pocket dosimeters are in possession of the Radiation Detector Section and the R.P.O.
7.2 3 2 These devices are not calibrated and hence are not recognized by the N.R.C.
They may be used but not as substitutes for film badges or thermoluminescent dos ime te rs.
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- 20 Revised 6/15/84
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- 7. 3.1. 6 Plating Room - Area 11 - Figure 5 Smear A-K Alpha and Beta / Gamma
- 7. 3.1. 7 Mounting Room - Area 12 - Figure 6 Smear J & K Alpha and Beta / Gamma Smear L & M Alpha and Beta / Gamma Positions L & M to be done' only upon notification by Section Foreman.
E 7.3.1. 8 Company Van - Ar6a 13 - Figure 7 Smear E & F Alpha and Beta / Gamma i
7.3.1. 9 Company Station Wagon - Area 14 - Figure 8 Smear E & F Alpha and Beta / Gamma
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7.3.1.11 Miscellaneous Floor Areas - Area 16 - Figure 10 A.
Cafeteria Entrance at Main Alsle-B.
Outside Front and Rear Doors of Detector Lab.
C.
Outside Plating Room j
l Smear A-C Alpha and Beta / Gamma t
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1 l Revised 6/15/84
-. -. -. =. -.
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- O 7.3 1.13 in-core Cable Assembly Area - Area 18 -
Smear A-M Alpha and Beta / Gamma i
7 3.1.14 1 & M Polishing Room - Area 19 Figure 118 Smear A-C Alpha and Beta /Gama t
7.3.1.15 i & M Phosphor Clean Room - Area' 20 - Figure llc Smear A-C Alpha and Beta /Gama 1
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7 3.1.16 Star Building - Area 21 - Figure 110 Smear A-D Alpha and Beta /Gama Survey perimeter including outside wall.
O 7.3.1.17 Uranium Electrode Test - Area 22 '- Figure 11E Smear A-G Alpha and Beta / Gamma 4
7 3.1.18 Uranium Electrode Firing - Area 23 - Figure 11F i
Smear A-E Alpha and Beta /Gama l
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AREA 11 PLATING ROOM O
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118 Inside Top Drawer of Safe File 11C.
Outside Top Drawer of Safe File l
11D-11K Floor 1
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Electrode Assembly MIC Sizing 1EC - lEli 18A A
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.18A Vise and adjacent table area 18B Floor under table lac - 101 See Figure llA-2 Figure llA-1 Rev. 5-14-64
AREA 18 In Cable Ass:=bly Area Eloctr Assembly Ares Detail O
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180 G234 Glove Box 18D Ultrasonic Cleaner 18E Tables 1FF Tablea 18G Sink 18H Table ISI U234 Glove Eox 18J' 18K
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AREA 19 i & M POLISHING ROOM
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19A Buffing Wheel 19B Table O
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AREA 20 I&M Phosphor Clean Econs O
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20A Ealsnee table 20B Cat-ccating apparatus
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20D Ealance table j
203 Cat-coating apparatus
- 20F Cat-coating apparatus
- 20G Floor
- 'Jipe hood surface in front of cat-coating apparatus.
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-34D-Revised 7-11-84
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Area 21 Star Building O
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Area 22 Uranium Electrode Test (Plating Room) l l
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Scalers Pulse Generator Amplifier 22F Lead p
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i22A 22A Table Top 228 Lead Pig 22C Pre-Amp & Test Container 22D u Ammeter & Lambda Power Supply 22E Scope (Front) 22F Scalers, Generators, Ampli fiers, ND 2400 (Front) 22G Floor Figure llE O
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AFIA 23 UP.AFIUli 312.CTECDS FIFITG (IF-CCRE DETECTCP. LAL)
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23C 25 23D 23E 23A Ttble Top 233 Exhaust Syste:2 Tsble Top 23C he-Icn Power Supply Contrels.
23D Furnsee Centrols 23E Floor (couposite of ceveral spots) i t
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8.3 9 DISPOSAL SHEET FOR SCRAPPING U 235 WESTINGHOUSE PROCEDURE 203-8-70 TO:
T. Patterson, Accountability REPRESENTATIVE DATE:
PLEASE NOTE: This tube / material to be sent to the Radioactive Materials Storage Vault / Uranium Plating Room /other.
The following information must be filled out prior to securing apprevil to scrap.
Scrap U235 QUANTITY Tube Serial Rumber (s) n EACH TOTAL Q'
Gross Weight Net Weight Tare Weight "U" Weight Origin of Material Scrapped Person Scrapping Accountability Approval T. Patterson, Acet. Rep.
SNN - 182 NOTE:
00 NOT SCRAP OR MOVE WITHOUT SIGNATURE OF ACCT. REPRESENTATIVE.
I DATE SCRAPPED i
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Revised 6/15/84
ET 2600 R1 O
O Form ET 2600 MARKING, LABELING AND DOCUMENTATION OF PACKAGED RADIOACTIVE PRODUCT DATE TUBE irrc SERIAL NO.
DEVICE ON CONTACT MR/HR.
DEVICE AT 4 INCHES MR/HR.
PACKAGE AT CONTACT MR/HR.
PACKAGE AT 3 FEET MR/HR.
ISOTOPE ACTIVITY uCI
~ REPORTED BY R.P.O.
SIG.
DATE REVIEVED BY PACKAGING SIG.
DATE REVIEWEU B'Y TRAFFIC SIG.
DATE 1
TRANSPORTATION HAZARDS CHECK ONE:
H.P.
ELEMENT:
PS I A:
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R. C. Carstens Packaging Dept. Revised 6/15/84
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O 235'234 11 2., 3 O_234 O
"c,2'5 TYPE U038
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MG/cM2 2
2 g cg c3 CM pCi uCi ISOTOPIC 3514 2
0.34 1070 0.36 0.9C 22 3527 2
1.57
' 1070 1.68 4.20 101 O 3586 o2 o t>7 555 o oa7 o 22 52 I
3595 2
1.57 260 0.41 1.0 25 3709 2
1.57
- 1. 7 0.00267 0.007 0.16 '
3721 obsolete 3755 1
0.73 Lo70 0.83 2.1 50 3756 2
1.57 1070 1.68 4.20 101 l
3786 2
1.57 260 0.41 1.0 25 3787 2
0.34 1070 0.36 0.9 22 3806 2
1.57 1180-1.85 4.63 111 3833 2
1.57 2.45 0.00385 0.01 0.23 3871 2
0.34 1180 0.4 1
24 3872 2
0.34 1180 0.4 1
24 3880 2
i 1.57
- 1. 7 0.00267 0.0G7 0.16 3881 2
1.57
- 1. 7.
0.00267 0.0C7 0.16 3884 2
1.57 1070 1.68 4.20 101 3905 2.
1.57
- 1. 7 0.00267 0.007 0.16 3906 2C 1.57
- 1. 7 0.00267 C.CC7 0.16 3916 2
1.57 1.7 0.00267 0.007 0.16 3928 Obsolete 3930 2
1.57 1180 1.85 4.63 111 3931 2
1.57 1070 1.68 4.20 101 3933 2
1.57 268 0.42 1.1
'25 3935 0.2 0.157 1070 0.168 0.42 10.1 3936 0.2 0.157 1070 0.168 0.42 10.1 0 3937 0.2 0.157 1070 0.168 0.42 10.1 3941 L.2 1.57
- 1. 7 0.00267 0.007 0.16 )
3958 2
1.57 1365 2.14 5.35 129 3968 2
1.57 1070 1.68 4.20 101 3996 2
1.57
- 1. 7 0.00267 0.0C 7' O.16 3
4014 2
1.57 1070 1.68 4.20 101 4031 2
1.57
- 1. 7 0.00267 0.007 0.16_
4036 2
1.57 1200 1.88 4.70 113 4093 1
1 0.78 597 0.47 1.2 2E j
4094 0.5 0.39 1070-0.42 1.1 25 4107 2
1.57 1365 2.14 5.35 129 4110 2
1.57 2.45 0.00385 0.01 0.23 4152 2
1.57 2.45 0.00385 0.01 C.23 4162
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2 1.57
- 1. 7 0.00267 0.007 0.16 4173 2
1.57 1070 1.68 4.20 101
-1 4174 1
0.78 1070 0.83 2.1 50 4182 2
1.57 2.45 0.00385 0.01
,0.23 4214 2
1.57 2.45 O.C0385 0.01
- \\0.23 4245A 1
0.78 1070 9.83 2.1
' 50 4314 2
1.57 1070
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- 0. 6 0.47 0.67 1.00032 0.0002 0.02 4336 (U238)
(U235 1ppe) depleted. ma6 t i,t1 4343 (U238)
(U235 10-50 ppa) deplaced material 4344 2
1.57 1070 1.68 4.2C 101'.
O 4359 3
2 1.57 1.32 0.00207 0.C05 0.12 i 4392 2
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1.57 2.45 0.00385 0.01 0.23 4396 2
-1.57 1070 1.68 4.20 101 4414 2
1.57 500 0.786 1.S7 47.1 l
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O -23 9234 U 235 Aree U
U-235 U-234 U038 TYPE Mc/m2 O ece m 2
-cx2 cx uc1 ect ISOTOPIC "
i 4420 2
1.57 1200 1.88 4.70 113 4422 (U238)
(U235 1 ppm)
Depleted Material 2
1.57 1.7 0.00267 0.C07 0.16 O
4423 4475 2
1.57
- 1. 7 0.00267 0.007 0.16 1-4491 2
1.57 5
0.0078 0.02 0.47 4516 2
1.57 1365 2.14 5.35 129 4559 2
1.57
. 1070 1.68 4.20 101 4576 (U138)
(U235 1 ppm)
Depleted Material 4585 2
1,57 1070 1.68 4.20 101 4645 2
1.57 2.6 0.0041 0.01 0.25 4652 2
1.52 1070 1.68 4.20 101 4652A 2
1.52 1070 1,68 4.20 101 4661 2
1.47
- 1. 7 0.0025 0.006 0.15 4676 2
1.57 1070 1.68 4.20 1C1 4677 (U238)
(U235 10-50 ppm) Depleted Material 4690 2
1.57 1070 1.68 4.20 1C1 4706 2
1.57
- 1. 7 0.00267 C.007 0.16 4757 2
1.57 2.45 0.00385 0.01 0.23 4765 2
1.57 1370 2.15 5.3E 129 4766 0.2 0.157 1370 0.215 0.54 12.9 4767 2
1.57 13.6 0.0213 0.05 1.26 4863 2
1.57
- 1. 7 0.00267 0.007 0.16 4925 2
1.57 3.5 0.0055 0.01 0.33 4948 2
1.57
- 1. 7 0.00267 0.007 0.16 5003 2
1.57 1260 1.98 4.95 119 5022 2
0.34 1070 0.36 0.90 22
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5024 Obsolete 5027 (U238)
(U235 25 ppa)
Depleted Material 5030 2
1.57
- 6. 9 0.011 0.03 0.66 5046 1
0.78
- 3. 4 0.00267 0.007 0.16 5406 0.3 0.24 20 0.0048 0.01 0.29 5436 2
1.57 1070 1.68 4.20 101 5449 0.5 0.39 1970 0.42 1.1 25 6376 2
1.57 1070 1.68 4.20 101" 6376A 2
1.57 1070 1.68 4.20 101 6941 2
1.57 2 60 0.41 1.0 25 6941A 2
1,57 260 0.41 1.0 25 6971 2
0.34 1070 0.36 20% 0.14 3.5 6971A 2
0.34 1070 0.36 202 0.14 3.5 g
7186 2
1.57
- 1. 7 0.00267 0.007 0.16 7187 1
0.78 1070 0.83 2.1 50
!1 7188_
0.2 0.157 555 0.087 0.22 5.2 7657 2
1.57 1070 1.68 4.2C 101 i
8073 2
1.57 1070 1.68 4.20 101 23033 2
1.57 1070 1.68 4.20 101 23044 2
1.57
- 1. 7 0.00267 0.007 0.16 23051 2
1.57
- 1. 7 0.00267 C.007 0.16 I
23065 2
1.57 163 0.256 0.64 15.4 23070 2
0.34 1180 0.4 1
24 1
23071 2
1.57 1370 2.15 5.38 129
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23072 2
1.57 500 0.786 1.97 47.2 l
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Revised 6/15/84
-235/23a U-235 U-234 2 Q U-235 Arga TYPE U038 2
Mc/CM m
GM
_uCi uCi Mc/m ISOTOPIC 23073 0.3 0.24 20 0.0048 0.01 C.29 23074 2
1.57 1070 1.68 4.20 101 05 o 39 1070 0 42 11 25 0
23075 23076 (U238)
(U235 200 ppm) Depleted Material 23077 2
1.57 1070 1.68 4.20 101 23088 2
1.57
- 2. 6 0.0041 0.01 0.25 23089 1
0.78 3.5 0.00273 0.0C7 0.16 23090 2
1.57 2.45 0.00385 0.Cl 0.23 23091 2
1.57 2.45 0.00385 0.01 0.23 23092 2
1.57 2.45 0.00385 0.01 0.23 23093 2
1.57
- 1. 7 0.00267 0.CC7 C.16 23094 0.5 0.39 0.034 0.000013 0.CCCO3 C. Col 23110 2
1.57 265 0.416 1.04 25.3 21 50 23149 1
0.78 1070 0.83 2.1 51 23150 2
1.57 535 0.84 23170 (U238)
(U235 25 ppa)
Depleted Material 23172 0.2 0.16
- 1. 7 0.00027 0.001 0.02 23195 2
1.57 3.5
- 0.0055 0.01 0.33 23202 2
1.57 2.6 0.0041 0.01 0.25 23234 2
1.57 10.5 0.0165 0.04 0.99 23238 2
1.57
- 2. 6 0.0041 0.01 0.25 23254 2
1.57
- 1. 7 0.0027 0.01 0.16 23261 2
1.57 3.5 0.0055 0.C1 C.33 23266 2
1.57
- 2. 6 0.0041 C.Cl G.25 23284 2
1.57 0.89 0.0014 0.CC4 0.C8 23287 2
1.57 3.5 0.0055 C.01 C.33 0
23292 2
t.57 0.07 0.00011 0 coC3 o ol 23430 0.35 0.275 646 0.178 C.45 10.7 23432 0.3 0.235 240 0.0565 C.14 3.39 23434 (U238)
(U235 200 ppa)
Depleted Material 23435 2
1.57
- 2. 6 0.0041 C.01 C.25 23436 2
1.57
- 1. 0 0.0016 C.C04 C.1C 23442 2
1.57 1700 2.67 6.68'160 23448 2
1.57 0.8 0.00125 C.CO3 C.C8 23465 2
1.57
- 2. 6 0.0041
" Cl C.25
, 23466 2
1.57 13.0 0.02 0.C5 1
23467 2
1.57 13.0 0.02 0.05 1
l 23468,
2 1.57 13.0 0.02 0.05 1
23470 2
1.57 2320 3.64 9.10 218 23477 0.05 0.39 1070 0.417 1.C4 25.1 l
23478 1
0.78 163 0.128 0.32 7.68 23485 1
0.78 3.2
.0025 0.CC6 C,15 23489 1
0.78 3.5 2.73 6.83 164 i
23604 2
1.57 1070 1.68 4.2C 101 23610 0.5 0.39 2.1 0.00082 C.CO2 0.05 l
i 23612 2
1.57 1070 1.68 4.20 101 23621 0.5 0.39 2.1 0.00082 C.CC2 0.C5 1
23622 0.5 0.39 3.5 0.00136 0.003 U.c8 23623 0.5 0.39 2.6 0.001 C.CO3 0.C6 3.5 1.36 3.4C 81.6 23625
- 0. 5 0.39 O
23630 2
1.57 2.6 0.0041 0.01 0.25 23637 0.5 0.39 8.4 0.00328 0.008 0.2C 23639 (U238)
(U235 10 ppa) Depleted Material 23640 (U234)
Depleted in U-235
- 95B -
Revised 6/15/84
^
- l 235/234 C-235 U-234 U-235 Area U038 2
MG/CM g
GM uCi uC i__
TYPE 2
2 MG/04 ISOTOPIC 23642 2
1.57 3.5 0.0055 0.C1 0.33 2
1.57 2.6 0.0041 C.01 0.25 O 23643 23644 (U238)
(U235 20 ppm) Depleted Material 4.20 1C1 23650 2
1.57 1070 1.68 l
23651 2
1.57 1070 1.68 4.20 101 23652 2
1.57 1070 1.68 4.20 1C1 23653
- 0. 5 0.39 2.1 0.00082 0.CO2 C.Cf 4.20 101 l
23660 2
1.57 1070 1.68 4 20 101 23669 2
1.57 1070 1.68 0.03 0.7:
23670 2
1.57
- 7. 6 0.012 0.05 1.1 l 23671 2
1.57 11.6 0.018 4.20 1C1 23684 2
1.57 1070 1.68 23698 2
1.57 1070 1.68 4.20 101 23700 (U238)
(U235 20 ppa) Depleted Material 23718 0.5 0.39 10.5 0.0041 0.01 C.2:
l 23723 2
1.57 1370 2.15 5.38 129 23724 2
1.57
- 2. 6 0.0041 0.01 0.2-23733 1
0.78 990
.772 1.93 46.3 23734 019 0.70 515 0.36 0.90 22 23735 2
1.57 1070 1.68 4.20 1C1 23757 2
1.57 1070 1.68 4.20 101 23767(23786) 2 1.57 1070 1.68 4.20 101 l
23771 2
1.57 1070 1.68 4.20 101 23777 0.5 0.39 180 0.070 0.18 4.2 j
23789 2
1.57
- 3. 5 0.0055 0.01 C.3 23790 2
1.57
- 2. 6 0.0041 0.01 C.2 23792
- 0. 5 0.39 10.4 0.004 0.01 0.2 23798 0.5 0.39
- 2. 6 0.001 0.003 0.C 23814
- 0. 5 0.39 8.4 0.0033 0.008 0.2 23816 0.5 0.39 10.4 0.004 0.01 0.2 i
23830
- 1. 0 1.0 1138 1.14 2.85 68.4 23831 2.0 2.0 1138 2.28 5.70 137 23885 2.0 1.57 0.85 0.0013 0.003 C.C i
23928*
2.0 1.57 0.85
.002 0.CC5 C.2 23936
.5
.39 10.4
.004 0.01 C.;
i 23952
- 2. 0 1.57 2300 3.62 9.05 217 1
23953
- 2. 0 1.57 1070
- 1. 6'8 4.20 101 2.0 1.57 1070 1.68 4.20 101 23957 2.0 1.57
- 1. 7
.0027 0.CC7 C.:
23954 23958
- 2. 0 1.57
- 1. 7
.0027 0.007 C.:
23983 2.0 1.57
- 1. 7
.00267 0.CC7 0.:
23992 2.0 1.57 1787 2.806 7.C2 168 23993 2.0 1.57-1370 2.15 5.38 129 23994 2.0 1.57 1787 2.806 7.02 16E 24000 2.0 5
1070
.42-1.1 25 24004 2.0
- 2. 0 1138 2.28 5.70 137 24008
.5
.39
- 2. 6
.001 0.003
- c. !
24018
.5
.39 10.4
.004 0.C1 C.
.5
.39 10.4
.004 0.01 C.
24025
.55
.55 1205
.66 1.7 40 Q
24019 24027
.074
.00053
.135
. 072(Natural Uranium) 24028 1.
.9 1.71
.00154 C.C04 C.
1.98 gas 0.50 119 24036 contains 3 24025 24052 0.5 0.39
- 2. 6 0.001 0.003 C.
24053
- 0. 5 0.39
- 2. 6 0.001 0.CO3 C. I N
R 1.57 1070deplaced 1.68 11 ppa U-235
/
vuuwxs I
E O
O Area U-235/2?4 r-235 C-2: 4 U-235 U038
' TY PE MG/CM2 MG/CM2 2
g GM uCi uCi ISOTOPIC 24080 1.35 0.14
- 2. 8 0.0004 C.001 C.c 2 O
24081 1.35 0.14 11.2 0.0016 C.004 0.10 24086 0.0016 C.004 C.1C 24117 Same as 24086 24120*
- 2. 0
.258
.446 1.12 26.8 24200*
.0027 0.007 C.16 24201*
.66 1.7 40 24202*
1.98 4.95 119 30045 2
1.57
- 1. 7 0.00267 0.0c7 0.16 30055 2
1.57 61 0.096 0.24 5.8 30084 1
0.78 3.5 0.00273 C.CC7 C.16 30224 2
1.57 1.7 0.00267 C.C07 0.16 30301 (U238)
(U235 200 ppa) Depleted Material 30303 2
1.57 1070 1.68 4.2C 1C1 30501 2
1.57 -
0.61 0.00096 0.002 0.06 30548 0.35 0.275 646 0.178 C.45 1C.7 30549 (U238)
(U235 loppa)
Depleted Material 30572 2
1.57 68.5 0.108 0.27 6.48 30573 2
1.57 3.5 0.0055 0.01 0.33 30574 (U238)
(U235200 ppa)
Depleted Material 30585 (U238)
(U235 loppa)
Depleted Material 30588 2
1.57 3.5 0.0055 0.01 0.33 30604 2
1.57 1.7 0.00267 0.007 0.16 30606 2
1.57 3.5 0.0055 0.01 0.33 30609 2-1.57 2.8 0.0044 0.01 0.26 0
30612 2
1.57 3.5 0.0041 C.01 C.25 30626 2
1.57 3.5 0.0055 0.01 0.33 30627 2
1.57 3.5 0.0055 0.01 0.33 30655 2
1.57 13.1 0.0206 0.05 1.24 30656 2
1.57 13.1 0.0206 0.05 1.24 30665 2
1.57
- 1. 7 0.00267 0.007 0.16 30666 2
1.57 153 0.24 C.60 14 30673 2
1.57 50 0.0785 0.20 4.71 30683 2
1.57 1070 1.68 4.20 101 30689 2
0.34 1.75 0.0006 0.002 0.04 30711 2
1.57 1070 1.68 4.20 1C1 30713 2
1.57 5.1 0.008 0.02 0.5 3.5 0.0055 0.C1 0.33 30715 2
1.57
. Depleted Material 30727 (U238)
(U235 loppe) 30728 (U238)
(U235 loppa)
Depleted Material 30748 (U238)
(U235 2 ppa)
Depleted Material 30758 2
1.57 1070 1.68 4.20 101 30760 2
1.57 1070 1.68 4.20 101 30797 2
1.57 1.0 0.0016 0.004 C.10 30817 2
1.57 20 0.0314 0.08 1.92 30820 2
1.57 1070 1.68 4.20 101 30863 2
1.57 2.6' O.0041 C.01 0.25 30868 2
1.57 0.8 0.00125 0.003 0.0E 2
1.57
- 0. 64 0.001 0.003 0.1 O.
30869-30881 2
1.57 2.6 0.0041 0.01 0.25 30883 2
1.57 2.6 0.0041
'0.01 C.25 30904 2
1.57 1.0 0.0016 C.004 0.1C 30933 2
1.57 3.5 0.0055 0.01 0.33 30942 2
1.57 3.5 0.0055 0.01 0.33 30944 2
1.57
- 7. 8 0.0123 C.03 0.74 m
O235'2x t-us u-a O u-235 MG/Q(2 MG/CM2 2
U038 P.
TYPE CM GM uC1 uCi
~
ISOTOPIC 30960 2
1.57 1070 1.68 4.2C 1C1 2
1.57 1070 1.68 4.20 101 l
p 30961 I
v 30964 (U238)
(U235 10 ppm) Depleted Material 30965 (U238)
(U235 10 ppm) Depleted Material 30969 2
1.57 8.8 0.0138 0.03 0.83 30970 2
1.57
- 8. 8 0.0138 0.C3 0.83 30971 2
1,57 8.8 0.0138 0.03 0.83 30977 2
1.57 1.9 0.003 0.006 0.2 30980 (U238)
(U235 10 ppm)
Depleted Material 30981 (U238)
(U235 loppa)
Depleted Material 30988 2
1.57 3.5 0.0055 0.01 0.33
'31002 2
1.57 0.0083 0.000013 0.00CC3 C.001 31093 2
1.57 3.86 6.06 15.2 364 j'
31095 1
0.78 1070 0.83 2.1 50 j
31100 2
1.57 535 0.84 2.1 50 31152
- 0. 3 0.234 10.9 0.00255 0.006 0.15 31168 (U238)
(U235 25 ppm)
Depleted Material 31169 0.3 0.234 12.5 0.00293 C.CC7 0.1B 31183 (U238)
(U235 6 ppa)
Depleted Material 1
31234 2
1.57
- 3. 5 0.0055 0.01 0.33 31246 2
1.57
- 2. 6 0.0041 0.01 0.25 j
31261 2
1.57 10.5 0.0165 0.04 0.99 j
31291 0.01 0.0078 3.5 0.000027 0.00007 0.002 l
31293 1
0.78 15.3 0.012 0.03 0.72 j
31335 0.2 0.16 1.7 0.00027 0.C007 C.02 (U238)
(U235 10 ppa) Depleted Material 0 31354 31356 (U238)
(U235 10 ppa) Depleted Material 31369*
2 1.57 2300 3.36 8.40 202 i
31384*
2 1.57 2300 3.36 8.40 202 31417
- 0. 8 0.625 200 0.125 0.'31 7.50 l 31418 0.24 0.187 208 0.039 0.10 2.3 31419 2
1.57 14 0.022 0.06 1.3 31424 2
1.57 14 0.000027 0.C0C07 0.00; i 31434 2
1.57 3.5 0.0055 0.01 0.33 l 1
31438 2
1.57 3.5 0.0055 0.01 C.33 l 31440 2
1.57
- 7. 6 0.012 0.03 C 72 31441 2
1.57
- 7. 6 0 012 0.03 0.72 31442 2
1.57 2.6 0.0041 0.01 0.25 31456 (U238)
(U235 loppe)
Depleted Material
'31458 (U238)
(U235 loppe)
Depleted Material 31463 2
1.57 32 0.050 0.13 30 31465 2
1.57 3.5 0.0055 C.01 0.33 31471 2
1.57
- 7. 6 0.012 0.03 0.72 31474 2
1.57 2.6 0.0041 0.01 0.25 31479 (U238)
'(U235 2ppe)
Depleted Material 31480 (U238)
(U235 2 ppe)
Depleted Material 31491 2
0.34 1.9 0.00065 0.002 0.04 31493 2
1.57
- 1. 9 0.003 0.008 0.2 l
31496
.2 1.57 1.9 0.003 C.00E C.2 2
1.57 3.5 0.0055 0.C1 0.33 Q
31517 31543 2
1.57 1300 2.05 5.12 123 31546 2
1.57 153 0.24 0.60 14 31552 2
1.57 1.9 0.003 0.008 0.2 31553 0.5 0.39 8.4 0.0033 0.0C8 0.2C l
- 95E -
Revised 6/15/84
-235 Arme U
3/234 U-235 U-234 U038 TYPE MC/m2 MC/cM2 g2 CM uci uci j
ISOTOPIC 31554 2
1.57 0.07 0.00011 0.0003 0.01 2
t 57 to7o t 68 t 2c tot 01563 31568 2
1.57 525 0.825 2.06 50 31573 2
0.34 19 0.00065 0.002 C.c4 31574 2
0.34 1.9 0.00065 0.002 0.04 31575 2
0.34 1.9 0.00065 0.0C2 C.04 11576 2
0.34 1.9 0.00065 0.002 0.04 31578 2
0.34 1.9 0.00065 0.CO2 0.04 31579 2
0.34 1.9 0.00065 0.C02 0.04 31640 1
0.78 36.5 0.0285 0.07 1.71 31656 0.5 0.39 180 0.070 0.18 4.2 31671
. (U238)
(U235 20 ppm)
Depleted Material 31687 (U238)
(U235 50 ppm)
Depleted Material 31721 2
1.57 2.6 0.0041 0.01 0.25 31749 2
1.57 1880 2.95 7.38 177 31756 2
1.57 26 0.041 0.10 2.5 31771 0.5 0.39 180 0.070 0.18 4.2 31772 0.5 0.39 180 0.070 0.18 4.2 31790 2
1.57 1070 1.68 4.20 101 31830 1
0.78 1070 0.83 2.1 50 31875 2
1.57 3.5 0.0055 0.01 0.33 31942 0.2 0.157 163 0.0256 0.C6 1 54 31943 2
1.57 2.46 0.00385 0.01 0.23 31964 2
1.57 2.46 -
0.00385 0.01 0.23 32172 2
1.57 163 0.256
.0.64 15 4 32173 0.1 0.078 2.1 0.00016 0.0004 0.01 32174 2
1.57 3.5 0.0055 0.01 0.33 32253 0.5 0.39 2s1 0.00082 0.002 0.05 32254 0.5 0.39 2.6 0.001 0.002 0.06-32296 2.0 1.57 2.6 0.0041 0.01 0.25 32435 0.5 0.39 6.3 0.0025 0.006 0.15 32436 0.5 0.39 8.4 0.004 0.01 0.2 32476 2.
1.57 1.8 0.0028 0.007 0.17 32479 2
1.57 1370 2.15 5.4 129 32496 2
1.57
~2. 6 0.0041 0.01 0.25 32530 2
1.57 0.78
.00135 0.003 C.08 32581 1
0.78 170 0.133 0.33 7.98-32716 2
1.57 1.078
.00135 0.003 0.08 32720 (U238) 32816 2
1.57 1070 1.68 4.20 101 l
32905 2
1.57 2.45 0.00385 0.01 0.23 33057
.770
.607 2.47
.150 0.37 9.0 33059
.770
.607 2.47
.150 0.37 90 33073 2
1.57 1.7
.0027 0.007 0.16 33100 2
1.57 1.7
.00269 0.007 0.16 33346 2
1.57 1070 1.68 4.20 101 33412 2
.84 1070
.90 2.2 54 33714 2
1.57 1.7
.0027 0.007 0.16
.225
.2 23
.0046 0.C1
'O.28 l
Cs33779
.0016 0.004 0.10 33904
- 95F -
Revised 6/15/84
-c
- ~ -
r a~.
~
1 wa..
.x.~
- +.. -
12.4.4 Tube Uranium-depicte d Tube Uranium-depicted i
Type Grams uCi Type Grams uCi 10 WL-22826 18.68 9.34 1
22907 18.68 9.34 23076 1.68 0.84 VX-30727 0.00273 0.0014 23170 0.00267 0.0013 30748 1.68 0.84 23434 0.0041 0.0020 30943 0.00273 0.0014.
23639 0.0004 0.0002 30964 0.00137 0.0007 !
23640 0.0004 0.0002 30965 0.00546 0.0027 ;
l 23644 0.00082 0.0004 30980 0.00137 0.0@7 i
23700 0.0041 0.002 30981 0.00546 0.0027 WX-4336 0.00267 0.0013 31168 0.00267 0.0013 1
4343 1.68 0.84 31183 0.136 0.068 4
4422 0.00267 0.0013 31354 0.00273 0.0014 l
4576 0.00267 0.0013 31356 0.234 0.117 4677 1.68 0.84 31456 0.00273 0.0013 ;
5027 0.00267 0.0013 31458 0.008 0.004 30301 1.68 0.84 31479 0.00137 0.0007 30549 1.14 0.57 31480 0.00546 0.0027 i
30574 0.00273 0.0014 31671 0.00267 0.0013 i
30585 0.00273 0.0014 31687 0.00065 0.0003 j
L 36077 18.68 9.34 i
O Tuse Taorium-tur i Tuse Taertum-aaturei Type Grams uCi Type Grams uCi L 759 O.53 0.17 lus 0.2 uCi Kr 85 l
4712 0.ho373 0.0008 WL-23263 0.0204 0.0045 f
7676 0.00373 0.0008 23264 0.0204 0.0045 l 7903 0.00186 0.0004 23265 0.0204 0.0045 l 22754 0.0204 0.0045 23747 0.00186 0.0004 !
23782 0.00186 0.0004 22868 0.0204 0.0045 WX-30874 0.00373 0.0@s 22869 0.0204 0.0045 31186 0.0204 0.0045 )
31542 0.00186 0.0004 I 22923 0.00186 0.0004 31854 0.00373 00%8 22947 0.0204 0.0045 L 36072 12.5 2.75 22948 0.0204 0.0045 22949 0.0204 0.0045 1
23027 12.5 2.75 i
23028 12.5 2.75 i
Miscellaneous Tube i
Tzpe
- O
=
0.3 uoi x, 85 L 23761 100 uCi C 14 i
l i Revised 6/15/84
O O
Radioactive Shipping Labels O
oa Figure 18 Radioactive White - I
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[
Coset NTs........................
ACTtvlrY.........................
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":"'; i RADIOACTI'/E II e. _.,,
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rnanyonris.o o O Revised 6/iS/84-
O O
l 14.
PHYSICAL EXAMINATIONS FOR PERS_0NS.__W0JKING WIT _H.
k ig lZING RADIATION AND RADl0 ACTIVE y TERIALS 14.1 Prospective Radiatio, Workers i
14.1.1 A preplacement general physical examination.
14.1.2 A preplacement complete blood examination.
14.1 3 Abnormal results shall prevent employment with lonizing radiation or use of radioactive materials.
i 54.2 Persons Working with X-rays and Sealed Radioactive Materials 14.2.1 Radiographers and radiographer's assistants will I
be given a general physical examination and a complete blood examination on a 12 month schedule.
14.2.2 All others will be given the above examinations only O
j if their film badges show exposure greater than 500 mR/ year.
14.3 Persons Working With Unsealed Radioactive, Material 14.3.1 A general physical examination on a 12 month schedule.
14.3 2 A complete blood examination on a 12 month schedule.
14.3.3 For those working with uranium prior to encapsulation, urine samples shall be analyzed for total uranium on a 6 month schedule. The W action level is 25 dpm/ liter.
4 O
i
- 100 -
Revised 6/15/84
O O
14.3.h For those working with thorium or thoria prior to encapsulation, urine samples shall be analyzed for thorium on a 6 month schedule.
The E action level Is 0.2 dpm/11ter.
4 14.3.5 Those involved in the operation of the CINO2 fill system shall be required to have an urinalysis for gross f -K40 at the time of each new production run but no more frequently than once each year.
The sample should be taken no later than five days af ter l
the last usage. The y action level is 2200 dpm/ liter.
I 14.4 All of the above' sampling and testing shall be the responsibill ty of the Medical Department on a routine basis except 14.2 and 14.3.5.
It shall be the responsibility of the Radiation Protection Officer to alert the Medical Department when that testing should be scheduled.
I 1 O i.
- l
- 101 -
I
^
- 15. FIRE N TROL INVOLVING RADI0 ACTIVE "
- IALS 15.1 Westinghouse fire department and security personnel shall be informed of the hazards in fighting a fire involving radioactive material and shall be shown the locations of appreciable quantities of radioactive material in the plant, see Fig. 21.
15.2 Should municipal fire departments be called to the plant to
' assist in fire fighting, they will operate under the direction of Westinghouse fire department and/or security personnel in areas where appreciable quantities of radioactive materials are present, see Fig. 21.
15.3 In the event of a fire involving radioactive material or in a radiation area, tha Radiation Protection Officer shall be notified immediately.
15.4 The presence of flanunable materials shall be kept to a minimum in areas where radioactive materials are used or stored.
15.5 Fire Extinguishing Agents 15.5.1 Adequate and readily available fire extinguishing agents shall be provided in areas where appreciable quantities of radioactive materials are present, see Fig. 21.
O 15.5.2 escause pressurized extinguisners may spread contamination ey blowing radioactive material around, the preferred material is G-1 powder, M75131AA, spread over the fire from a hand scoop.
A container of powder will be provided in each of the areas shown in Fig. 21.
15.5.3 The second choice of fire extinguishing agents would be CO
- 2 In this case the extinguisher should be used in a mann u that will not blow any radioactive material around. Direct it at the fire with the nozzle at least three feet away. A CO2 extinguisher will be kept in proximity to each of the areas shown in Fig. 21 except the radioactive materials storage vault.
)
15.5.4 00 not use a high pressure water stream.
If water has to be used, it should be only as a fine spray or mist.
Even so, it should be used only sparingly so as to reduce the spread of contamination by water running over the floor.
15.6 Miscellaneous 15.6.1 Do not hesitate to remove an injured person from the burning O-area.
15.6.2 Do not enter radioactive area without good reason.
15.6.3 Self-contained breathing apparatus shall be worn when fighting a fire in any of the areas shown in Fig. 21.
RED
- 102 -
Revised 1/26/84
,f %
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(
LEGEND
'o l
8 A.
Pu-be Source in Detector lab.
M L.
U-235 in Uraniuu Plating Room C.
Co-60 Source in Gamma Test Room" L,
D.
Pu-be Sources in Neutron Test lioom i
E.
}{ise, in Radioactive 14at'Is Storage Vault g
F.
Am-Be Source in Wire Line Lab
_j
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16.
RADIOACTIVE MATERIAL CONTROL 3(V 16.1 The New York State and Nuclear Regulatory Commission licenses held by the Industrial and Government Tube Division authorize us to possess the radionucildes IIsted in the IIcenses.
In addltion, the IIcenses are quite specific stating the total amount of each Isotope we are allowed to possess at any one time. The RPO must know at all times the total amount of each Isotope on hand.
In order to accomplish this, the following program shall be followed:
16.2 The Purchasing Section shall forward to the RPO packing slips for all radioactive materials received.
The radioactive materials involved are as follows:
16.2.1 Argon gas containing Krypton-85.
OV 16.2.2 Nitrogen - Helium gas mixture with carbon - 14 in the form of carbon dioxide (CINO )-
2 16.2.3 Thorium Nitrate and Thorium Oxide.
16.2.4 Thorium metal.
16.2.5-Natural and Depleted Uranium.
16.2.6 Enriched Uranium.
(U234 and U235)
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Revised 6/15/84
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O 19 REPORTS AND REGISTRATIONS 19 1 Certain reports to the regulatory agencies must be made on a recurring basis and are as follows:
19.1.1 HEW Annual Report (21CFR,Section 1002.11) on High Voltage Recti fier Tubes.
Due: August 31.
19.1.2 HEW Annual Report (21CFR,Section 1002.11) on High Voltage Switches.
Due:
Currently exempt from filing.
19 1.3 HEW Annual Report (21CFR,Section 1002.10 and 1002.12) on
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l & M Cathode Ray Tubes.
Due: August 31.
19 1.4 NRC Radioisotope Useage Report (10CFR 32.16, re: NRC License 31-13372-ole).
Due: Within 30 days af ter 5 years after filing previous report, or within 30 days after filing for renewal of license.
19.2 Certain registrations to the regulatory agencies must be made on a one-time or when-change-is-made basis and are as follows:
19 2.1 Certain generally licensed items must be registered with the NYS Dept. of Labor.
See Code Rule 38.4.
19 2.2 Radiation producing equipment must be registered with the NYS Dept. of Labor.
See Code Rule 38.4 19 2 3 Lasers must be registered with the NYS Dept. of Labor.
See Code Rule 50.8.
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Revised 6/15/84
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19 REPORTS AND REGISTRATIONS (CONT'D) 19 3 Miscellaneous Reports 19 3 1 Visitor doseage reports from TLD badges.
Send report to individual on Form NRC 5 upon receipt of results from laboratory.
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- 112A -
1 a.
f SE1WEth: William D. Migr. Chief O-License Fee mat.agement Branch Office of Administration John E. Glenn, Chief Nuc1 car Materials Section B Division of Engineering and Technical Programs LICENSE FEE TRANSMITTAL
_\\ ee Necc\\ec A.
REGION s
1.
APPLICATION ATTACHED f
Applicant / Licensee: k 7$hnnhou% Elerdric CorotrTLMon J
Application Dated:
6 f n f Si5 fj/L 7 9
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Control No.:
License No.:
WN, rn- \\ M Q i
2 FEE ATTACHED Amount:
0 Check No.:
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COMMENTS Signed k clnnnjo 9]NI~,.k 7 Date 5f'h/99 y///
B.
LICENSE FEE MANAGEMENT BRANCH j [?
1.
Fee Category and Amount:
Ik - bh) 2.
Correct Fee Paid.
Application muy be processed for:
Amendment
/
Renewal License R$6IL_aw signed
/
'l/WC/l'J" Date
/
/
REGION I FORM 213 (MARCH 1983)