ML20141F450
| ML20141F450 | |
| Person / Time | |
|---|---|
| Site: | 07000124 |
| Issue date: | 01/24/1997 |
| From: | Raymond Gibson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| References | |
| 123957, NUDOCS 9707020393 | |
| Download: ML20141F450 (115) | |
Text
p m , a w a o o s < n se m g q w_ m a w g g e e g g y g g q 97 ,9 p y _
h"gf " , , , U.S. NUCLEAR REGULATORY COMMISSION PAGE - OF 3 eacts '
MATERIAL.S 1.ICENSE Amendment No. 05 i[
i Pursuant to the Atomic linergy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public 1.aw 93 438), and Title 10 I Federal Regulations. Chapter I, Parts
- 30. 31,32,33. 34,35,36,39. 40, and 70, and in reliance on statements and representations heretofore made l J by the licensee, a heense is hereby iwued authoriting the hcensee to receise, acquire. pmsess, and transfer byproduct.
y material designated behm: to use such material for the purposetn) and at the place (s) designated below; lo deiner or transfer such material to p persons authorized to receive it in accordance with the regulanons of the applicame Part(s). This license shall be deemed g%Nuclear specified ReFulatory in Section Commiwion now or183 ofin the hereafter Atomic effect and Energy to any conditions Act specified of 1954. as amended. and isj sub below.
OFFICIAL RECORD COPY b 'I'* " *" '
In accordance with the letter dated 3 November 27, 1996, Sj L Teledyne Environmeni.al, Inc. 3. License Number SNM-107 is amended in Sj dba Teledyne Brown Engineering - its entirety to read as follows:
II Environmental Services
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j 50 VanBuren Avenue A Expiration Date November 30, 2003 Bj P.O. Box 1235 I9 Westwood, New Jersey 07675 5. D r$No. 070-00124
~
g 6. Bypnxtuct. Source, and/or 7. Chemical and/or Physical Special Nuclear Material 8. Maximum Amount that Licensee g Form May Possess at Any One lime -
g Under This License .
3 5 A. Uranium 232 A. Any A. 5.0 micrograms E 5 8. Uranium 233 B. Any B. 1.0 gram (l 5 C. Uranium 235 C. Any C. 240.0 grams (I 3 D. Plutonium 236 D. Any D. 5.0 micrograms (!
9 E. Plutonium 238 E. Any E. 6.0 milligrams El 9 F. Plutonium 239 F. Any F. 10.5 grams (!
9 G. Plutonium 240 G. Any G. 100.0 milligrams H. Any
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$ H. Plutonium 241 H. 100.0 milligrams (!
9 1. Plutonium 242 I. Any I. 50.0 milligrams r.l
$ J. Plutonium 244 J. Any J. 200.0 milligrams I l 5 K. Any Special Nuclear K. Any K. 1.0 gram L.j!
a Material h { i 3 9. Authorized use Q.
$ Gj g A. through K. Research and development as defined in 10 CFR Part 70.4; sample analysis; $l 9 calibration of instruments and dosimeters for clients; reference samples in Ql g tracer studies; and for possession as recovered from decontamination Q g processes on precious metals. R a
E CONDIfl0NS h
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C 10. Licensed material may be used only at the licensee's facilities located at $
50 Van Buren Avenue, Westwood, New Jersey ar.d Degussa Corporation facility at 3601 Q
j$ South Clinton Avenue, Plainfield, New Jersej.
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pl 11. Licensed material shall be used by, or under the supervision of, individuals A. 1,3 p designated in writing by the Radiation Safety Committe9. The licensee shall Gj s maintain records of individuals designated as users for three years after;the I Li last use of licensed material by the individual. ,
I, The Radiation Safety Officer for this license is Steven A. Black. [
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guLMLN.Br.ptw w w w w_m_w w w m_g_w_w w ww w w w w w w w w w w w w w w w w w w w w w w w w w FORM 374A U,_S. NUCLEAR REIULATORY COMMISSION g , , PAGE 2 OF 3 PAGES gl Lrense Nuniber g g' .
p SNM-107 g' N MATERIALS LICENSE Docket or Reference Number g
( S'JPPLEMENTARY SHEET 070-00124 g N E g Amendment No. 05 g n E l N "
g 12. A. Sealed sources and detector cells containing licensed material shall be tested for leakage and/o'r contamination at intervals not to exceed six months or at i s
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such other intervals as are specified by the certificate of registration s l referred to in 10 CFR 32.210, not to exceed three years. j l
! B. Notwithstanding Paragraph A of this Condition, sealed sources designed to emit !
2 alpha particles shall be tested for leakage and/or contamination at intervals not to exceed three months.
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E C. In the absence of a certificate from a transferor indicating that a leak test E g
has been made within six months prior to the transfer, a sealed source or g 5
E detector cell received from another person shall not be put into use until tested.
l 8 E
$ D. Each sealed source fabricated by the licensee shall be inspected and tested l 4 for construction defects, leakage, and contamination prior to any use or -
! transfer as a sealed source. E s E E. Sealed sources and detector cells need not be leak tested if:
s (i) they contain only hydrogen-3; or n
N (ii) they contain only a. radioactive gas; or E s E
( (iii) the half-life of the isotope is 30 days or lass; or E R E
$ (iv) they contain not more than 100 microcuries of beta and/or gamma emitting E y material or not more than 10 microcuries of alpha emitting material; or E N E y (v) they are not designed to emit alpha particles,.are in storage, and are E W not being used. However, when they are removed from storage for use or E g transfer to another person, and have not been tested within the required E y leak test interval,-they shall be tested before use or transfer. No E g sealed source or detector cell shall be stored for a period of more than E g 10 years without being tested for leakage and/or contamination. E R E s F. The test shall be capable of detecting the presence of 0.005 microcurie of E y radioactive material on the test sample. If the test reveals the presence of E g 0.005 inicrocurie or more of removable contamination, a report shall be filed E q with the U.S. Nuclear Regulatory Commission and the source or detector cell E y shall be removed immediately from service and decontaminated, repaired, or E a disposed of in accordance with Commission regulations. The report shall be s filed withi'i five days of the date the leak test result is known with tl.; $gl g U.S. Nuclear Regulatory Commission, Region I, ATTN: Chief, Nuclear Materials El y Safety Branch, 475 Allendale Road, King of Prussia, Pennsylvania 19406. The El g report shall specify the source or detector cell involved, the test results, g!
g and corrective action taken. Records of leak test results shall be kept in El y units of microcuries and shall be maintained for inspection by the Commission. El gi Records may be disposed of following Commission inspection. Ej W Ei n E W E \.
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NR FORM 374A U.S. NUCLEAR REcVLATORY COMMISSION PAGE 3 OF 3 PAGES g
, License Number g j
( SNM-107 E i
g MATERIALS LICENSE Docket or Reference Number (
( SUPPLEMENTARY SHEET 070-00124 E N E l
Amendment No. 05 E ;
q E G. The licensee is authorized to collect leak test samples for analysis by the g 1 licensee. Alterriatively, tests for leakage and/or contamination may be y l performed by persons specifically licensed by the Commission or an Agreement g j State to perform such services. y j f 13. The licensee shall conduct a physical inventory every six months to account for all g sealed sources and devices containing licensed material received and possessed under lg )
y the license.
g , j 5
- 14. The licensee is authorized to transport licensed material in accordance with the provisions of 10 CFR 71, " Packaging and Transportation of Radioactive Material."
l 5l l k5 15. Except as specifically provided otherwise in this license, the licensee shall N conduct its program in accordance with the statements, representations, and E
! procedures contained in the documents, including any enclosures, listed below. The E Nuclear Regulatory Commission's regulations shall govern unless the statements, E representations, and procedures in the lic.ensee's application and correspondence are mcc restrictive than the regulations.
j N A. Application dated June 30, 1992 E B B. Letter dated September 22, 1993 E B C. Letter dated November 27, 1996 E 9 D. Letter dated January 17, 1997 E N
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g For the U.S. Nuclear Regulatory Commission M
l Date M 24 W By Original Signed By-Richard Gibson
{f gl g Nuclear Materials Safety Branch E;
, Region I j 4 King of Prussia, Pennsylvania 19406 Wi gj g i mKWm~KMXMMMMERMEM*****T*EEEE"E3"""NEER"""""""""
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1 JAN 2.41997 4
- Eugene O'Brien, Assistant Secretary
- . Teledyne Environmental, Inc.
j Teledyne Brown Engineering-
- Environmental Services 50 Van Buren Avenue
- Westwood, NJ 07675-1235 9
Dear Mr. O'Brien:
1
- This refers to your license amendment request. Enclosed with this letter is the
- amended license. Please note that as part of this amendment, in accordance with 1 10 CFR 30.36, effective February 15,1996, the expiration date of your license has
! been extended by a period of five years. Your new expiration date is stated in item 4 i
of the license.
Please review the enclosed document carefully and be sure that you understand and fully implement all the conditions incorporated into the amended license. If there are any errors or questions, please notify the U.S. Nuclear Regulatory Commission, Region i Office, Licensing Assistance Team, (610) 337-5093 or 5239, so that we can provide !
appropriate corrections and answers. j Thank you for your cooperation.
. i Sincerely, Oripnal Signed By:
- Richard Gibson, Jr.
Division of Nuclear Materials Safety
- ~ License No. SNM-107 Docket No. 070-00124 Control No. 123957
Enclosure:
I Amendment No. 05 i
OFFICIAL RECORD COPY ML 10 i
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s DOCUMENT NAME: R:\WPS\MLTR\LSNM107.LTR TO receive a copy Of thle document, indcate in the box: "C' = Copy w/o attach /enel *E' = Copy w/ attach /enct *N* = No copy OFFICE DNMS/RI lN DNMS/RI l l l NAME RGibson/rxg A DATE 01/24/97 01/ /97 01/ /97 01/ /97 OFFICIAL RECORD COPY
. IAtl-24-1997 14:53 FROM TBE EtblPOItENTAL TO 916103375393 P.01
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i bbbk@ @ k @ $1b rlb $ E 7k @ @ $ hbbaoo To: Richahd Gibson i Company: U.S. NRC !
FAX' No: 601-337-5393 l l :
From: TELEDYNE ENVIRONMENTAL, Inc.
Radiological Services Department i 50 Van Buren Avenue Westwood, NJ 07675 :
Main Telephone Number: 201-664-7070 i I i Fax Nismber: 201-664 6921 Date: January 24, 1997 j Sender: Steve l Black Phono / Ext.: 201 664-7070 x225 l i
Richard, .'
I have made changes l in the manual to reflect your the concerns in your fax of 1/23/97. Please review them ' and let j me know if thay're j0K.
Call me when you gt a chance.
l If the changes are OK, please let me know so I can get a hard copy to you vi,a1 US Mail. j l
Thanks... ,
I stove Black i !
Total Sheets,irmfuding this coversheet: $ I, if you do not receive the above nu of pages, please contact the sender identified above. !
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123957
, OFFICIAL RECORD COPY ML 10 , ;JAN 2 4 997
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. Jft!-24-icr37 14:53 FPCt1 TBE EtOIPONMEllTAL TO 916103375393 P n2 l
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I Instructions for Updating RSC&QCM v5.0 to v5.01 (* Revised 1/24/9k) l l
Replace The' following Pages: l i
Cover Pa'ges ,
Authorization & Approval Page Revision Control Form l toc Pages il and iii toc Page v
- Page II-2 ;
i Page II-5 Page II-12 Page II-20 .
i Page III/4-2* l Page III/4-12 In Section II Fonus:
Page 2 of Form IWL RW-231 l Diagram I - Degussa Corporation j i
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i l Section 111/4 -1 4 ' j Section III Forms after Page III/4-14* !
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i Ifd l44-1997 14:54 FPOM T M EtlUIPOt#1FilT OI. TO 916103375393 P.03 1
Radiation Safety Code & T TELEDYNE i ,
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BROWN ENGINEERING Quality Coritrol Manual Environmental Services Table of Contents (C'.ndnued) l l
SECTION 111 SI'ECIAL PROCLL)l RLS 1OR PREClOUS METALS DECONTAMIN ATION l
,, U.S. NRC License No. 29 000U 15 i j , Page No.
i 111-4.1 Introduction. . .. .. . . .. . . . . . .. . 111 / 4 -1 i
III 4.2 Facilities & Equipment. . .. . . . . . . . . . . . . . ... ..III/4-1 l
111-4.3 Training & Retraining.. .. . . . . . . . ...... .
..j.. . ...III/4-2 l
. i j I11 4.4 Radiation Survey Program.... . . .. . . ... .. . . . . .
. ..{.. . ..III/4-2 l 111-4.4.1 Weekly Surveys.... . . . . . . . . . . . .
. .311/4-2 l
) 111-4.4.2 Contamination Limits. . . ..III/4-4 (
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..III/4-5 d
111-4.4.3 Procedure for Exiting the PM Area . . .
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111 4.4.4 Air Monitonng.. .. . . . . . . . ... . .. ., , .. .III/4 -6 111-4.4.5 Respiratory Protection Program.. . ..III/4-7 I
I 111-4.5 Shipments .. .. . . . . . . . . .. ..... ... .111/ 4-8 i
III 4.6 Records Management.. . . ... . . . . . . . . . . . . . . ..111/4-8 I
III4.7 Material Control Provisions. . . . . . . . . . . . . . . . . . . ...III/4-8 III-4.8 Safety Rules. . . . . . ...... . . . . . . . . 111/ 4 9 III-4.9 Waste Management.. . . . . . . . . , ,, . . , . ...III/4-11 111-4.1 0 Decontamination Guidelines.. .. . . . . . . . .. ..III/4-11 111-4.1 1 I*.otope Possession Limits... . . . . . . ... . . . . . . . . . . . . .. . . . .. .11I/4-12 III 4.12 Disposal to the Sanitary Sewer.. . . . . . . . . .. .. . . ..III/4-13 i
111-4.1 3 Transfer of Material from TBE-ES to Degussa.. . .
. 3. . .111/4-13 111 4.14 Release of Processed Material.. . . . . . . .... ,. . . ..111/4-13 111-4.15 Secunty... .. . . . . . . ... . . . . . . . . . . . . . . . . ... . .. ...' . .111/4-14 III 4.16 Contractual Arrans:ements., . . . .111/4-14 SECTION 111/4 FORMS i
January 26,1997 Page v Version 5.01
- mil-24-1997 14:54 FPOf1 TFE ENVIPOtI1EllTAL TO 916103375393 P 04 j
Radiation Safety Code & 'PPTELEDVNE . !
Quah.ty Control Manual - BROWN ENGINEERING l Environmental Services !
l The ceramic vacuum filters are over-sized "buchner" funnels, about 2 feet in diameter, and are used to filter and collect various purified metals during the last step of the process. The collected metals are then j washed, dried and fired to a stoichiometric sponge form.
The furnace used to melt the alloy n the beginning of the process is called a " speedy-melt" It is a floor-mounted gas fired furnace in which the crucible resides. From past experience, this crucible is the only piece of equipment on which any activity has ever been detected. For this reason, this crucible is designated for this work only and will be bagged and scaled when not in use.
In addition to the Health Physics equipment liped in Section II, a Ludlum Model 2929 alph'a/ beta counter (or comparable instrument) will be kept in the office area of the Degussa racility and will be used to count smears. j 11143 Training and Retraining All employees working under thi.s license are required to attend the Basic Radiation Safety course as outlined in Section 11-1.2 " Indoctrination of Personnel". TBE-ES employees are required to have an additional 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of supervised on-the-job training. Employees at the Degussa facility are not required to habe any additional training due to thh limited quantities they will have on hand. All specific wntteri procedures and health and safety factors are to be learned to the supervisor's satisfaction. The items of health and safety are listed in Sections 111-4.4,4.8 and 4.9. An annual refresher course will be given to all employees working under i this license. Documentation will be kept in each person's Health Physics file. ,
All employees who work under this license are required to read this section of the, Radiation Safety Code & Quality Control Manual, and are tested on their knowledge using Form IWI,PM-02, "29-00055-15 Licensed Activities Exam".
117 4 4 Radiation Surtwy Program The radiation safety program is, in general, that found in Sections 11-5.0,11-6.0 and 11-7.0. The following is a further description of the procedures to be performed for this license.
4.4.1 Weekly Surveys i Radiation contamination surveys of the Buffer Zone and Precious Metals lab at TDE-ES are performed weekly. Surveys include monitoring for surface contamination on all laboratory bench tops, chairs, tables, sinks, floors, exposed portions of hoods and glove boxes, and Sencral laboratory equipment. Surveys of the Degussa
~ facility will be performed on a quarterly frequency. An Eberline Instrument PAC-4G or PAC-4G3 gas proportional survey instrument is used to measure direct surface contamination.
General radiation levels in the rooms are measured with an Eberline Instrument E-120 GM counter with end window probe or comparable instrument. Smear surveys for removable surface contamination are taken Vernon 5.01 January 24,1997 Page 111/4-2 t
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,, JAt1-24-1997 14:55 FROM TBE EtPJlPOtIIEtITAl. TO 916103375393 P.05
- , j Radiation
- Safety Code!& W TELEDYNE! !
Quahty Con: trol Manual r
BROWN ENGINEERING .
Environmental Services 111-4.1 5 Security i
The TBE-ES Precious Metals decontamination laboratory can only be ntered by authorized p sonnel using a magnetic card key . The laboratory has a safe where all materials not in process are stored. In addition, a motion detection security system is installed that alarms off-site to a central btation.
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The Degussa facility is a precious metals processing facility that pro' cesses much bore than just the limited amount of contaminated metal we will be sending there. As such, they!are very secusty conscidus and have armed guards at every door, metal detectors for personnel leaving the facility, an x-ray inspection jsystem for packages and briefcases, a video / motion detection security system, and! two large walk-in vaul'ts. The lead / precious metal button will be stored in one of these vaults when not being processed. !
! i 111-4.1 6 Contractual Arrangements l \
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TBE ES and the Degussa Corporation will enter into a Contract and/or Purchase Order whbe the following items will be addressed: ; ! i i l
- 1. Authorization of Degussa personnel to work with licensed material will be made by the kBE-ES Radiation Safety Committee. l l
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- 2. Degussa Corporation agrees to abide by all the applicable constraints, conditions, requirements, I
commitments and representations identified in TBE-ES' U.S. NRC License Nos. 294005515 and SNM-107.
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- 3. Degussa Corporation will agree to notify TBE ES of changes fit personnel that are either a) assigned to radiation safety matters or, b) authorized as a radioactive materials user. ;
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- 123957' Version 5.01 Jmuary 24,1997 Page 111/4-14 l i
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OFFICIAL RECORD COPY ML 10
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TELEPHONE CONVERSATON RECORD Date: 1/23/97 Time: 3:30 4
p.m.
Mail Control No.: 123956 & 123957 License No.: Docket No.:
29-00055-15 & 030-14482 SNM-107 070-00124 Person Called: Steven Black, RSO Organization: Telephone Teledyne Number:
Environmental Inc. 201-664-7070 Person Calling: Richard Gibson Jr.
Subject:
Licensing action / amend license to add the Degussa Corporation facility to the license.
Summary: I informed Mr. Black that in order for me to continue witti the amendment request, I will need additional information.
- The correction for the Manual Table of Contents for Section III was not submitted with the correspondence dated January 17,1997. Submit correction.
- Your manual did not state how you will secure from unauthorized removal or access licensed materials that are stored in controlled or unrestricted areas at the Degussa facility. In addition, control and maintain constant surveillance of licensed material not in storage in a controlled or unrestricted.
- Describe fully the agreement between the personnel at the Degussa Corporation facility and Teledyne Environmental Inc., having control over licensed activities at the Degussa facility. Is there any changes in personnel such as authorized users responsible for radiation safety of use of licensed j material? A complete, clear description of the agreement and that the l personnel at the Degussa facility agree to abide by all constraints, conditions, requirements, commitments and representations identified in the license.
Action Required /Taken: Faxed information to Region I Signature: Richard Gibson, Jr. h Date: 1/23/97 mmsm em ML 10'
, W TELEDYNE BROWN ENGINEERING January 17,1997 Environmental Services 50 VAN SUMN AVENUE P.O. 80x 1236 WESTWOOO. hilW JEH6EY 0787S1236 Re: License No. SNM-107 en.7aro man u License No. 29 00055-15 gg Docket No. 030-14482 Docket No. 070-0012 < @ 7-Control No. 123956 Control No. 123957 PLEA SE EXPEDITE Mr. John D. Kinneman, Chief U.S. Nuclear Regulatory Commission, Region I Nuclear Materials Safety Branch 2 475 Allendale Road King of Prussia, PA 19406-1415
Dear Mr. Kinneman:
This letter is in response to your letter as cited above dated January 11, 1997. We have referenced our response with respect to your numbered items.
Item 1: Decomm issioning Plan We wish to confirm hat there was no decontamination performed prior to the final release survey and we intend to run the operation at the Degussa facility as before. I have added $5,000 (plus 10% contingency) to our Decommissioning Cost Estimate to cover any possible decommissioning costs for the Degussa facility. See the enclosed revision to Table 6 of our Decommissioning Cost Estimate.
Item 2: Radiation Safety Code & Quality Control Manual Corrections a) I have corrected the page numbers in the Table of Contents of the RSC&QCM.
i b) The Degussa facility where the radioactive materials will be used is located at 3601 (Building D) South Clinton Avenue, Plainfield, NJ. I have corrected the RSC&QCM to reflect this. There is a Degussa office located ar 3900 South Clinton Avenue, Plainfield, NJ, but for the purposes of this license only the 3601 l address wii! he used.
{
1 c) Section 11-1.3.1 incorrectly referenced 10 CFR 201203. The correct reference is 10 CFR Part 20.2203.
I have corrected the RSC&QCM to reDect this.
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W TELEDYNE January 17,1997 BROWN ENGINEERING :
g ggg Mr. John D. Kinneman U.S. Nuclear Regulatory Commission l
1 Page 2 i
d) Section II-5.0 incorrectly referenced 10 CFR Subpart C - Occupational Dose Limits. The correct i
reference is 10 CFR Part 20 Subpart C - Occupational Dose Limits. I have corrected the RSC&QCM to reflect this.
l c) The spelling of the word " scintillation" has been corrected in Item 11 of the Packaging of Radioactive i Waste Exam.
f) Section 111-4.2 incorrectly states that the diagram of the Degussa facility is in the Forms Section of Section Ill. It is actually located as the last form in the Forms Section following Section IL I have revised the diagram to include the cross-hatching and changed the reference in 111-4.2.
Item 3: Quarterly Radiation Protection Guide Values l Section II-2.2 and 11-2.4 " Radiation Protection Guide Values": These references should have been to the current 10 CFR Part 20 limits found in Appendix B, Table 1. I have corrected the RSC&QCM to reflect this.
If the information provided herein is satisfactory, please process the amendment as soon as possible. We would appreciate an advanced copy by FAX (201-664-6921 Attn: S. Black) so that we can continue negotiations with the U.S. DOE to provide them with this specialized service in the very near future.
Thank you for your assistance in expediting the processing of this request. It is greatly appreciated.
If you have any questions, please call me or Mr. Steven Black, RSO at the above phone number.
Sincerely, TELED 'NE ENVIRO ' 1 ENTAL Inc.
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/f/
Eu ene O'Brien, Assistant Secretary cc: Donald F. Schutz, Chairman RSC Steven A. Black, RSO
Attachment F Dec;mmissioning Cost Estimate TABLE 6 Y,_d.J. 3$'
7 FeimitiNedw: .
TELED NE BROWN EN5 9*
Summary of Costs
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- Er m 9 Cost Planning and Preparation Labor- Table 1 $26,275.20 Decontam] Dismantling Labor - Table 3 $24,724.00 Equipment - Table 4 $5,000.00 Radioactive Waste Disposal- Table S $574,210.47 Degussa Decommissioning Survey $5.000.00 Sub-Total $635,209.67 Contingency factor (10%) 563,520.97 GRAND TOTAL DECOMMISSIONING COSTS l $698.730.63 l t
1/17/97 Decommissioning Funding Plan
W TELEDYNE BROWN ENGINEERING Environmental Services Instructions for Updating RSC&QCM v5.0 to v5.01 f
Replace The following Pages:
Cover Pages Authorization & Approval Page Revision Control Form
~
toc Pages ii and iii Page11-2 Page II-5 Page II-12 l Page 1I-20 Page III/4-12 In Section II Forms:
Page 2 of Form IWL-RW-231 Diagram I - Degussa Corporation 1
Insert the following Pages: ,
Section III Forms after Page 111/4-13 l a
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! Radiation Safety Code Quality Control Manual j
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R diati:n Saf ty Cod 2 & TTELElWNE
'. Quah.ty Contre.' Manual ! 'ROWN ENTilNEERIN3 o
Environmental Services l Authorization & Approval Page The Radiation Safety Code & Quality Control Manual defined herein has been approved by the Management of Teledyne Brown Engineering -
Environmental Services. This program manual defines the employer and employee's responsibilities to protect the environment and to provide a safe working environment for all employees.
l Radiation Safety Officer:
Nn A. Black General Manager (Chairman of Radiation Safety Committee): / M- "
Donald F./chutz S
Please note: Paragraphs marked with a vertical line on the right margin have been revised as of the date shown either in the margin or the bot +am of the page. If there is no date next to the vertical line, all changes are of the date in the footer.
Version 5.01 January 17,1997
Radiati " Safe'Y Cods & TTELEDYNE BRD,WN ENGINEERIND Quality Contr:1 Manual Environmental Services Revision Control Form '
Issue & Date Affected Effective Prepared By Approv By Revisions issued Pages Date 5.0 11/26/ % All 11 /26/ % Steven A. Black
[ g .
5.01 1/17/97 TOC,11-2,5,12 1/17/97 Steven A. Black
[ ,v.
l Version 5.01 january 17,1997 l l
Radiation Safety Code & W TELEDVNE Quah.ty Control Manual BROWN ENGINEERING i Environmental Services l 1
Table of Contents (Continued) ,
$1 C I ION 11 - GI NI R Al l'ROCl.l)URil5 i OR ( ON I Rol 1 IN(. K AI)l()Al iIVI '
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\1 \ II RITI s ANI) R Al)I \ l H )N I \l'OsL R1 %
i Page No.
11 1.0 INDOCTRINATION OF PERSONNEL EXPOSED TO I O N I Z I N G R A D I ATI O N .... ................................................ ............................ .......... 11 1 1.1 Company Policy on Matters Involving Radiation Exposure... .... . . . . . . . . . . . . . . . . .11-1 1.2 Indoctrination & Training of Personnel.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . .11-1 1.3 Rights and Responsibilities of Radiation Workers and the Company Regarding NRC Licensed Activities.. . .. . . ... .. . . . . . . . .. . . . .11-2
- 1.3.1 Exposure History.... .. . . .... . . . . . . . . . . . . . . . . . . . . . ...... .. . . . . . . . . . . . . . . . . . .!! 2 1.3.2 Notification of Violations During Inspection.. .... . . . . . . . . . . .11-2 j 1.3.3 Notice of Violations, Adverse Conditions, or Potential Violations or Conditions Prior to an Inspection.. . . . . . . . . . . . . . . . . . . . . ..11 3 1.3.4 Procedure for Reporting Violations and/or Potential Violations. . .. . . ..11-3 1.3.5 Requirement for Posting NRC " Notice of Violations" . .. . 11 4 4
j i i1-2.0 1 M EDI CA L EXAMI N ATION S AN D EM E RG ENCI ES ........... ........................ .........................II-5
- 2.1 Pre-Employment Medical Examination.. . . .. .. . . . . .11-5 i 2.2 Follow-Up Medical Examination.. .. ... . .11-5 1 2.3 Termination Medical Examination.. . . . . . . . . . . . . . ..11-5 2.4 Accidents Involving Radiation. .. . . . . . . . . . . . . . . . . . . . . . . . . .. ... .. .....II-5 2.5 Emergencies and Decontamination of Equipment.. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..II-6
. 2.6 Fire. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . ....11-6 l 2.7 Secu rity.. ... .... .... . . . . . .. .. .. . . . . . . . .
..........................................11-6 1
- II-3.0 LA B O RATO R Y PRACTI CES ... . .. .. . . .. . . . . .. . . .. . . .. . .. . . .. . .. . . . .... . . ... ..... ... . .. ... . .. .. . .. . .... .. .... .. .. . .... . . ..
3.1 Personnel Directives.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11-7 l 3.2 Minor Spills.. . . . .. . . . . . . . . . .. . .. ...!!-8 3.3 Major Spills. . . .. . . . . . . . . . . . . . . . . . . . 11-8 3.4 List of Persons to CallIn Radiation Emergency. . . .. .. .. .. .. . . . . ... .11-9 3.5 Contamination Control Directives. . .. . . . . . . . . . . . . . . . . . . . . . . . . . ... ..11-10 11 4.0 ORDER, TRANSFER, RECEIPT AND SHIPMENT OF RAD. MATERIALS. . .. ..1111 4.1 O rd e r.. . .. . . .. .. .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . .. . . . . . . . . . . .II 11
. 4.2 Transfer.. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .... . ..11-11 4.3 Receipt. .. . . . . . .. . . . . . ... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .II- 1 1 4.4 Shipment.. .. . .. .. . . . . . . . . . . .. . ..... . . . . . . . . . . . . . . . . . .II- 1 1 II 5.0 P E RS O N N E L M O NITO RI N G . ... . . .. . .. . . .. . . . . . . . . .. . .. . . . .. .. .. . . . . . .. . . . . ... ... . .. . ... . . .. . .. . .. . ... . .... ..... .. .... 11 12 5.1 External Dosimetry... . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . 11 - 12 5.2 Internal Dosimetry.... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 - 13 11 6.0 SURVEYS...........................................................................................................................II14 6.1 Area Surveys . . . . . . ... . . . .. . .. ... . . . . . . . . . . . . . . . . . . . . . . 11-14 6.2 Decontamination... . . . . . . . . . . . . . . . . . . . . . . . . . . . ..II-14 6.3 Survey Review... .. . . . . . .. . . . . .. . . .. ..II 15 5
I Version 5.01 January 17.1997 Page ii
I Radictirn Safity Cod: & T TELEDVNE Quality Contr:1 Manual ! ROWN ENEINEERING Environmental Services Table of Contents (Continued)
Page No.
II.7.0 IN STR UM ENT CALI B RATI ON ............... ................................ ........
7.1 Genera 1.................................................................................................................I 7.2
...............................II-16 Gamma Calibration .. ................ .. .. . . . . . . . . . . . . . . . . . . . ......................... ...!!-16 7.3 Be ta C a lib ra tion....... . .... .. . . . ..... .. . ... . . .
7A
...................................................II16 A 1 p ha Ca lib ra tion..... .. .. . .... . . .. . . . . .. .. . ...... . .. . ... ........
.............................II-16 7.S Frequency of Calibration... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
...II-16 7.6 Standards.. ...... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................................!!-16 II 8.0 RADIO ACTIVE WASTE PACAAGING AND DISPOSAL......................................................II-17 8.1 Safe Packaging of Radioactive Material - Training and Retraining l
.. .. . . ..11-17 8.2 Classification of Radioactive Waste to be Packaged for Shipment. . ... . .... . . . . . . . . . ...11-18 8.3 Packaging Procedures for Radioactive Waste... . . .. . .. . . . . . . . . . . . .. . . . . . .... .11 18 8.4 Radioactive Waste Interim Storage Plan.. .. . . . . . . ... .. . .. .. 11-1 9 Il 9.0 F A C 1 L I TI E S & E Q U 1 P M E N T.... . .. ....................... ..... . . ..... ....... ..... .. ... ... .. ... .. ..... .. ..... ..
Il-10.0 I NTE R STATE O P ERATI ON S .... ........... ..... .... . ... ... .. . . . . .. . . . . . .. . . ... . . . ... . . . . . . ... ... . . ... .
Licensing Officials in Agreement States..... .... ..... .. . . . ... . . . . . . . . . . . . . . . . . . . . .. . . . .. . . II-21 4
SECTION II FORMS l
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Radisti:n Saf;ty Cody & TTELEtWNE Qualtty Control Manual t ROWN ENEINEERING l Environmental Services i
Form IWL-HP-06 is given to the supervisor of the employee who then fills in the section requesting authorization for the employee. This form is sent to the Radiation Safety Officer who will determine what additional training or monitoring is required for the employee to begin work utilizing radioacti/e materials. If an employee's job function changes where new procedures involving radiation or radioactive materials occur, the supervisor is responsible for preparing a revised Form IWL-HP-06 and submitting it to the RSO for approval. No new job functions are allowed until this approval is obtained.
Persons who through their work attitudes and habits show a disregard for safe operating procedures with radioactive material are recommended for transfer out of radiation work or, if such alternative work is not available, may be terminated from employment.
Il-1.3 Rights and Responsibilities of Radiation Workers and the Company Regarding NRC Licensed Activities 1.3.1 Exposure History All personnel staning work with radioactive materials at TBE-ES are required to supply thetr supervisor and the Health Physics Office as complete a radiation exposure history as available. '
Each new employee will also have their estimated current year's exposure entered into their exposure file. Pursuant to 10 CFR Part 19.13(c), a worker may request his/her exposure history from a previous licensed employer. I Pursuant to 10 CFR Part 19.13(b), a worker may request, and each licensee (company) shall furnish annually, the radiation exposure that the worker has received.
When the company (licensee) is required pursuant to 10 CFR Part 20.2203 to report to the NRC an exposure of an individual to radiation or radioactive material, the company (licensee) must also report to the individual.
l 1.3.2 Notification of Violations During Inspections Pursuant to 10 CFR Part 19.14(b) the NRC inspector may consult privately with workers conceming matters of occupational radiation protection and other matters as deemed necessary by the inspector. During the course of these consultations, any worker may bring privately to the attention of the inspector, either orally or in writing, any past or present condition which he has reason to believe may have contributed to or caused any violation of the act, the regulations of 10 CFR Parts 19,20, and 21, or license condition, or any unnecessary exposure of any individual to radiation from licensed radioactive material under the licensee's control.
Venion 5.01 January 17,1997 Page 112
- Radicti n Saft*Y Cod & TMLE[NNE Quality Control Manual F:HOWN ENGINEERING Environmental Services ll-2.0 MI;I)lCAI l~\ A MIN A IlONS ANI)i Mi RGl'NCil$ '
, l 112.1 Pre Employment Medical Examination New company personnel who will be exposed to, or potentially exposed to ionizing radiation may be l required to submit to a medical examination at the discretion of the company Radiation Safety Officer or the Company Health Physicist. 'Ihe results of this examination become a part of each person's pre-employment i record and is kept on file in the Persor nel Department.
1 11-2.2 Follow-Lip Medical Examination Routine medical examinations are not presently required for those persons who are working with ionizing radiation due to the low permissible limits and excellent detection methods now available fo. external and internal radiation protection. At present, physical methods of detection of radiation are much more sensitive than signs or symptoms of deleterious biological effects identifiable in a routine medical examination.
However, if a person receives an exposure in any one quarter in excess of the limits specified in Appendix B, Table 1, of 10 CFR Part 20 but less than twice the limit, he may be required to take a medical examination at the discretion of the company Radiation Safety Officer or Company Health Physicist. If the exposure is in excess of twice the limit, a medical examination is mandatory. l 11 2.3 Termination Medical Examination Persons who are leaving the employment of the company may be required to submit to a medical examination as directed by the Company Health Physicist or Radiation Safety Officer. A radiobioassay examination is required for all personnel having worked with ionizing radiation.
11-2.4 Accidents involving Radiation Every incident involving exposure of company personnel to radiation in excess of the limits specified in Appendix B, Table 1, of 10 CFR Part 20, is classified as an accident and a report of the accident must be made to the Radiation Safety Committee by the Radiation Safety Officer. An accident involving exposure of company personnel to more than twice the limit must be immediately reported to the Radiation Safety Committee and General Manager of the Westwood, NJ facility at the earliest practical date on its findings.
Every incident involving contamination of equipment and requiring disposal or decontamination in excess of $100 or 1 man-day cleanup time must be investigated by the Radiation Safety Officer and a report made to tl e Radiation Safety Committee. Incidents with equipment losses in excess of $1,000 or S man-days for decontaraination must be investigated by an Investigating Subcommittee appointed by the Radiation Safety Commi tee.
Version 5.01 January 17,1997 PageII5
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- Radiati:n Safe 7 Cod & F:ROWN ENGINEERING
_ Quality Control Manual Environmental Services 11h.0 l'l RSONNI I N1()NiIORING .,
Intemal and external personnel monitoring will be in accordance with 10 CFR Part 20 Subpart C - Occupational Dose Limits.
115.1 External Dosimetry Every employee of, and visitor to, TBE-ES laboratories and plants must wear personnel monitoring devices such as TLD badges and/or pocket dosimeters if their work or tour involves entry to radiologically controlled areas containing sources of penetrating radiation.
Radiologically controlled areas are defined as specified by Part 20 of Title 10 of the Code of Federal Regulations and consist of the following areas: ;
Environmental Analysis -
Provisions of NRC License #29-00055-06 Standard Solutu Storage Room Laboratory Room 614A -
Trovisions of NRC License #SNM-107
'4 Metals Processing & -
Provisions of NRC Licenses #29-00055-15 &
Nuclear Fuels #SNM-107 Laboratory ,
Source Room -
Provisions of NRC Licenses #29-00055-06 Warehouse - Provisions of NRC License #29-00055-14 and NJ License #10123 A list of those persons monitored by TLD badges is maintained by the Health Physics Office. The TLD badges are read out by TBE-ES Badge Service Department.
TLD whole body badges are changed quarterly. A formal investigation by the RSO will be done whenever a badge receives a dose in excess of ten percent of the applicable limit.
Quality control of TLD dosimetry is set forth in the TLD personnel Badge Service Quality Control Manual (IWL-03420-416) and TLD Badge Service Quality Assurance Manual (IWL-0792-442).
I Version 5.01 January 17,1997 Page 11-12
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- Radiation SafeTCode & T TELE N NE Quality Control Manual CROWN ENGINEERING Environmental Services 11-9.0 I ACil ITil % & I OUIPMI N I' '
Please see the diagrams in the Forms section at the end of this Section. A list of the Health Physics equipment that is available for use can also be found in the Forms section.
l Construction of 103 Woodland Avenue Please refer to the diagram that is included with Section II-Forms " Diagram of Warehouse 103 Woodland Avenue" This building is constructed of cement block walls. There is a flat roof that is covered by sheet rock on the inside. The overhead door is wooden and the other exit / entrance is steel.
Construction of 50 Van Buren Avenue Please refer to the diagrams that are included with Section Il-Forms. This building is constructed of cement block walls. There is a flat roof covered with a synthetic membrane.
- onstruction of the Degussa Facility - 3601 South Clinton Avenue, South Plainfield, NJ l Please refer to the diagrams that are included with Section II-Forms.
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l Version 5.01 January 17,1997 Page 1120
Radiati:n Safe'Y Code & T TELEN NE Quality Control Manual [ 'ROWN ENEINEERIN3 Environmental Services
-l i fil 4.11a Isotope Possession Limits - License 29-000SS-15 i
A. Torpossession and use at S0 Van Buren Avenue, Westwood, NJ:
Element & Mase No. Chemical & Maximum Possession Limits Physical Forms item 6 (a) Any By-Product material item 7 (a) Any item 8 (a) No single nuclide to (Z3-Z83) exceed one millicurie and 25 millicuries total (b) Any Transuranic Isotope (b) Any (b) No single nuclide to (Z93 and higher, excluding exceed one millicurie and plutonium) 25 millicuries total l l
B. Tor possession and use at 3601 South Clinton Avenu:, South Plainfield, NJ: l 1/100th of the limits in the above table.
l fil-4.11b isotope Possession Limits - License SNM-107 (This is a subset of the SNM 107 isotope Possession Limits found in Section 111-3) l Torpossession and use at 3901 South Clinton Avenue, South Plainfield,NJ:
l Element & Mass No. Chemical & Maximum Possession Limits l Physical Forms Item 6 (a) U-235 Item 7 (a) Any item 8 (a) I gram (2.0 x10-3 mci)
(b) Pu-238 (b) Any (b) 0.00006 gram (1.0 x10-2 mci)
(c) Pu-239 (c) Any (c) 0.01 gram (6.0 x10-1 mci)
(d) Any other SNM not (d) Any (d) 0.01 gram detailed above
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< 9. Items in different categories i' be mixed.
- 10. All scintillation vial drums must be lined with a . i 11.
The amount of absorbant added to any scintillation vial drum must be capable of l absorbing the volume ofliquid in the drum. '
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- 12. Liquid Special Nuclear Material has to be before disposal.
II. True at False (1 point each)
I' All drums which have a Radioactice I. II oc III label require security
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seals.
- 2. 400 lbs is the maximum weight a!! owed in a Y-gallon container.
- 3. Class A Stable is a DOT classific. tion.
- 4. _ Two 2-mil liners is an acceptable substitute for a eingle 4-mil liner. i
- 5. The pH range for acceptable ligeids for incineration is 5.0-10.0.
6' Animal carcasses are to be completely surrounded with rock salt and absorbant.
- 7. Cement is an acceptable solidification media.
8' Ra-226 is acceptable at the Washington burial site under certain conditions.
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- 9. Packaging regulations are under the direct control of the NRC only.
10" The burial site's (or processor's) iicense requirements are of paramount consideration when determining how to package a given material.
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Form IWL.RT-231 l
DIAGRAM I Degussa Corporation l
3601 South Clinton Avenue South Plainfield, New Jersey I
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Radiation Safety Code &
Ty[WyENGINEERING guality Control Manual
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%I!C I ION 111 i Ol{ M's 'Q i
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- Allforms referenced in Section 111 follow. Ecrms referenced in Sections I & il each section. ,
1 1
- FORM NUMBER TITLE '
l l IWL-FM-01 PM Radwaste Form i
IWL-FM-02 29-00055-15 Licensed Activities Exam l t
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JAN I I 1997 l
l License Nos. 29-00055-15 SNM 107 Docket Nos, 030-14482 070-00124 Control Nos. 123956 123957 Eugene O'Brien, Assistant Secretary Teledyne Environmental, Inc.
Teledyne Brown Engineering-Environmental Services 50 Van Buren Avenue Westwood, New Jersey. 07675-1235
Dear Mr. O'Brien:
This is in reference to your letter dated November 27,1996 requesting to amend Nuclear Regulatory Commission License Nos. 29-00055-15 and SNM 107. In order to continue our review, we need the following additional information:
- 1. In your letter dated November 27,1996, you stated that a revision to your Decommissioning Funding Plan (DFP), to cover the new facility was not submitted because a survey confirmed the lack of radioactive contamination in your last decommissioning of that facility, in your response to this letter, confirm that the previous facility actually required Do decontamination prior to the final survey and confirm that you plan to operate the facility as before.
Even if no decontamination is likely to be necessary, your DFP must include sufficient funding to dispose of the maximum amount of radioactive waste and other licensed materiallikely to be on hand at any time and to fund a survey adequate to demonstrate that the facility is suitable for release for unrestricted use. Please modify the cost estimate in your Decommissioning Funding Plan so that it includes sufficient funding for these items or provide justification that they can be accomplished for a smallincrease in cost (less than $2,000). You must include all costs, including labor, equipment, overhead and a contingency in the cost estimates.
- 2. Some information in your Radiation Safety Code & Quality Control Manual (RSC
& QCM), version 5.0, dated November 27,1996 appears to be in error. Please provide correct information or provide additional information concerning the following:
1 OFFICIAL RECORD COPY
-~ -- - - . - - . - - - - . . _ . . ~ _- - -.
- l l
l E. O'Brien, Asst. Secretary -
2-Telodyne Environmental Inc.
I
- . a. The Manual Table of Contents incorrectly indicates the page numbers for i parts of Section ll and Section lil (i.e. Section ll-8.0 is not on page ll-18, .
Section ll-9.0 is not on page ll-21, Section lll-4.9 is not on page Ill/410, l and Section 111-4.10 is not on page lil/4-10). l
- b. Your letter lists the address to the Degussa Corporation facility as 3601 South 2nton Avenue, South Plainfield, New Jersey. Section ll-9.0 and I Section lil-4.11(a) and (b) of the manual, list the place of use as 3901 South Clinton Avenue, South Plainfield, New Jersey. Please clarify the j apparent contradiction of the two addresses.
- c. Section ll-1.3.1 of the manual, you referenced 10 CFR Part 20.1203 as i the requirement to report to the NRC an exposure of an individual to radiation or radioactive material, and in addition, a report to the individual. 10 CFR 20.1203 of our regulations requires determination of external dose from airborne radioactive material and it is not a ,
requirement to report to the NRC an exposure of an individual to I radiation or radioactive material. Did you meant to reference 10 CFR 20.22037 Please clarify the correct reference to our regulations.
-1
- d. Section 115.0 of the manual, you stated that internal and external personnel monitoring will be in accordance with 10 CFR Subpart C -
Occupational Dose t.imits. That is an incorrect listing of our regulations.
The correct listing is 10 CFR Part 20 Subpart C - Occupational Dose Limits. Please make the necessary correction in the manual.
- e. In item 11 of the Packaging of Radioactive Waste Exam of the manual, the word " scintillation" is misspelled. Please make the necessary correction.
- f. Section lil-4.2 of the manual, you stated that the area where materialis used under this license is identified on facility diagram (in the Forms Section at the end of this Section) by the cross-hatched area. The manual does not have any Form Section at the end of Section lli that i identify facility diagrams. Please submit the Forms Section for Section lli of the manual.
- 3. Section ll-2.2 and Section 11-2.4 of the manual, you mentioned a quarterly radiation protection guide value. Please ascribed your quarterly radiation protection guide value and tell how does it relate to the limits required by our regulations.
i i
OFFICIAL RECORD COPY W ry w g y e M v =-t- 7 s -ca. r * - -
e l
E. O'Brien, Anst. Secretary Teledyne Environmental Inc.
J -
We will continue our review upon receipt of this information. Please reply in duolicate to my attention at the Region i Office and refer to Mail Control Nos. 123956 and 123957. If you have any technical questions regarding this deficiency letter, please call Richard Gibson, Jr. at (610) 337 5071.
If we do not receive a reply from you within 30 calendar days from the date of this letter, we shall assume that you do not wish to pursue your application.
Sincerely, i
I l
John D. Kinneman, Chief Nuclear Material Safety Branch 2 Division of Nuclear Materials Safety License Nos. 29-00055-15 SNM-107 i Docket Nos, 030 14482 070-00124 Control Nos. 123956 123957
Enclosures:
- 1. 10 CFR Parts 19, 20,21 and 30 a DOCUMENT NAME: R:\WPS\DLTR\L2900055.15 To receive a copy of thle document, bdicate in the boa: 'C' = Copy w/o attach /enct *E' = Copy w/ sttach/enci *N* = No copy OFFICE DNMS/RI _ lN DFMS/3 l/J l NAME RGibson/rxg R) JKeman i DATE 01/08/97 C/1/ $i97 01/ /97 01/ /97 OFFICIAL RECORD COPY
!' T TELEDYNE l November 27,1996 BOMEMERM
. Environmental Services 50 VAN BUREN AvtNVf PO 80x v235 WESTWOOO. NEW AR6EY 07e751235 Nuclear Materials Safety Branch re ee4 7oio fax acu se4 sses U.S. Nuclear Regulatory Commission, Region I o yg ggjg
- 475 Allendale Road King of Prussia, PA 19406-1415 Re
- License No. SNM-107 Amendment License No. 29-00055-15 Amendment
Dear Sir / Madam:
Through 1991 Degussa Corporation and Teledyne had an arrangement 'where Teledyne would perform the gross decontamination of precious metals and then send the material to Degussa for refining. The U.S. DOE contract expired and the Degussa radioactive materials license was terminated because of the expense of maintaining it.
We are in the process of finalizing a contract with the U.S. DOE to start-up this process again but would like to license the Degussa facility under our existing licenses. There are two licenses that are affected because the NRC made us move all the SNM onto one license.
Therefore, Teledyne Environmental Inc. requests that the above licenses be amended as follows:
License SNM 107:
- 1) Add place of use: Degussa Corporation facility at 3601 South Plainfield, NJ. See single page revision to the SNM-107 RSC&QCM (111-3,1 - Introduction).
- 2) Note Licensed Material Restrictions: See RSC&QCM Section 111-4, page 111/4-12.
License 29 00055 15:
- 1) Complete revision of RSC&QCM to incorporate the Degussa Facility. See revised RSC&QCM - Section 111-4.0.
I have also enclosed revisions to sections 1 & II of the RSC&QCM as there have been various changes to them since the -15 license renewal.
I have enclosed two checks in the amounts of $290 and $300 to cover the amendment fees for categones ID and 3P respectively.
It should be noted that we have not submitted a revision tu our Decommissioning Funding Plan to cover the new facility because when we decommissioned it the last time all it took was a survey to confirm the lack of radioactive contamination. If you feel we need to add this minor cost (less than $1000) to the documentation, please notify us and we will comply.
If you have any questions, please call me or Mr. Steven Black, RSO at the above phone number.
Sincerely.
TELEDYNE ENVIRON ENTALInc.
Eu ne O'Brien, Assistant Secretary ec: Donald F. Schutz, Chairman RSC Steven A. Black, RSO 123957 OFFICIAL RECORD COPY ML 10
W TELEDYNE BROWN ENGINEERING ii Environmental Services IIIACTIVITIES 3.0 SPECIAL PROCEDURES FOR NRC LICENSE NO. SNM-107 LICENSED
!!!-3.1 Introduction This section of the Radiation Safety Code & Quality Control Manual covers specific items related to our US NRC License SNM-107. 'Ihe place of use for all materials under this license will be 50 Van 13uren Avenue, Westwood, NJ 07675. In addition, certain small quantities of SNM will be used at the Degussa Corporation facility located at 3G01 South Clinton Avenue, South Plainfield, NJ. Refer to Section 111-4.0 for details. The possession and uses of the special nuclear materials are:
a) The analysis of un-Irradiated enriched uranium for uranium content and isotopic composition by mass spectrometry. Samples are prepared for analysis in the Uranium liexafluoride Laboratory, Uranium-Plutonium Laboratory, and the Low Level Uranium Preparation Laboratory for analysis in the Mass Spectrometry area (see diagrams in Appendix A). All samples are stored either in the Low Level Uranium Preparation Laboratory, the Uranium-Hexafluoride Laboratory or the Uranium-Plutonium Laboratory; b) Use of U-235 as a tracer to determine uranium concentration of geological samples by isotope dilution. Standard solutions of microgram quantities of U-235 are kept in a cabinet in the Low Level Uranium Preparatfor Laboratory; c) The analysis of samples for isotopic content by alpha spectroscopy; d) As contaminants of precious metals sent to Teledyne Isotopes to decontaminate as detailed in our 29-00055 15 license (See Section 111-4.0);
e) Calibration ofinstruments and dosimeters for clients; f) For use in research and development as defined in Section 70.4(J) of 10 CFR Part 70.
111- 3 . 2 Traininc and Re-trainina All employees working under this license are required to attend the Basic Radiation Safety Course as outlined in Section 11-1.2 " Indoctrination of Personnel." Only employees working with greater than 50 milligram quantitles are mandatorily required to have additional training. This additional training consists of more than 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of supervised on-the-job training. All specific procedures and health and safety factors are to be learned to the supervisor's satjsfaction. The items of health and safety are listed in Section !!!-3.8. A refresher course will be given at one year intervals.
The employees are required to read this secticn of he Radiation Safety Code and Quality Control Manual, and will be tested on their knowledge using Form IWlAIP-30, "SNM-107 Licensed ActWilles Exam."
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RSC &OCM 7/92 111 - 3 1 Revised: ///b/b -
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Authorization & Approval Page The Radiation Safety Code & Quality Control Manual defined herein has been approved by the Management of Teledyne Brown Engineering -
Environmental Services. This program manual defines the employer and employee's responsibilities to protect the environment and to provide a safe working environment for all employees.
Radiation Safety Officer:
Yen A. Black
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General Manager (Chairman of Radiation Safety Committee): / _
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< onald [ Schutz '
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Radiati n Saftty Cod: & TTELE[NNE Quality Control Manual BROWN ENGINEERING i
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Revision Control Form Issue & Date Affected Effective Prepared By Approved By Revisions issued Pages Date 5.0 11/26/ % All 11/26/ % Steven A. Black 1
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SECTION I- M AN AGEMENT POLICY AND ORG ANIZATION
- Page No.
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1.0 INTRODUCTION
................................................................................................................I-1 l 1.1 Statement of Basic Policy - ALARA.. .... . . . . . . . . .. .. . .
. .I- 1 1.2 Implementation of Policy. . . . . . . . . . . . . . . . . . . . . . . . . .. ... . . . .. . .I- 1 1.3 Philosophy of Radiation Safety: Risk versus Benefit.. .. ... .. . . . .. . . .. . ..I- 1 i
1 2.0 RA DI ATI O N S AFETY CO MMITFEE ... ......... ..... .. ..... ..... ... ..... .. ... ................. ................. .. . .... . ...I-2 l 2.1 Responsibilities.. .. . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . .. . ..I-2 2.2 Membership & Qualifications.. . . . . . . . .. . . . . .. . . . . . . . . . .. .. . .I -2 2.3 Executive Subcommittee. ... . . . . . . .. . . . . . . . . . . . . ... . .. ..I-3 2.4 Safety Committee... . .
. . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . ..I-3 2.5 Records. .... . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .I-3 2.6 Qualifications of the Company Health Physicist and the Radiation Safety Officer.. . . . . ..I-3 I-3.0 H E A LTH P H Y S I CS O FFI C E . . . . .... . . . . . . .. . .. . . .. . .. . . . . . . . .. . . . . .. . .. . . . . . . . . . . . . .. . . . . . .. . .. . . . . .
3.1 Personnel .... . . . . . . . . . . . . . .
.......................................... ..I-4 3.2 Du ties... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .I -4 3.3 Records . . . . . . . . . . . . .. . . . . . . . . .. . . . . . . .. . . . . . . . . . . . . . . ..I-S 3.4 Reference Material.. . .. .. . . . . . . .. .
. . . . . . . . . . . . . . . . . . . . . . . . . . .......I-6 3.5 Professional Association.. .. . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . .I- 6 1 4.0 PROCEDURE FOR REVISING RADIATION SAFETY CODE AND QUALITY CONTROL MANUAL... . . . . . . . . . . . .. .. .. . . . . . . . . . . . . . . . . . . . . ..I-7 4.1 Writing a Procedure or Producing a Form . ... . .... . . . . . . . . . . . . . . . . . ...............I-7 4.2 Submission and Review. . .
. . . . . . . . . . . . . . . . . . . . .. ...........................I-7 SECTION I FORMS l
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SECTION 11 - GENI RAI PROCEDURES FOR CONTROLLING R ADIOACTIVE M ATERI Al S AND R ADI ATION EXPOSURES Page No.
11 1.0 INDOCTRINATION OF PERSONNEL EXPOSED TO I O N I Z I N G R A D I ATI O N ............................................................. ....... ...... ..... ...............I1 1 1.1 Company Policy on Matters Involving Radiation Exposure.... .. .. . .11-1 1.2 Indoctrination & Training of Personnel.. . . . . . . . . . . . . . . . .. . . . . . . . . . . . ...I1 1 1.3 Rights and Responsibilities of Radiation Workers and the Company Regarding NRC License'd Activities.. .. . . . . . . . . . . ..II-2 1.3.1 Exposure History.. .. . . ....... .. . . . . . . . . .. . ... . . . . . . . . . . . ..II 2 1.3.2 Notification of Violations During Inspection... . . . . . .. . . ..11-2 1.3.3 Notice of Violations, Adverse Conditions, or Potential Violations or Conditions Prior to an Inspection. . . . . . . . . . . . . . . . . ..... .....II-3 1.3.4 Procedure for Reporting Violations and/or Potential Violations. . . . . . . . ................II-3 1.3.5 Requirement for Posting NRC " Notice of Violations" . .. . ..II-4 II 2.0 M EDICAL EXAMINATION S AND EMERG ENCIES ..............................................................II-5 2.1 Pre-Employment Medical Examination.. . . . . . . ......... .. . .... . . . . ...11-5 2.2 Follow-Up Medical Examination... . . .. . . . . . . ... ... . . ..II-5 2.3 Termination Medical Examination... .. . . . . . . . . . . . . . . . . ..II-5 2.4 Accidents Involving Radiation. . .. . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . .II- 5 2.5 Emergencies and Decontamination of Equipment... .. . . . . . . . . . . . . . . . . . . . . . . . . ..II 6 p)
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2.6 2.7 Fire.... . .. . .
Security.. .. . . . . . . . .
. .11-6
. . . . . . . .II-7 H 3.0 LA B O RATO RY PRACTI CES ......... .... . ...... ...... ..... ..... . ..... .. ... ... . ... .. . ... . . ......... . ......... . ... .. ... ... . ...I I-8 3.1 Personnel Directives.... . . . . . . .. . . . . . . . . . . . . .. . .. .. ..II.8 3.2 Minor Spills... . . . . . . . . . . . . . . . . . . . . . . . . . . ... . .. ..... ......II-9 3.3 Major Spills.. .. . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....II-9 3.4 List of Persons to Call In Radiation Emergency. . . .... .
. . . . . . . . . . . . . . . . . . 11 - 10 3.5 Contamination Control Directives . ... .. ..... . . . . . . . . . . . . . . . . . ......................II-11 11-4.0 ORDER, TRANSFER, RECEIPT AND SHIPMENT OF RAD. MATERIALS . . . . . ..II 12 4.1 Ord er..... . . . . . .. .... . . . . .. .. . . . . . . . .. . . . . . .. ... . . . . . ..II-12 4.2 Transfer.. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...II-12 4.3 Receipt. . . . . . . . . . . . . . . . ... . . . . . . . . . . . .. ....II-12 4.4 Shipment.. .. . . . . . . . . . . . . .. .. . .. . . . . .. . . . . . . . . . . . . . . . .I I- 12 II-5.0 PERSO NN EL M O NITO RIN G ............. .... ............... ................. ..... .. . .. .. ... ... ....... .... ....... ..........I1 -13 5.1 External Dosimetry... . . .. . . . . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . .II- 13 5.2 Internal Dosimetry.. .. . . . . . . . . . . . . . .. .. .. .. .. ..II-13 II-6.0 SURVEYS............................................................................................................................II-15 6.1 Area Surveys. .. . . . . . .. . . . . . .. .... . . . . . . . .. . . .. ..II-15 6.2 Decontamination... . . . .. . . . . . . . . . . . . . . . . . . . . . . . ..II-15 6.3 Survey Review. . . . . . . . . . . . . . . . . . . . . . .... . ..II-16 1
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II-7.0 I N STR UM ENT CA LI B RATI O N ....... .............................. ...... ...... ... ......... ... .... ......... .... . . .. ... .. ..I 1 17 !
7.1 C en e ra 1. . . . .. .. . . . . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. . . . . . . . . .. . . ..II-17 7.2 Gamma Calibration . . .. .. .. . . .... . ........ .. . . . . . . .. . . . . . . . . . . . . . . . . . . ... .. ..II-17 ]
j 7.3 Beta Calibration..... . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .II-17 7.4 Alpha Calibration.... ... ... . . .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ..I1-17 7.5 Frequency of Calibration ........ . .. ... . ... . . . .. ....... ... .. . . . .. . . . . . . . . . . . . . . . . . . .. . . . . 11 - 17 7.6 Standards......... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ..!! 17 II 8.0 RADIOACTIVE WASTE PA CKAGING AND DISPOS AL......................................................I1 18 .
8.1 Safe Packaging of Radioactive Material - Training and Retraining . . . . ..II-18
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8.2 Classification of Radioactive Waste to be Packaged for Shipment. .. . . . . . . . . . . . ... .... ..II-19 i 8.3 Packaging Procedures for Radioactive Waste.. . .. . .... ... . .. . . .... . .. . . . . . . . . . . . . . . . . .I I- 19 !
8.4 Radioactive Waste Interim Storage Plan.... . ............ .... ... . . . ..... . . . . . . . . . . . . . . . . . . . . . . . .I 1 2 0 1I 9.0 FA C I L I TI E S & E Q U I PM ENT.............................................................................. ...................I I 21 1
II-10.0 I NTERSTATE O PERATI ON S ......... .... ........ ......... ............................... ........ .... ... ... .... .. ....... .. ..II-22 !
Licensing Officials in Agreement States............ .. . ... ... ... . ... . . ... .......... .. ..... .. . .......II-22 1 SECTION II FORMS r
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Table of Contents (Continued) j l SECrlON 111 SPECI AL l'ROCEDURES FOR PREClOUS METALS DECONTAMINATION 1 i U.S. NRC License No.,29-00055-15 i
Page No.
- 111 4.1 Introduction .. .... .
.. . . . . . . . . . . . . . . . . . . . . . . . . ....III/4 1
] III-4.2 Facilities & Equipment ....... . ..... .... .. .. . . . . . . . . . . . . . . . . . . . . ..III/4-1 j III-4.3 Training & Retraining... . ... .. . . . . . . . . . . . . . .,, .. , ,,ityj4 1 III 4.4 Radiation Survey Program..... . . .. . ... . . . . . . . ... . .. . ..III/4-2 j 111 4.4.1 Weekly Surveys.. ...
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. . . . . . . . . . . . .. ... .. . . . . . . . . . ....III /4-2 j j III 4.4.2 Contamination Limits. .. . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. ....III/4-3 j III-4.4.3 Procedure for Exiting the PM Area . .. .. ..III/4-4 l 111-4 4.4 Air Monitoring..... .. .. . . . . . . . . . . . . . . .
.. . ..III/4-5 4
i 111-4.4.5 Respiratory Protection Program.. . . . . .. .. . . . . ... . ..III/4-6 -
j III-4.5 Shipments . . . . . . . . . . . . . . . . . . . .. . .. . . . ...III/4-6 a
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- III-4.6 Records Management.. .. . .. .. . . . . . . . . . .. ... . . . . . .
.. ... ..III/4-7 1
i III-4.7 Material Control Provisions.... .. . . . . . .. . .. . . . . .... . ....III/4-7 1
4 111 4.8 Safety Rules.. . . .. . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .III / 4 -8 l 111 / 4.8.1 General Safety Rules... . . . . . . . . . ... ..III/4-8 l 111 / 4.8.2 General Safety Instructions for Glove Box Use . . .. .. ...!!I/4-9 3
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] III-4.9 Waste Management.. .. . . .. . . . . . . . . . . . . . . .. .. . ..III/4-10 III-4.10 Decontamination Guidelines... ..... . . . . . .. ... .
.. . .. ... . .111/4-10 i
111-4.1 1 Isotope Possession Limits.. . . . . . . . . . . . . . .. . .. . . . ..III/4-11 l 111-4.1 2 Disposal to the Sanitary Sewer.. . .... . . . . . . . . . . . ... ... . . . . . ..III/4-11 l 1
111-4.1 3 Transfer of Material from TBE-ES to Degussa.... .... . . . . . . . .. . . . . . ...III/4-12 ;
III-4.14 Release of Processed Material. . . . .. . . . . ... . . . . .. . . . . ..III/4-12 SECTION III/4 FORMS Version 5.0 November 27,1996 Page iv I
Radiation Safety Code & TTELEENNE Quality Control Manual BROWN ENGINEERING Environmental Services SECllON I - M AN AGEMLN'I POLICY AND ORG ANIZATION 1-
1.0 INTRODUCTION
in January,1994, Teledyne isotopes had changed its business name to Teledyne Brown Engineering -
Environmental Services (TBE-ES). Although still incorporated as Teledyne isotopes, Inc., all naming references within this document will be to TBE-ES. Subsequently, in 1996, Teledyne isotopes, Inc. was re-incorporated under the name of Teledyne Environmental Inc.. however we continue to use the business name of Teledyne Brown Engineering - Environmental Services and are continuing the use of TBE-ES in this document.
1-1.1 Statement of Basic Policy - ALARA The basic policy underlying this Radiation Safety Code and Quality Control Manual is that the health and safety of personnel working with ionizing radiation and the prevention of any release of radioactive contaminants which could adversely affect the environment are of paramount importance to TBE-ES. All decisions, rules and recommendations will be made with the basic premise that levels of radiation exposure are to be minimized to the lowest level that can be reasonably achieved (ALARA). The Radiation Safety Officer will make recommendations to the Radiation Safety Committee at least annually concerning any changes or modifications of procedures that would further reduce exposures.
1-1.2 Implementation of Policy The policy is enunciated by a Radiation Safety Committee composed of members drawn from various company departments who use or manage the use of sources of ionizing radiation. The implementation of decisions of the Radiation Safety Committee is the responsibility of the Health Physics Office.
1-1.3 Philosophy of Radiation Safety: Risk versus Benefit l
1 The benefits to be derived from the use of ionizing radiation may require some risk of exposure to radiation. In such insteaces it is necessary to strike a balance between risk and benefit in keeping with basic company policy. This decision is part of the function of the Radiation Safety Committee together with the Health Physics Offica. Though strict objective criteria cannot be drawn up to apply in all circumstances, objective guidelines and established regulations will be followed whenever possible. l O '
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C l-2.0 RADI ATION SAFETY COMMITTEE -
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l-2.1 Responsibilities i
l The Radiation Safety Committee is responsible to the General Manager of TBE-ES. The responsibilities of this Committee are:
- 1) Formulate special company policy in the area of radiation safety.
- 2) Make decisions on the uses and approve the users of radioactive material (only for the 29-00055-06 license).
- 3) Approve new facilities and major equipment for the use of radioactive material by the company (only for the 29-00055-06 license).
- 4) Approve changes for existing facilities and major equipment (only for the 29-00055-06 license).
- 5) Enforce the safety requirements of international, federal, state, and local agencies as well as the procedures and policies as set forth by the Radiation Safety Code and Quality Control 1 Manual.
1-2.2 Membership & Quahfications The Committee is composed of members from the following divisions, sections or areas of p responsibility:
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- 1) Health Physics 1
- 2) Services
- 3) Products
- 4) Administration Membership may be changed as necessary. The membership of this Committee as of the date of this revision is shown in Section I Forms. The overall TBE-ES organization is shown in Section I Forms.
All members of the Radiation Safety Committee must have a college level degree and be familiar with radiation safety procedures and regulations. They must also be of management level or higher, or a member of the Health Physics Department with a minunum of 2 years experience.
12.3 Executive Subcommittee An Executive Subcommittee comprised of the Chairman, the company Health Physicist, R.S.O. and Alternate R.S.O. is authorized to act on behalf of the committee for approval of necessary actions between regular meetings of the Radiation Safety Committee. A quorum shall consist of any combination of two of the following persons: the Chairman of the RSC, the Company Health Physicist, the R.S.O. and the Alternate R.S.O.
l l-2.4 Safety Committee l p A Safety Committee comprised of various representatives of operational and administration l V departments will make recommendations to the R.S.C. for implementation of safety programs beyond the specific scope of radiation safety but within the requirements for general health and safety. Membership may be changed as necessary. The Safety Committee reports directly to the Radiation Safety Officer h..d 'he current membership is shown in Section 1 Forms.
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Radiation Safety Cod & T TELEW NE l Quah.ty Control Manual BROWN ENGINEERING Environmental Services l /3 O l-2.5 Records The Radiation Safety Committee is required to keep minutes of all quarterly meetings and any meetings of an Executive Subcommittee.
l l-2.6 Quahfications of the Company Health Physicist and the Radiation Safety Officer
- 2.6.1 The Company Health Physicist must have a B.S. degree in Health Physics or related field and have at least 4 years of practical health physics experience. Unless certified by the American Board of Health Physics,8 or more years practical experience is required. In the absence of the RSO, the Company Health Physicist serves as the Alternate RSO.
2.6.2 The Radiation Safety Officer must have a college degree in Health Physics or related field, and have at least 3 years practical health physics experience.
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Radiation Safety Ccde & T TELEDVNE Quality Control Manual BROWN ENGINEERING Environmental Services U(3 I-3.0 HEAL.TH PHYSICS OFFICE ,
1-3.1 Personnel This office is headed by a person qualified in the field of health physics and radiation protection.
This person's title is Radiation Safety Officer (R.S.O.) and he performs or supervises others so that the duties required of the Radiation Safety Program are performed in a timely manner. The person designated as Company Health Physicist is available to the RSO for support and for auditing purposes. In the absence of the RSO, the Company Health Physicist serves as the Attemate RSO. The R.S.O. is assisted by sufficient staff to carry out the Radiation Safety Program as set forth in this manual.
1-3.2 Duties The duties of this office are:
1
- 1) Approve all requests for the purchase or use of radioisotopes (lWL-HP-04). !
- 2) Survey all radioisotopes received by or slJpped by TBE-ES (IWL-HP-05). )
- 3) Maintain radiation histories of all TBE-ES personnel working with or exposed to sources of ionizing radiation (NRC Form 5 or equivalent, or other form required by law).
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- 4) Periodically (generally weekly) survey and make recommendations concerning TBE-ES j radiologically controlled areas.
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- 5) Dispose of all radioactive waste generated on TBE-ES property or under TBE-ES licenses.
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- 6) Prepare emergency procedures in case of an accident involving ionizing radiation. !
- 7) Indoctrinate all new TBE-ES personnel who will be working with, or be exposed to sources of ionizing radiation (IWL-HP-07).
- 8) Perform quarterly calibrations of all radiation survey instruments (IWL-HP-08).
- 9) Perform semiannualleak tests of alllicensed sealed sources owned by TBE-ES.
- 10) Assure compliance with all effective licenses and apply for m.mendments and renewals in a timely manner as approved by the Radiation Safety Committee.
- 11) Formulate procedures for, revise, and maintain the Radiation Safety Code and Quality Control Manual.
- 12) Serve as technical advisor to the Safety Committee. Provides liaison with the Radiation Safety Conunittee and submit recommendations for approval.
- 13) Approve all users of radioactive materials (IWL-HP-06).
- 14) The Company Health Physicist and the Radiation Safety Officer each have the authority to shut down any operation involving the use of radioactive materials if they feel the continuation of such activities could pose a hazard to the health and well-being of the employees or the general public.
f (O/ 15) The Radiation Safety Officer will review all survey and personnel monitoring data and report to the Radiation Safety Committee, at periods not exceeding one year, his recommendations to reduce exposure with respect to ALARA.
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U 16) Serve as the company liaison to the U.S. Nuclear Regulatory Commission on license and inspection matters.
- 17) Establish and maintain a leak test program for sealed sources.
- 18) Conduct semiannual physical inventory of radioactive material.
- 19) Investigate the cause of any incident and determine the proper preventive actions. ,
1-3.3 Records are maintained by the Health Physics Office on the following:
Licenses and license applications.
License inspection reports and responses.
Radiation history, past and present, on all TBE-ES personnel.
All requests for sources of ionizing radiation.
- Waste disposal.
- Surveys and recommendations.
- Calibration results.
- Surveys of all sealed sources.
All records will be maintained a minimum of five (5) years after the expiration date of any licensed activity to which they pertain.
1-3.4 Reference Material
- 1) The Health Physics Office maintains a current file of all domestic and foreign regulations pertinent to activities under the various licensed activities.
- 2) The Health Physics Office maintains a reference library of health physics, radiation protection and related measurement technology as required for support of licensed activities, license revisions, and expansion of business in related areas.
1-3.5 Professional Associations The Health Physics Office maintains membership in appropriate local, state, national and international professional societies as required to remain current in development of radiation protectbn philosophy, regulation, and techniques, and to enhance our professional reputation and explore opportun'. ties for future business.
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Radiation Safety Code & T TELEDVNE Quality Control Manual BROWN ENGINEERING Environmental Services 1-4.0 - PROCEDURE FOR REVISING RADIATION SAFETY CODE AND QUALITY CONTROL M ANU Al To ensure that any procedure or form complies with all of the laws, rules, and regulations goveming the safe handling of radioactive materials, a procedure whereby a person directly involved in the manipulation of the materials may submit a procedure or form for approval by the Radiation Safety Committee and the Company Health Physicist must be followed. The following lists the steps to be followed to ensure such compliance.
1-4.1 Writing a Procedure or Producing a Form 4.1.1 The person who writes the procedure will generally be the supervisor or manager of the area.
4.1.2 A r,eneral outline will be followed in the writing of a procedure as follows:
- GeneralInformation
- Detailed Procedures
- Conclusions (when necessary)
- Forms Used (Documentation) 4.1.3 The numbering system will be as follows:
1.0 General Information 1.1 1.1.2 1.1.2.1 1.2
] 2.0 4
2.1 etc. . . .
i Forms are numbered by IWL (Isotopes Westwood Laboratories), plus a two letter code designating the I license area (e.g. RW= Radiological Waste) and a consecutive two or three digit serial number. Each page of each manual or procedure must be identified by a code which indicates the manual or procedure, the date of revision, and an indication of approval.
1-4.2 Submission and Review 4.2.1 Once drafted, the procedure will be reviewed by the Department Manager with respect to general safety practices and fulfillment of objectives.
j 4.2.2 Once reviewed by the Department Manager, he will submit it to the company Radiation Safety Officer (R.S.O.) for review with respect to compliance with all the applicable laws, rules and regulations.
4.2.3 The R.S.O. will make any changes deemed necessary and return the draft to the Department Manager for review. This is done to ensure that any changes made will not appreciably alter the scope or purpose of the procedure.
i O 4.2.4 The Manager will then submit the draft to the Executive Subcommittee. The Executive Subcommittee will make a determination on the draft and if acceptable, the Chairman of the R.S.C. will approve the draft. He will endorse the procedure to verify acceptance.
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Radiati2n Saf:ty Code & TTELED(NE Quality Control Manual BROWN ENGINEERING Environmental Services 4.2.5 If the procedure does not meet with approval by the Executive Subcommittee, the changes will be made and resubmitted.
4.2.6 Upon final acceptance, the procedure and/or forms will be incorporated into the appropriate section of the Radiation Safety Code and Quality Control Manual.
4.2.7 Review of Radiation Safety Code and Quality Control Manual.
The entire Radiation Safety Code and Quality Control Manual will be reviewed and approved by the R.S.O. at intervals not to exceed five years. Upon complete review and revision, all previously issued copies will be replaced. Significant interim changes will be issued for insertion into issued copies as they occur.
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i Radiation Safety Code &
Quality Control Manual T[RO ENGINEERING Environmental Services SKTION I FORMS
,i Allforms referenced in Section ifollow. Forms referenced in Sections 11 & !!! can befound at the end of ea individual section.
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4
] Organization Chart i
Members of Radiation Safety Committee Members of Safety Committee Dr. Donald F. Schutz Resums Steven A. Black Resume 4
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MEMBERS OF RADIATION SAFETY COMMITTEE Donald F. Schutz, Chairman General Manager Steven A. Black, Radiation Safety Officer Manager, Radiological Services Jeffrey M. Guenther, Company Health Physicist Manager, Quality Control Alan Latham Manager, Environmental Analysis Lewis F. Casabona Manager, Mass Spectrometry Services Eugene D. O'Brien Manager, Administration & Finarce Arlene Baker Personnel Director Note: This Table is subject to change without notification to Regulatory Authorities.
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O MEMBERS OF SAFETY COMMITTEE Diahann McFarlane, Chairperson Radiological Services Department I
Linda Tyndall Environmental Analysis Department i Arlene Baker Personnel Department l l
Al Hogan Environmental Analysis Department Robert Pavese Maintenance Department Keith Noyes Mass Spectrometry Department Note: This Table is subject to change without notification to Regulatory Authorities.
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1 Radiati::n Saf:ty Code & T TELEDVNE Quality Control Manual BROWN ENGINEERING Environmental Services p 1 A RESUME Donald F. Schut:, Ph.D. l General Manager - TBE-ES Dr. Schutz is General Manager of Teledyne Brown Engineering - Environmental Services in which capacity I he has overall responsibility for all activities of the company. These include products, services, and research in j environmental radioactivity monitoring, thermoluminescent dosimetry, sodium iodide crystal manufacture, ,
radiological waste disposal, nuclear fuel analysis, geochronometry, and isotope geochemistry. Dr. Schutz is l actively engaged in the technical direction and marketing of TeleTrace - a subsurface fluid tracing procedure offered to the petroleum industry to enable them to obtain more meaningful data in their enhanced secondary recovery operations. He is the Chairman of the Radiation Safety Committee and is responsible for the Quality Assurance Program of the company.
1 From 1970 to 1975 Dr. Schutz was Vice President of Teledyne Isotopes in charge of the Westwood Laboratories. Prior assignments have included Manager of Nuclear Operations from 1968 to 1970, with responsibility for projects carried out for the Nuclear Monitoring Research Office of the Defense Advanced Research Projects Agency (DARPA), the Arms Control and Disarmament Agency (ACDA), and the Atomic Energy Commission for the study of radioactive products of underground nuclear explosions. His responsibilities ranged from laboratory studies of inert gas extraction and radioassay techniques to engineering development of sampling and detection systems. He participated in, and directed numerous field operations at the Nevada Test Site and various off-site nuclear test areas in Mississippi, New Mexico, Coloracio, Nevada, and Alaska. Dr.
p Schutz was principal investigator on Department of inergy projects concemed with the application of nuclear techniques to the exploration for uranium ore deposits, l
Prior to joining Teledyne Isotopes in 1964, Dr. Schutz was a Research Staff Geologist in the Department of Geology at Yale University where he received the Ph.D. degree in geology. He was primarily concerned with development of analytical techniques for the determination of trace elements in seawater and stream water by neutron activation, X-ray fluorescent and emission spectrographic analysis. The techniques developed were applied to a worldwide sampling of seawater which included sarnples taken by Dr. Schutz in the Antarctic during the summer of 1963-1964.
At Rice University Dr. Schutz completed a statistical study of regional variations in the chemical composition of basaltic rocks for which he received the M.A. in geology in 1958. Dr. Schutz received the B.S. l (cum laude) in geology from Yale University in 1956. Prior field experience includes work for the Bear Creek Mining Company on geochemical prospecting projects in the states of Maine and Arizona.
Professional and technical memberships include Sigma Xi, Geochemical Society, Geological Society of l America, American Geophysical Union, American Nuclear Society, Society of Petroleum Engineers of A.I.!A.E.,
Society of Petroleum Exploration, American Association of Petroleum Geologists, Energy Minerals Division of AAPG, Air Pollution Control Association, Atomic Industrial Forum, American Public Health Association, and Scientists & Engineers for Secure Energy.
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OFFICIAL RECORD COPY ML 10
Radiation Safety Code & T TELEDYNE Quality Control Manual BROWN ENGINEERING Environmental Services
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RESUME Steven A. Black B.A.
Manager, Radiological Services Mr. Black presently manages operations in the Radiological Services Department of Teledyne Brown Engineering - Environmental Services and is responsible for implementation of the facility's health physics program as the company's Radiation Safety Officer, and the facility's industrial / laboratory safety program as the Chairman of the Safety Committee. He has also been named the Plant Emergency Officer and is in charge of all evacuation and emergency procedures.
Specific duties include the following:
Operational control of the Health Physics & Radioactive Waste product lines.
Determining prices, preparing bids, and designing brochures.
Maintaining *he chemical inventory and proper hazardous waste disposal.
Radioactive & hazardous materials shipping compliance.
Compliance with N.J. Dept. of Environmental Prot. Divisions of Air & Water Quality.
Compliance and maintenance of six U.S. Nuclear Regulatory Commission licenses for the possession and use of radioactive materials.
Compliance and maintenance of an Illinois state license and a New Jersey state license for the possession and use of radioactive materials.
Implementing the facility's Right-To-Know program for employees and for emergency service p personnel.
\
- Computerization of all facets of the business using both Macintosh, BASIC and UNIX based systems.
Preparing and updating employee evacuation plans. ;
Safety orientation training for all new employees prior to their starting to work. i e
Fire Brigade leader and the liaison with the local volunteer fire department.
Mr. Black supervised the decontamination of the Department of Energy's New Brunswick laboratory located in New Brunswick, NJ. This project included the coordination of decontamination procedures, maintaining radiation safety records, and packaging radioactive wastes according to U.S. Department of Transportation, U.S. Nuclear Regulatory Comnussion, and burial site laws, rules, and regulations.
Mr. Black also supervised the removal and packing of approximately 21,000 cubic feet of thorium metal waste at the IBM facility in Owego, NY. During this operation he was in charge of all transportation coordination, health physics monitoring, and regulatory considerations of the transporting of large amounts of low specific activity radioactive materials.
While attending Brown University, Mr. Black obtained a Bachelor of Arts degree in Biology. He has taken numerous short courses on the packaging and transport of radioactive waste. He aim successfully completed the Rutger's University Radiation Science introductory course for the Master's program in Health Physics. He has acquired detailed computer programming skills in BASIC and FORTRAN, and is an experienced Macintosh
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computer user.
Radiation Safety Code & T TELEDYNE BROWN ENGINEERING Quality Control Manual Environmental Services SECTION 11 - GENERAL PROCEDURES FOR CONTROLLING RADIOACTIVE M ATERI ALS AND RADI ATION EXPOSURES l
This section deals with the general procedures for radiation protection which apply to the activities carried on )
under the several licenses currently in effect. Specific procedures relating to activities under particular licenses are included as sub-sections of Section !!! of this rnanual.
11-1.0 INDOCTRIN ATION OF PERSONNEL EXPDSED TO IONIZING RADI ATION 11-1.1 Company Policy on Matters involving Radiation Exposure Work performed under the various licensed activities treated in this manual require some degree of exposure to radiation by operating personnel. It is necessary, therefore, to classify these individuals in the population subgroup of occupational radiation workers. For individuals classified in this group, radiation exposure must be recorded on the employee's radiation exposure history while in the employ of Teledyne Brown Engineering - Environmental Services (TBE-ES).
Minors:
Employees under the age of 18 will be limited to an occupational exposure as detailed in 10 CFR Part 20.1207 (10 O percent of the annual dose limits for adult workers specified in 10 CFR Part 20.1201).
Declared pregnant wornen:
A declared pregnant woman will be limited to an occupational exposure as detailed in 10 CFR Part 20.1208 (500 mrem during entire pregnancy). Where possible and upon request by the employee, it is TBE-ES policy to transfer a declared pregnant woman to a position where there is little, if any, exposure to the individual.
11-1.2 Indoctrination & Training of Personnel All persons starting to work with any radiation sources at TBE-ES are required to read this Radiation Safety Code and this is documented on Form IWL-HP-07. In addition, each employee is required to furnish as complete a history as possible of their training in the principles and practices of radiation protection. This is documented on Form IWL-HP-06. A basic radiation safety course is then presented to each employee. Included is the showing of a ten part film series entitled "The Story of Radiation", distributed by Training Resources, a division of Nuclear Support Services. The outline of this course is given on Form IWL-HP-07 and this form is used as documentation of the presentation. These records are kept in the person's health physics folder.
Periodically, lectures and films on radiation safety are shown to keep all personnel apprised of the necessity for safe operating procedures.
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Quality Control Manual BROWN ENGINEERING l Environmental Services Form IWL-HP-06 is given to the supervisor of the employee who then fills in the section requesting authorization for the employee. This form is sent to the Radiation Safety Officer who will determine what l
l additional training or monitoring is required for the employee to begin work utilizing radioactive materials. If '
an employee's job function changes where new procedures involving radiation or radioactive materials occur, the supervisor is responsible for preparing a revised Form IWL-HP-06 and submitting it to the RSO for approval. No new job functions are allowed until this approval is obtained.
Persons who through their work attitudes and habits show a disregard for safe operating procedures with radioactive material are recommended for transfer out of radiation work or, if such alternative work is 1 not available, may be tertninated from employment.
11-1.3 Rights and Responsibilities of Radiation Workers and the Company Regarding NRC Licensed Activities l
l 1.3.1 Exposure History All personnel starting work with radicactive materials at TBE-ES are required to supply their supervisor and the Health Physics Office as complete a radiation exposure history as available.
g Each new employee will also have their estimated current year's exposure entered into their i
exposure file. Pursuant to 10 CFR Part 19.13(c), a worker may request his/her exposure history from a previous licensed employer.
Pursuant to 10 CFR Part 19.13(b), a worker may request, and each licensee (company) shall furnish annually, the radiation exposure that the worker has received.
When the company (licensee)is required pursuant to 10 CFR Part 20.1203 to report to the NRC an exposure of an individual to radiation or radioactive material, the company (licensee) must also report to the individual.
1.3.2 Notification of Violations During Inspections Pursuant to 10 CFR Part 19.14(b) the NRC inspector may consult privately with workers concerning matters of occupational radiation protection and other matters as deemed necessary by the inspector. During the course of these consultations, any worker may bring privately to the attention of the inspector, either orally or in writing, any past or present condition which he has reason to believe may have contributed to or caused any violation of the act, the regulations of 10 CFR Parts 19,20, and 21, or license condition, or any unnecessary exposure of any individual to radiation from licensed radioactive material under the licensee's control.
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Radiatien Saft*Y Coda & T TELED(NE Quality Control Manual BROWN ENGINEERING Environmental Services bv 1.3.3 Notice of Violations, Adverse Conditions, or Potential Violations or Conditions Prior to an Inspection If an employee becomes aware of any condition which may cause a violation of 10 CFR Parts 19, 20, or 21 or a lWnse condition or any unnecessary radiation exposure of an individual, the employee is responsible for the reporting of such a condition. The procedures for reporting can be found in Section 11-1.3.4.
1.3.4 Procedure for Reporting Items of Non-Compliance, Violations and/or Potential Violations 1.3.4.1 Super visor Contact The first person to be notified is the supervisor of the area in question. This notification is to be in writing and as detailed as possible.
The supervisor is then to take the necessary steps to follow up the report. If the problem is of sufficient severity, he will report it to the company Radiation Safety Officer.
1.3.4.2 Radiation Safety Officer Contact
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The Radiation Safety Officer will be notified by the individual if they feel the supervisor has not handled the situation in a prompt and efficient manner. This report is to be in writing and as detailed as possible.
1 The Radiation Safety Officer is then to take the necessary steps to follow up the report. If l the problem is of sufficient severity, he will report it to the Radiation Safety Committee.
1.3.4.3 Radiation Safety Committee Contact l
1 The Radiation Safety Committee will be notified by the individual if they feel the R.S.O. ,
has not handled the situation in a prompt and efficient manner. This report is to be in writing I and as detailed as possible.
The R.S.C. is then to take the necessary steps to follow up the report. If in the estimation of the Radiation Safety Committee, the situation warrants it, they will notify the Nuclear Regulatory Commission. See 10 CFR Part 19.5 for whom to contact.
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Radiati:n Saf:ty Codt & T TELEDVNE-Quality Control Manual BROWN ENGINEERING Environmental Services b 1.3.4.4 Nuclear Regulatory Commission Contact The Nuclear Regulatory Commission will be notified in writing by the individual as detailed i
in 10 CFR Part 19.5 if he feels the Radiation Safety Committee has not h.mdled the situation in a prompt and efficient manner. The report shall include appropriate identifying data such
' as the name of the licensee, the name of the individual, and a detailed description of the suspected violation.
1.3.4.5 Review of Reports on Violations In all cases where the report reaches the Radiation Safety Committee, the actions required, the actions taken, and the results obtained will be kept with the minutes of the Radiation 4
Safety Committee. If the report does not warrant the Radiation Safety Committee's review, l
it will be deemed of not sufficient importance and therefore no written record shall be required.
1.3.5 Requirement for Posting NRC " Notice of Violations" g If subsequent to an NRC inspection the licensee is given a " Notice of Violation", such notice must
, V be posted in a conspicuous place for 5 days or until compliance is achieved, whichever period is
- longer. Any written response required pursuant to a " Notice of Violation" will also be posted in a like manner.
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11-2.0 MEDICAL EXAMINATIONS AND EMERGENCIES -
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11-2.1 Pre-Employment Medical Examination New company personnel who will be exposed to, or potentially exposed to ionizing radiation may be required to submit to a medical examination at the discretion of the company Radiation Safety Officer or the Company Health Physicist. The results of this examination become a part of each person's pre-employment record and is kept on file in the Personnel Department.
11-2.2 Follow-Up Medical Examination Routine medical examinations are not presently required for those persons who are working with ionizing radiation due to the low permissible limits and excellent detection methods now available for external and internal radiation protection. At present, physical methods of detection of radiation are much more sensitive than signs or symptoms of deleterious biological effects identifiable in a routine medical examination.
However, if a person receives an exposure in any one quarter in excess of the radiation protection guide value but less than two times this slue, then he may be required to take a medical examination at the discretion of the company Radiation Safety Officer or Company Health Physicist. If the exposure is in excess of ( vo times the e radiation protection guide value, a medical examination is mandatory.
11-2.3 Termination Medical Examination Persons who are leaving the employment of the company may be required to submit to a medical examination as directed by the Company Health Physicist or Radiation Safety Officer. A radiobioassay examination is required for all personnel having worked with ionizing radiation.
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Il-2.4 Accidents involving Radiation Every incident involving exposure of company personnel to radiation in excess of the quarterly radiation protection guide value is classified as an accident and a report of the accident must be made to the Radiation Safety Committee by the Radiation Safety Officer. An accident involving exposure of company personnel to two times the quarterly radiation protection guide must be immediately reported to the Radiation Safety Committee and General Manager of the Westwood, NJ facility at the earliest practical date on its findings.
j Every incident involving contamination of equipment and requiring disposal or decontamination in excess of $100 or 1 man-day cleanup time must be investigated by the Radiation Safety Officer and a report made to the Radiation Safety Committee. Incidents with equipment losses in excess of $1,000 or S man-days for decontamination must be investigated by an Investigating Subcommittee appointed by the Radiation Safety j Committee.
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! A V Reports to federal, state, county and city authorities as required by law are the responsibility of the company Radiation Safety Officer.
11-2.5 Emergencies and Decontamination of Equipment The Health Physics Office is equipped with the necessary tools and protective clothing to handle all foreseeable incidents on company property. Specially trained teams are available to handle most anticipated incidents involving company personnel and property.
11-2.6 Fire Every precaution must be taken by all personnel to eliminate the possibility of fire on company property. This involves personal habits in regard to smoking and housekeeping. All electrical connections and ,
electrical equipment installation are made only with the approval of company Maintenance Department. I The presence of radioisotopes can complicate the control of a fire once started. Therefore, sources must !
not be left unattended except for standard sources used in instrument calibration containing an insignificant l amount of activity (less than ten microcuries). Overnight, all sources except as noted must be locked in fire-p resistant containers. Those sources under active preparation are excluded from this requirement as long as V adequate safeguards are instituted and cleared with the Health Physics Office. Also excluded are those sources which are permanently mounted in a shielded source holder.
In case of a fire the emergency evacuation procedure which can be found in the Safety Manualis to be followed. In the case of restricted labs, reentry will not be made unless accompanied by a Health Physicist.
Fires at night in company buildings will be controlled by the local Fire Department, but company l personnel will be alerted by the Fire Departnent and be present to direct them in fires involving radioactive material. The list of persons to call is included in Section 11-3.4 and is posted in easily accessible locations at the front and rear entrances of the main building and radiological warehouse. The local Fire Department will be updated every three years with the location of diffe- nt sources of radioactive material at our facility. An
" Introduction to Radiation" training program will also be presented at these times.
l 11-2.7 Security Any radioactive material misplaced, lost or stolen must be immediately reported to the Health Physics Office. An immediate investigation will be made by this office to locate the radioactive material. If it is not immediately found, steps must be taken to alert other persons in the company to this fact as well as federal, state, county, and city officials as required by law.
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} 11-3.0 LABORATORY PRACTICES IN THE SAFE H ANDLING OF RADIOACTIVE MATERI ALS i
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11-3.1 Personnel Directwes i
- 3.1.1 Wear laboratory coats or other protective clothing at all times in areas where loose radioactive j materials are used.
3.1.2 Wear disposable gloves at all times while handling loose radioactive materials.
i 3.1.3 Do not eat, drink, smoke, or apply cosmetics in any area where radioactive materials are stored j or used.
- 3.1.4 Wear a TLD badge at all times if you have been assigned one. If you are entering an area where l
) the suspected radiation levels can be in excess of 0.5 mR/hr., the entry will be posted that TLD l badges are required. If you don't have a TLD badge, please contact the Health Physics Office
. prior to entry into a posted area.
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l 3.1.5 Confine radioactive materials in covered containers plainly identified and labeled with l identification number and if applicable, a " radioactive material" label bearing the l l radionuclide, activity, date and radiation level, i
l 3.1.6 Always transport radioactive material in shielded containers if required by the character of f radiation and strength of source.
3.1.7 Dispose of radioactive wastes only in specifically designated receptacles. See Section 11-8.0 for packaging and disposal procedures.
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- 3.1.8 Remove your lab coat when you leave an area where loose radioactive material were used. No lab coats are to be worn outside the restricted areas.
3.1.9 Never pick up an unshielded radioactive container with your hands. Even short tongs may make a significant difference in exposure.
3.1.10 Remember the inverse square law: Dose Rate is proportional to 1/d2 where d = distance 3.1.11 Mouth pipetting is strictly prohibited.
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! O O 11-3.2 Minor Spills I
l 3.2.1 Notify persons in the area that a spill has occurred.
3.2.2 Cover the spill with absorbant material.
3.2.3 Use disposable gloves and remote handling tongs. Carefully fold the absorbant paper and pad.
l Insert into a plastic bag and dispose of in the radioactive waste container. Also insert into the plastic bag all other contaminated materials such as disposable gloves.
3.2.4 Report the incident to the Radiation Safety Officer for follow-up survey.
11-3.3 Major Spills 3.3.1 Notify all persons not involved in the spill to vacate the room.
l 3.3.2 Cover the spill with absorbant material, but do not attempt to clean it up. Confine the movernent I of all personnel potentially contaminated to prevent the spread. l 3.3.3 If possible, and warranted by the characteristics of the isotope (s) involved, the spill should be shielded, but only if it can be done without further contamination or without significantly l increasing your radiation exposure. i 1
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3.3.4 Leave the room and lock the door (s) and prevent entry.
3.3.5 Notify the Radiation Safety Officer immediately. j 3.3.6 Contaminated clothing should be removed and stored for further evaluation by the Radiation Safety Officer. If the spill is on the skin, flush thoroughly and then wash with mild soap and lukewarm water.
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N.A 11-3.4 List of Persons to Call in Radiation Emergency
- 1) Person who is in charge of laboratory or area where emergency has occurred. This Person's name will be on the hazard sign for the laboratory area.
- 2) Radiation Safety Officer Steven A. Black Office: (201) 664-7070 Ext. 225 Home: (201) 666-4588 Cellular Phone: (201) 294-0546
- 3) Maintenance Engineer Robert Pavese Office: (201) 664-7070 Ext. 205 Home: (201) 262-4270
- 4) General Manager - Chairman, Radiation Donald F. Schutz Safety Committee i k Office: (201) 664-7070 Ext. 213 Home: (201) 391-2790
- 5) US Nuclear Regulatory Agency (610) 337-5000 (301) 816-5100 After Hours
- 7) NJ State Police Emergency Management (609) 882-2000 O
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U 11-3.5 Contamination Control Directives i
3.5.1 Never consider the outside surface of the inner container of radioactive material to be free of contamination.
3.5.2 Always survey the innet container surface for contamination by taking a smear and checking it with the proper instrument. Only packages of radioactive material which contain greater than
" limited quantities" are subject to this directive.
3.5.3 Always use gloves and fume hood when working with unsealed radioactive materials in excess of exempt quantities.
3.5.4 Never open a container unnecessarily without a definite purpose.
3.5.5 in transferring any liquids, the following steps must be taken:
Prepare a shallow tray by lining it with plastic-backed absorbant material.
Put the radioisotope container, the properly labeled receptacle and necessary tools into V the tray.
Evaluate by calculation or measurement the extremity and whole body dose expected during the operation.
Consider that me radioisotope container top is highly contaminated.
- Perform the transfer operation in a hood wearing gloves and lab coat.
- Remove and dispose of the absorbant liner, survey and dispose of or decontaminate any contaminated items.
Decontaminate the original container unless it is to be disposed of, seal it in a plastic bag and return it to storage.
3.5.6 Notify Health Physics whenever work is to be done with finely divided powders or especially hazardous substanc. s.
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i Radiation Safety Code & T Quality Control Manual BR N ENGINEERING l Environmental Services 11-4.0 ORDER, TRANSFER, R.EGIPT AND SHIPMENT OF RADIOACTIVE .
i M ATERI.ALS i
} 11-4.1 Order J
- All purchase requests for radioisotopes must be forwarded to the Health Physics Office on a standard TBE-ES Purchase Requisition form and Form IWL-HP-04.
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- 11-4.2 Transfer i
i j No radioisotopes can be transferred from the user (s) as recorded on Form IWL-HP-04 for the specific j radioisotope or radiation source unless another Form IWL-HP-04 is submitted and approved indicating the new
]. user (s), use, and location of the radioisotope.
} 11-4.3 Receipt j All incoming radioactive material must be checked and recorded by the Health Physics Officer or i designated representative on Form IWL-HP-05. Prior to delivery of radioisotopes from the Receiving j Department to a user, the shipment must be checked by the Health Physics Office.
- O 11-4.4 Shipment j
l Shipment of all radioactive material is under the supervision of the Health Physics Office. Each l shipment must be checked and approved by the Health Physics Office on Form IWL-HP-05. Shipment
} procedures are dealt with in detail in subsections on Radiological Waste Disposal License (NRC License #29-q 00055-14), State of New Jersey License (#10123), Precious Metals Decontamination License (NRC License #29-00055-15, and Special Nuclear Material License (NRC License #SNM-107).
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11-5.0 PERSONNEL MONITORING -
l Internal and external personnel monitoring will be in accordance with 10 CFR Subpart C - Occupational Dose Limits.
11-5.1 External Dosimetry l
l Every employee of, and visitor to, TBE-ES laboratories and plants must wear personnel monitoring ;
devices such as TLD badges and/or pocket dosimeters if their work or tour involves entry to radiologically l controlled areas containing sources of penetrating radiation.
l Radiologically controlled areas are defined as specified by Part 20 of Title 10 of the Code of Federal Regulations and consist of the following areas:
Environmental Analysis -
Provisions of NRC License #29-00055-06 Standard Solution Storage Room Laboratory Room 614A -
Provisions of NRC License #SNM-107 O
Metals Processing & -
Provisions of NRC Licenses #29-00055-15 & I Nuclear Fuels #SNM-107 Laboratory i
Source Room -
Provisions of NRC Licenses #29-00055-06 Warehouse -
Provisions of NRC License #29-00055-14 1 and NJ License #10123 j l
A list of those persons monitored by TLD badges is maintained by the Health Physics Office. The ;
TLD badges are read out by TBE-ES Badge Service Department. !
TLD whole body badges are changed quarterly. A formal investigation by the RSO will be done whenever a badge receives a dose in excess of ten percent of the applicable limit.
1 Quality control of TLD dosimetry is set forth in the TLD personnel Badge Service Quality Control i Manual (IWL-03420-416) and TLD Badge Service Quality Assurance Manual (IWL-0792-442). '
O Version 5.0 November 27,1996 Page 11-12
Radiati n Safety Ccde &
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k 11-5.2 Internal Dosimetry Some radioisotopes do not emit radiation capable of penetrating 1 millimeter of tissue but are extremely toxic if taken internally. In this case, the standard monitoring technique is to analyze urine, feces, breath or blood of the person exposed to the particular radioisotope. This analysis is called bioassay and approximate equations permit an estimate of the intemal body burden and whole body dose.
Bioassay samples are collected from all TBE-ES personnel working with alpha emitters, carbon-14, hydrogen 3 (tritium) and such other radioisotopes as indicated by the Health Physics Office on a quarterly basis. Whole or partial body counts can also be used to estimate the body burden. Direct thyroid counting is done on employees using quantities in excess of 0.1 mci of any of the iodine isotopes. Bioassays for company personnel l
are carried out under the same procedures and controls employed for commercial service under Clinical !
Laboratory License #29-1012 by the New Jersey and New York State Departments of Health.
The action levels for tritium and iodine bioassay are equal to 10 percent of the Annual Limits of i Intake (ALI's). When these action levels are exceeded, an investigation into the actions and possible mode of I intake is performed. Additional bioassays are performed to determine the committed dose.
Procedures are set forth in the Environmental Analysis Analytical Procedures Handbook (IWL-0032-
\
419) with Quality Assurance as set fort in Section IV of IWL-0052-420, Radiocarbon Age Determination Quality Control Procedures. Bioassays are also performed in the Health Physics Department under the Health Physics Analytical Procedures Handbook (IWL-0312-452).
O Version 5.0 November 27,1996 Page 11-13
Radiation Safety Code & T TELEDYNE Quality Control Manual BROWN ENGINEERING Environmental Services G
V 11-6.0 SURVi?YS Unless otherwise specified in Section III, contamination surveys will be performed as follows:
I. Low-Level At least quarterly II. Medium-Level At least monthly III. High Level At least weekly Depending on the nature of the radiation emitted and the level of radioactivity, the area is checked for external radiation as well as airborne and surface contamination. NOTE: See Reference Table 2, p.12 NCRP report No. 30 " Safe Handling of Radioactive Materials". We use a factor of ten (10) lower than those listed as a guideline for determining low, medium or high hazard.
11-6.1 Area Surveys i
i Areas are checked with the properly calibrated instrument for intensity of external radiation. In addition, smears are taken on all accessible surfaces to check for transferable radioactivity. Particulate air and gas samples are collected with the appropriate sampling device to check for airborne contamination when required. The operation of all safety devices incorporated in laboratories and work areas for safe work with ionizing radiation such as interlocks, hoods and area radiation alarms are periodically checked as well. If the results of these surveys are in excess of the contamination levels listed in Section 11-6.3, the person responsible for the area is notified. A copy of the Health Physics Survey is kept in the Health Physics Office for future reference. Non-comphance with these recommendations is cause for removal from work with sources of ionizing i
radiation in TBE-ES facilities. l a
11-6.2 Decontamination Periodically, areas will become contaminated with radioactive material. The above-mentioned periodic surveys attempt to control this contamination hazard but will not eliminate it. Therefore, the Health Physics Office is equipped with decontamination clothing, respirators, tools, and cleaning solutions to assist in the decontamination of equipment and buildings in case the need arises. In most cases, the Health Physics Office will merely supervise the decontamination operation because of the educational value of decontamination experience by personnel responsible for the contamination. Request for permission to deviate from this rule must be made to the Health Physics Office.
O Version 5.0 November 27,1996 Page11-14
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(U 11-6.3 Survey Review All survey results are reviewed by the Radiation Safety Officer or his designee. Results are evaluated according to the action limits designated below. Items found to be in excess of 25% of these limits will be reported to the laboratory manager. Items in excess of 50% will be decontaminated as soon as practicable.
Lab Surfacesl Clothingl Skin 2 Alpha fixed: 1000 100 50 l
Alpha removable: 200 20 N/A Beta-gamma fixed: 5000 500 250 Beta-gamma removable: 1000 100 N/A NOTE: All values are dpm/100 cm2, l
, All areas in excess will be decontaminated or disposed of as radioactive waste.
2 1f any area cannot meet these levels after vigorous cleansing, additional Health Physics review is necessary.
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Radiation Safety Code & T TELEDVNE Quality Control Manual BROWN ENGINEERING Environmental Services O
O 11-7.0 INSTRUMENT CALIBRATION
!!-7.1 General A number of instruments listed in Section 11-10.0 (Form IWL-HP-18) are available to perform surveys and must be calibrated in accordance with the instrument calibration procedures below. On each company instrument a label must be placed indicating date of calibration, instrument serial number, and the initials of the person doing the calibration. Instrt. ment calibration records traceable to NIST standardized sources are maintained by the Health Physics Office (Form IWL-HP-08). Most of our instruments are calibrated by TBE-ES 1 under our 29-00055-06 license.
Each scale of the instrument is calibrated using two points. One point is in each half of the scale and they are separated by approximately 35% of the full scale. Log scale instruments are calibrated with one point near the mid-point of each scale. All instruments used must read within i 10% of the calculated or known
- calibration point. If the reading cannot be adjusted within 10% but is within i 20%, the instrument will not be l q used unless a graph indicating the actual value is attached. If the reading is off by more than i 20%, the instrument will be declared out of service and repaired.
A reference check source with a specific geometry shall be utilized after calibration, before use, after use, after maintenance and after a battery change. If the reading differs by more than the i 20% of the reading measured after calibration, the instrument will be recalibrated.
O 11- 7.2 Gamma Calibration All gamma sensitive radiation survey instruments are calibrated quarterly utilizing standard sources I traceable to NIST. The sources are approximate point sources.
11-7.3 Beta Calibration All instruments used to measure beta radiation during radiation surveys are calibrated quarterly with sources traceable to NIST.
11-7.4 Alpha Calibration All instruments used to measure alpha radiation during radiation surveys are calibrated quarterly with sources traceable to NIST.
11- 7.5 Frequency of Calibration All survey instruments are calibrated on a quarterly basis.
11- 7.6 Standards The standards utilized depend on the radiation to be detected. Generally, we use Cs-137, Co-60, Tc-99 or Pu-239 sources. All standards are traceable to NIST.
O Version 5.0 November 27,1996 Page 11-16
Radiation Safety Code &
yWyENGINEERING Quality Control Manual Environmental Services uO V 11-8.0 RADIOACTIVE WASTE PACKAGING & DISPOSAL -
Radioactive waste materials are disposed of by the Radiological Services Department in accordance l with all federal, state and local regulations. The generators of the waste are trained in the proper method of i packaging the waste and then tested on their knowledge to ensure compliance. The materials will be packaged !
using the " Classification of Radioactive Waste to be Packaged for Shipment" as a guide, and in conformance with the " Packaging Procedure for Radioactive Waste" i
11- 8.1 Safe Packaging of Radioactive Material - Training and Retraining i
Any person engaged in the preparation of waste for disposal must be properly trained in all the DOT, NRC and burial site requirements for proper packaging. The training program is as follows:
1 8.1.1 Each person is given a copy of the current Radiation safety Code and Quality Control Manual. He is to study these procedures (11-8.2 and 11-8.3) and then be tested on his knowledge of the material using Form IWL-RW-231, " Packaging of Radioactive Waste Examination".
8.1.2 Subsequent to the examination, each person will be physically supervised in the proper classification and packaging of waste in his area. Using Form IWL-RW-206, the supervisor will document such on-the-job training.
8.1.3 When the supervisor is satisfied the person has demonstrated a complete understanding of the procedures, he will notify the Radiation Safety Officer, who will authorize the individual to perform these procedures unsupervised and will document this on Form IWL-RW-206.
1 8.1.4 Retraining of the individual in tne most current DOT, NRC, and burial site packaging requirements is to be performed at a maximum one year interval unless significant changes require immediate review. Retraining and review will be documented using Form IWL-RW-206, or by filing a memorandum in each trainee's training folder. I Version 5.0 November 27,1996 Page 11-17
Radiarien Saftty Ccd & T TELEDVNE Quah.ty Control Manual BROWN ENGINEERING Environmental Services 11- 8.2 Classification of Radioactive Waste to be Packaged for Shipment
! 8.2.1 Characteristics of Material to be Packaged l
- Isotope
- Activity (mci) l
- Physical State (solid, liquid, vials, carcasses, biological matter or gas)
Concentration (mci / gram)
- A1, A2 Values Form (Normal or Special)
= 10CFR Part 61 Class A, B, C Stable or Unstable Chemical Form 8.2.2 Proper Shipping Name and UN ID Number Radioactive Material, Excepted Package - Limited Quantity of Material, n.o.s. (UN2910)
Radioactive Material, Low Specific Activity or LSA, n.o.s. (UN2912)
Radioactive Material, n.o.s. (UN2982)
Radioactive Material, Special Form, n.o.s. (UN2974)
Radioactive Material, fissile, n.o.s. (UN2918)
Radioactive Material, Excepted Package - Instruments Or Articles (UN2910)
Le
- Uranyl Nitrate, solid (RQ-100 lbs.) (UN2981) 8.2.3 Determination of Shipment Specification What specification container is required.
What labels are required.
Whether a security seal is needed or not.
mR/hr limits @ contact.
Additional requirements 11-8.3 Packaging Procedures for Radioactive Waste 8.3.1 General - All radioactive waste packaging procedures are in compliance with the current applicable regulations and license criteria of the respective processor or burial site to whom the package is intended. These procedures can be found as a separate document entitled, "Teledyne Brown Engineering - Environmental Services Radioactive Waste Packaging Procedures."
I l
Version 5.0 November 27,1996 Page 11-18
Radiation Saftty C:de &
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/m l 11-8.4 Radioactive Waste Interim Storage Plan l
Radioactive waste will be placed into interim storage only if disposal is not available. As I
disposal is currently unavailable to facilities in NJ, it will be stored until it can economically be shipped off-site for volume reduction processing. After return from processing, the waste will be stored in our radioactive waste serage facility (see NRC License No. 29-00055-14 for details) until disposal becomes available. Ah interim stored wastes will have a 5 year storage limit (after return from processing). If at that time disposal is not available, we will discuss our options with the U.S. NRC at that time. When disposal becomes available, the materials will be shipped for final disposal within 6 months of that date.
All interim storage wastes will be stored in U.S. DOT approved steel containers. The containers will not be exposed to the weather except during movement to and frorr 4 facility. The facility is surveyed weekly for both direct radiation and removable contammat m h.vels. All interim stored wastes will be physically removed from the facility every three mentns so that each pallet of four drums can be visually inspected. We will have over-pack containers readily available should one be needed.
g All other considerations for security and safety of the materials are addressed in our U.S. NRC
( No. 29-00055-14 license.
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- Radiation Safety Code & TTELEINNE Quality Control Manual BROWN ENGINEERING Environmental Services
! 11-9.0 1:ACILITlIN & liQUIPMENT -
l
, Please see the diagrams in the Forms section at the end of this Section. A list of the Health Physics equipment that is available for use can also be found in the Forms section. '
1 Construction of 103 Woodland Avenue l Please refer to the diagram that is included with Section II-Forms " Diagram of Warehouse - 103 i k Woodland Avenue". This building is constructed of cement block walls. There is a flat roof that is covered by
) sheet-rock on the inside. The overhead door is wooden and the other exit / entrance is steel.
, Construction of 50 Van Buren Avenue Please refer to the diagrams that are included with Section II-Forms. This building is constructed of cement block walls. There is a flat roof covered with a synthetic membrane.
Construction of the Degussa Facility - 3901 South Clinton Avenue, South Plainfield, NJ j Please refer to the diagrams that are included with Section II-Forms.
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Environmental Services '
11-1 0.0 INTERSTATE OPERATIONS ,
l !
From time to time TBE-ES will engage in activities involving the use of radioisotopes in Agreement I States. The following is a list the licensing officials in the agreement states as of the date of this issue. l LICENSING OFFICIALS IN AGREEMENT STATES Alaboma Colorado 205-613-5391 303-692-3030
.Mr. Kirksey E. Whatley, Director Mr. Robert Quillin, Director Div. of Radiation Control Radiation Control Div.
State Dept. of Public Health (RCD-DO-B1)
State Office Building Dept. of Health 572 East Patton Avenue 4300 Cherry Creek Drive South Montgomery, AL36111 Denver, CO 80222-1530 Arizona Florida 602-255-4845 904-487-1004 Aubrey V. Godwin, Director Lyle E. Jerrett, Chief Arizona Radiation Regulatory Agency Office of Radiation Control 4814 South 40th Street Dept. of Health & Rehabilitative Services Phoenix, AZ 85404 1317 Winewood Boulevard Tallahassee, FL 32399-0700 O Arkansas 501-661-2301 Georgia l
Ms. Greta J. Dieus, Director 404-362-2675 Div. of Radiation Control & Emergency Mgmt. Mr. Thomas Hill, Manager Dept. of Health Radioactive Materials Program 4815 West Markham Street, Slot 30 Dept. of Natural Resources Little Rock, AR 72205-3876 4244 International Parkway, Suite 114 Atlanta, GA 30354 Californla 916-322-3482 Ilhnois 916-322-2308 - Licensing & Inspection 217-785-9868 Mr. Edgar Bailey, Chief Mr. Thomas W. Orteiger, Director Environmental Health Div. Dept. of Nuclear Safety State Dept. of Health Services 1035 Outer Park Drive 601 North 7th Street Springfield, IL 62704 P. O. Box 942732 Sacramento, CA 94234-7320 Mr. G. Wayne Kerr Dept. of Nuclear Safety Mr. Ruben Junkert 1035 Outer Park Drive Low-Level Radioactive Waste Prog. Springfield, IL 62704 State Dept. of Health Services 601 North 7th Street IDEA l P. O. Box 942732 515-281-3478
! Sacramento, CA 94234-7320 Mr. Donald A. Flater, Chief l Bureau of Environmental Health l lowa Dept. of Public Health l s Lucas State Office Building l Des Moines,IA 50319 Version 5.0 November 27,1996 Page!!21
Radiati:n Saftty Code & T BRO ENGINEERING l Quality Control Manual Environmental Services l O V Kansas Nevada 913-296-1562 702-687-5394 Mr. Gerald W. Allen, Chief Mr. Stanley R. Marshall, Supervisor KS. Dept. of Health & Environment Radiological Health Section Bureau of Air and Radiation Health Div.
Radiation Control Program Dept. of Human Resources Building 283 505 East King Street '
Forbes Field Carson City, NV 89710 Topeka, KS 66620 New Hampshire Kentucky 603-271-4588 502-564-3700 Ms. Diane E. Tefft, Administrator John Volpe, Ph.D., Manager Radiological Health Bureau Radiation Control Branch l Div. of Public Health Services '
Cabinet for Human Resources Health & Welfare Building 275 East Main Street 6 Hazen Drive Frankfort, KY 40621-0001 Concord, NH 03301-6527 Louisiana New Mexico 504-765-0112 505-827-4358 Mr. William H. Spell, Administrator Mr. Benito Garcia, Chief Radiation Protection Div. Bureau of Hazardous & Radioactive Materials Office of Air Quality & Radiation Protection Water & Waste Mgmt. Div.
7290 Bluebonnet Road Dept. of Environment 2nd Floor 525 Camino delos Marquez IO P. O. Box 82135 P. O. Box 26110 V Baton Rouge, LA 70884-2135 Santa Fe, NM 87502 Maine New York 207-289-5676 518-473-0048 Mr. W. Clough Toppan, Mgr. Ms. Donna Ross, Energy Planner Radiological Health Program Div. of Policy Analysis & Plannmg State House, Station 10 2 Rockefeller Plaza Augusta,ME 04333 Albany, NY 12223 Maryland Mr. Robert Kulikowski, Director 410-631-3300 Bureau of Radiological Health Mr. Roland G. Fletcher, Administrator New York City Dept. of Health Radiological Health Program 111 Livingston Street Office of Toxics, Environmental Science & Health 20th Floor (TESH) Brooklyn, NY 11201 Dept. of the Environment 2500 Browning Highway Karim Rimawi, Director Baltimore, MD 21224 Bureau of Environmental Rad. Pro.
New York State Health Dept.
Mississippi Two University Place 601-354-6657 Albany, NY 12203 Mr. Eddie S. Fuente, Director Div. of Radiological Health Paul Merges, Director State Dept. of Health Bureau of Radiation 3150 Lawson Street Dept.of EnvironmentalConserv.
S P. O. Box 1700 50 Wolf Road, Room 506 Jackson, MS 39215-1700 Albany, NY 12233-7255 Version 5.0 Novernber 27,1996 Page 11-22
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( (New York - continued) South Carolina 803-734-4700 i Rita Aldrich, Principal Radiologist Mr. Max Batavia, Chief i
New York State Dept. of Labor Bureau of Radiological Health l Radiological Health Unit Dept. of Health & Environmental Control Building 12, Room 457 2600 Bull Street State Office Campus Columbia, SC 29201 Albany, NY 12240 Virgil Autry, Director North Carolina Div. of Rad. Waste Mgmt.
919-571-4141 Dept. of Health & Environmental Control l Mr. Dayne H. Brown, Director 2600 Bull Street Div. of Radiation Protection Cohunbia, SC 29201 Dept. of Environment, Health & Natural Resources 3825 Barrett Drive Tennessee P. O. Box 27687 615-532-0364 Raleigh, NC 27611-7687 Mr. Michael H. Mobley, Director Div. of Radiological Health North Dakota L&C Annex,3rd Floor 701-221-5188 401 Church Street Dana K. Mount, Director Nashville, TN 37243-1532 Div. of Environmental Eng.
Dept. of Health Texas 1200 Missouri Ave., Room 304 512-834-6688 P. O. Box 5520 Mr. Richard A. Ratliff, P.E., Chief Bismarck, ND 58502-5520 Bureau of Radiation Control 1100 West 49th Street Oregon Austin, TX 78756-3189 503-731-4014 Mr. Ray D. Paris, Mgr. 512-908-6065 Radiation Control Section Susan Ferguson, Director State Health Div. Texas Natural Resource Conversation Comm.
Dept. of Human Resources Uranium & Rad. Waste Section 800 N.E. Oregon St. #21 Industrial & Hazardous Waste Div.
Suite 705 P. O. Box 13087 P. O. Box 14450 Austin, TX 78711-3087 Portland, OR 97232 Utah Rhode Island 801-536-4250 401-277-2438 Mr. William Sinclair, Director Marie Stoeckel, Chief Div. of Radiation Control Div. of Occupational & Radiological Health Dept. of Environmental Quality Dept. of Health 168 North 1950 West 206 Cannon Building P. O. Box 144850 3 Capital Hill Salt Lake City, UT 84114-4850 Providence, RI 02908-5097 Washincton 206-586-8949 l Mr. Terry R. Strong, Director l Div. of Radiation Protection l Dept. of Health, LE-13
\ Airdustrial Center Building #5 P. O. Box 47827 Olympia, WA 98504-7827 Version 5.0 November 27,1996 Page 11-23
. __ _ _ _ . . - - - . . . - . -. . . . . _ . . - . . __ _- ~ . . . .-
Radiation Safety Code &
Quality Control Manual RW ENGINEERING Environmental Services l SECTION 11 FORMS I
I Allforms referenced in Section 11 follow. Forms referenced in Sections 1 & lil can be found at the e each individual section.
, FORM NUMBER TITLE I l
IWL-HP-04 Application for Radiation Source IWL-HP-05 Shipping / Receiving Survey Form
. IWL-HP-06 Isotope User Request Form l IWL-HP-07 Basic HP Training Course
] IWL-HP-08,08a,08b, & 08c Sample Calibration Forms l IWL-HP-18 Radiation Detection Instruments List IWL-RW-206 Retraining in Regard to Processing Generated Waste IWL-RW-231 Packaging of Radwaste Exam Diagram of Warehouse - 103 Woodland Avenue j Diagram of Zones 1 & 2 - 50 Van Buren Avenue l
l Diagram of Zones 3 & 4 - 50 Van Buren Avenue '
l 4
Diagram of Zones 5,6 & 7 - 50 Van Buren Avenue j Diagram of Degussa Corporation - 3601 South Clinton
} Avenue, South Plainfield, NJ
}
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l T TELEDYNE BROWN ENGINEERING Environmental Services l V APPI2 CATION FOR RADIATION SOURCMS) l Name Date l Building Position Isotope (s) Telephone Number Quantity (les) Chemical Fonn Present Inventory Physical Form location of Use (Bldg. & Rm.) location of Storage Proposed use (activity levels, special hazards, method of disposal of wastes, safety measures)
Attach supplementarf sheet if necessary.
p)
N._
Applicant's training and experience (relevant to use of radioisotopes):
1 Radiation detection instruments, facilities, and equipment that will be used: '
The applicant agrees to abide by the letter and spirit of all applicable regulations as recorded in theRadiation Safety Code & Quality Control Manual Applicant's Signature For Use ofHealth Ph bsics ODice Only Comments of Health Phy sics Office Decision.
Date: _ Signature l Please complete and retum with Purchase Request to: Health Physics Oplce
! (O
! U l IWL.HP.04 Revised 8/88
W TELEDYNE BROWN ENGINEERING Environmental Services
(
(
SIDPPING/ RECEIVING SURVEY RECORD Date Shipped Date Feceived Fmm To _ _.
Owner of'Ihnsport
'lype of Package _
Pmper Shioping Name label Used: I,11, Ill, N/A Activity imCI) Huclide Activity (MCI)
Nuc!!de Reading at Contact Reading at 3 ft.
n V) i Instrument Ser.# Cal. Date Smear Survey (dpm/100 cm2):
Giuss Alpha Giuss Beta Package Shipped Properly? Yes No If no, specify problem:
Routing:
White: No further h-alth Physics r quired Green: Health Physics survey of mner package required Blue: Health Physics survey ofinner package required Red: Wore in cave (notify Health Physice prior to opening)
W'ute Green Blue Red (Check One)
Surveyed By Date Appnwed By Date FORM IWIeHP-05 Revised 8/88 l
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Birth Date Contact Ixnses: Yes No m
m Highest Level of Education Completed Teledyne isotopes Employee #
Type of Training Where Trained Duration On the Formal a ofTraining Job Course
- a. Principles and practices Yes No Yes No of radiation protection b,
3 dadioact.ve measurement Yes No standardization and Yes No monitoring techniques g and instruments j W c. Mathematics and j J calculations basic to the Yes No Yes No
- Q. use and measurement of l j E radioactivity l
j O d. niological efrects of Yes No Yes No l 3 O radiation l
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- O EXPERIENCE WITH RADIATION (Actual use of radioisotopes or equivalent experience) g Isotope Maximum Amount Where Experience Duration of Type of Was Gained Experience Use a
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!- C Radiation work for which authorization is sought:
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(D gb C > is otopes: Physical & Chemical Form: l
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H23 Activity: millicuries UPeMsor Requeshg Authorization:
j O 0) Safety Glasses Required: Yes ___ No __
O> Date:
m Safety Shoes Required: Yes__ No __
> I
! H y Health Physics Comments I 1, W LL WJ TLD Badge Required: Yes .__ No _._ Bioassay Required: Yes No 4gZ Type Analysis Frequency U) { go oOm Authorization Date By j U Radiation Safety Otheer 1 .
p@ Health Physics i O D. C OH original to Personnel Department
_ Supervisor TLD Badge Service Chemical Safety Trainer OE o Form IWI<HP-06 (Rev. 9/91)
HSCOCM 4 80 Date Approved Retn.
Ravevi
WTELEDYN'1 BROWN ENGINEERING Environmental Services (o) BASIC HEALTH PHYSICS TRAINING COURSE Name 1.ength of Course IYesented by Test Course Outline
- 1. Introduction V. Radiation Protection A. Electromagnetic Spectrum A. Monitoring Instrumentation B. Ionizing Radiation 1) Film Badges
- 2) Thermoluminescent dosimeters
- 1) Alpha 3) Portable survey meters
- 2) Beta 4) Bioassay l
- 3) Gamma l
- 4) X-rays B. Effects
- 11. History of Uses 1) Chemical change
- 2) Biological A. Consumer Reports 3) High doses
- 4) Low doses p B. Medical 5) Incidence of disease O C. Industry C. Cause & Effect RelaUonships III. Nuclear Constituents. Properties & Production D. Risk Assessment A. Alpha Particles E. Regulations
- 1) ICRP B. Beta Particles 2) NCRP C. Fission F. Organizational Troup:,
D. Gamma & X-rays G. Prenatal Exposure:
Regulatory Guide 8.13 IV. History of the Atom B. Modern Thecay C. Application for Radiation I have received the training outline above, read the Radiation Safety Manual and Regulatory Guide 8.13 "Instniction concerning Prenatal Radiation Exposure", and understand its implications. Any questions I may have had were answered to mjt satisfaction.
Employee's Signature Date Remarks O.
V IWirilP-07 Ikvised 1/19/95
1 CERTIFICATE OF
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_ _ _ _ . _ _ _ _ . _ _ _ - - _ . - . . . - - . ~ . - ~ . - . - . - . - . - - . - - - - . - -
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l SPECIAL NOTES:
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_ . _ _ _ _. _ _ _. _. ....._..____. _ _ _ _ _ _ _ . _ _ _ _ _ . . _ . ~ _ _
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CERTIFICATE OF gm CALIBRATION
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CALIBRATED FOR:
l MODEL No.: SOURCE USED:
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l GROSS BACKGROUND NET HIGH COUNTS COUNTS COUNTS VOLTAGE (CPM) (CPM) / (CfM) l
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naomnouoerecnoTmsravusurano" BROWN ENGlNEERING The fo!!owing instruments are currently available for field uSe or laboratory counting: Environmental Services MANUFACTURERS NO. TM RADIATION NAME DESCRIPTION MODELHO, AYAILABLE. i?,ETECTABLE_ BANCf. WINQQW.1NIC!DiESS USE Ebertine Lin4.og Gas PAC 4G 3 alpha ( >J,000 cpm Aluminize U r Surveying Ebertine proportional F44G beta 0.85 Floor Surveying Alpha Counter Ebertine Lin-Log Gas PAC-4G-3 1 Tritium 0-500.000 cpm Aluminized Mytar Surveying Proportional beta 0.85 mg/cm2 A$ha Counter alpha Ebertine Beta-Gamma E-120 4 alpha 0-50 mRhr Mica 1.4 to Surveying Survey Meter beta 2 mg'cm2 gamma Eberline Gamma Radiographic E-120G 1 gamma 0-1000 mRhr none Surveying Survey Meter Ebertine Gamma Radiographic E-130G 3 gamena 0-1000 mR/hr none Surveying Survey Meter Ebertine Beta-Gamma E-530 1 alpha 0-200 mRhr Mica 14 to Surveying Survey Meter beta 2.0 rraycm 2 gamma Ebertine Beta-Gamma E-140 2 alpha 0-50 mR/hr Mica 1.4 to Surveying Survey Meter beta 2.0 mg/cm2 gamma Victoreen ion Chimber V440N-440RF 2 alpha 0 300 mR,hr Mylar 1/4 mit Surveying Survey Meter beta gamma x-ray Victoreen ton Chamber V-471 1 alpha 0-300 Rhr Mytar 1.1 Surveying Survey Meter beta mg/cm 2 gamma x-ray intertechnique Liquid SL-30 1 low energy beta 0 1.000.000 none Laboratory Scintillation total counts Counting Ebertine Mird Scaler MS-2 2 alpha, beta, gamma Os5000.000 Mytar Laboratory 2
total counts 0.9 mgtm Counting Ebertme Alpha Counter SAC-4 1 alpha 0 1,000.000 none Laboratory total counts Counting Ebertine Alpha / Beta / Gamma ESP-1 2 alpha 0-50,000 cps Aluminized tar Surveying /
Survey Meter / 0.5 m Countmg Scaler beta 0-1000,000 cps Mica 4 to 2.0 rng/cm2 IWL-HP-18 RSC/DCM 4.80 Date Approved Rev'd:
Revs'd:
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- BROWN ENGINEERING l Environmental Services O
RETRAINMG OFPFJL%ONNEL REGARDING PROCESSING OF GENERATED WASTE DATE: / / LNSTRUCTOR:
l ATIENDEES:
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SUEMECT OLTTLINE:
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BVL-RW-206 Revised 8/88 i
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! W TELEDYNE BROWN ENGINEERING Environmental Services O
l Packaging of Radioact,ive Waste Exam Section I. Fill in the blanks - 3 points each
- 1. List 5 characteristics of the waste needed in order to determine the proper U.S.
DOT " Proper Shipping Name"-
1
- 2. List 5 " Proper Shipping Names" typically used for radioactive waste shipments:
- 3. The radiation limit at contact with the outside of a container cannot exce-d g mR/hr. J
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- 4. Enter the appropriate numbers:
l Label mR/hr limits @ Contact !
Radioactive White I to 1 Radioactive Yellow II to Radioactive Yellow III to
- 5. The marking (label) needed on a package of LSA material (exclusive-use) should read .
- 6. The marking (label on a package of Radioactive devices should read .
- 7. The weight is required to be printed on a container when it is in excess of lbs., and it is a DOT-7A TYPE A container.
- 8. List the 6 categories of radioactive waste:
Form IWL-RW.231
W TELEDYNE l BROWN ENGINEERING l Environmental Services
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j 9. Items in different categories be mixed.
- 10. All scintillation vial drums must be lined with a .
I 1. The amount of absorbant added to any cintillation vial drum must be capable of absorbing the volume ofliquid in the drum.
- 12. Liquid Special Nuclear Material has to be before disposal.
II. True er False (1pt. each)
All drums which have a Radioactive I, II or III label require security
- 1. seals.
- 2. 400 lbs is the maximum weight allowed in a 55-gallon container.
3 Class A Stable is a DOT classification. l 1
- 4. Two 2-mil liners is an acceptable substitute for a single 4-mil hner.
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- 5. The pH range for acceptable liquids for incineration is 5.0-10.0. l (d' Animal carcasses are to be completely surrounded with rock salt and
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- 6. absorbant. l
- 7. Cement is an acceptable solidification media.
Ra-226 is acceptable at the Washington burial site under certain
- 8. conditions.
- 9. Packaging regulations are under the direct control of the NRC only.
The burial site's (or processor's) license requirements are of paramount
- 10. consideration when 4:ermining how to package a given material.
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Form IWL-RW-231 O t
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! Emergency Exit Security System Main Panel j Fire System Panel i
- Gas % ,
-N Intruder Contact OOOOOO Fire Extinguishing System s
-Electrical Service Panels 4
Shutoff I & Meter J
Motion Detector E
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- g Security System Key Pad 1 5 Motion Detector Intruder Contact N Exhaust Fan Exterior Manual Fire 25 feet Extinguisher Release I l Exterior LED Indicator l for Gas Detection O = Smoke oetectors
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O O TTELEDYNE BROWN ENGINEERING O
Environmental Services OV N Zones 1 & 2
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1 DIAGRAM i Q Degussa Corporation 3601 South Clinton Avenue South Plainfield, New Jersey SIIII IIIII Catwalk Area up lilli li ...
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i Radiation Safety Code & T TELED(NE Quality Control Manual BROWN ENGINEERING Environmental Services 3
(V SECTION' 111-4.0. SPECIAL PROCEDURES FOR PREClOUS Mi~I ALS
\
l DECONTAMIN ATION - U.S. NRC License No: 29-00055-i 5/SN M-107 111-4.1 Introduction This section includes items specific to the decontamination of precious metals. The metals come in a variety of shapes and sizes. The contaminants are generally special nuclear material (SNM), transuranics and, in some cases, Co-60 and Cs-137. Most of the metal processed is received through Lockheed-Martin, Oak Ridge, Tennessee, who are under contract to the U.S. Department of Energy (DOE). The material is generally of DOE I origin and shipped directly to us from their various sites. The use of SNM is covered under our SNM-107 license. l The material is received in lots and processed alone or in combination with other lots, depending on the physical size of the individual shipments.
Once decontaminated to pre-designated levels through the smelting process, the lead-metal alloy is sent for processing to a precious metal refinery to recover the precious metals. The refinery used for this purpose is Degussa Corporation, located at 3601 South Clinton Avenue, South Plainfield, NJ. We will limit the amount l of radioactive material used at the Degussa facility to 1/100th of the license limits found in Section 111-4.11.
111-4.2 Facilities & Equipment l i
There will be two facilities where licensed material will be possessed and used. The first facility, located at S0 Van Buren Avenue, Westwood, New Jersey, will be referred to as the TBE-ES Facility. The second facility is the Degussa Corporation facility located at 3601 South Clinton Avenue, South Plainfield, NJ, and will be referred to as the Degussa Facility.
The TBE-ES Facility is a one story cement block construction. The area where material is used under this license is identified on facility diagram (in the Forms Section at the end of this Section) by the cross-hatched area.
The major equipment used under this license is a glove box train where the precious metals are processed. The glove box exhausts through two separate systems. Glove box number 4 in the train is the furnace box and it exhausts through a water scrubber and then through a roughing and HEPA filter system. All the other sections of the glove box train are exhausted through a separate roughing and HEPA filter system.
Once the materials have been processed at the TBE-ES Facility to remove a majcrity of the contaminants, the materials will be shipped to the Degussa Facility for final parification. A Diagram of this facility can be found in the forms area following this section. The glass-lined jacketed " reactor" vessels are 50-ga%n inner-glass lined tanks that are heated by an outer jacket that contains hot water or heated oil. These tar Mr/e hinged lids to provide access from above and enable liquids to be pumped from one tank to another.
O Version 5.0 November 27,1996 Page !!!/4-1
Radiatien Safe *Y Coda & T TELEDVNE Quality Control Manual BROWN ENGINEERING Environmental Services The ceramic vacuum filters are over-sized "buchner" funnels, about 2 feet in diameter, and are used to filter and collect various purified metals during the last step of the process. The collected metals are then washed, dried and fired to a stoichiometric sponge form.
The furnace used to melt the alloy n the beginning of the process is called a " speedy-melt". It is a floor-mounted gas fired fumace in which the crucible resides. From past experience, this crucible is the only piece of equipment on which any activity has ever been detected. For this reason, this crucible is designated for this work only and will be bagged and sealed when not in use.
In addition to the Health Physics equipment listed in Section II, a Ludlum Model 2929 alpha / beta counter (or comparable instrument) will be kept in the office area of the Degussa Facility and will be used to count smears.
111-4.3 Training and Retraining All employees working under this license at the TBE-ES Facility are required to attend the Basic Radiation Safety course as outlined in Section II-1.2 " Indoctrination of Personnel". They are required to have an additional 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> of supervised on-the-job training. All specific written procedures and health and safety factors are to be learned to the supervisor's satisfaction. The items of health and safety are listed in Sections III-4.4,4.8 and 4.9. A refresher course, which is documented by memorandum, will be given at one year intervals.
All employees who work under this license are required to read this section of the Radiation Safety Code & Quality Control Manual, and are tested on their knowledge using Form IWL-FM-02, "29-00055-15 Licensed Activities Exam".
111-4.4 Radiation Survey Program The radiation safety program is, in general, that found in Sections 11-5.0,11-6.0 and 11-7.0. The following is a further description of the procedures to be performed for this license.
4.4.1 Weekly Surveys P=<% tion contamination surveys of the Buffer Zone and Precious Metals are performed weekly.
S"- *e monitoring for su > ontamination on all laboratory bench tops, chairs, tables, sinks, floors, u of hoods and y xes, and general laboratory equipment. Surveys of the Degussa facility wit %.ed on a a
- _
acy. An Eberline Instrument PAC-4G or PAC-4G3 gas proportional survey instr 6 -
wi arface contanunation.
G. .sels in the rooms are measured with an Eberline Instrument E-120 GM counter with end window probe or comparable instrument. Smear surveys for removable surface contamination are taken of areas designated to be representative of contamination on floors, benches, and equipment. Smear surveys are Version 5.0 November 27,1996 Page 111/4-2
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l Radiati:n Safity C:de & TTELErWNE l Quality Control Manual BROWN ENGINEERING Environmental Services v \,
U assayed using an Eberline Instrument Model MS-2 Mini-Scaler Single Channel Analyzer with a Model FC-1 Proportional Flow Counter or comparable instrument.
All survey results are reviewed by the RSO or the Alternate RSO. Results are evaluated according to the contamination limits designated in section III-4.2.2. Items found to be in excess of 25% of these limits will be reported to the laboratory manager. Items in excess of 50% will be decontaminated as soon as practicable, insides of hoods and glove boxes are assumed to be contaminated and are not included in the above.
The TBE-ES Precious Metals Decontamination Labs have access restricted to authorized personnel only. Entrance to these areas may only be obtained through use of a magnetic card key.
Laboratory coats and laboratory equipment are of the disposable type whenever possible, and must be removed prior to leaving the area. They must also be monitored. If contamination is found, they must be put in the appropriate waste container and a call must be made to the Health Phpics Department.
Workers must monitor hands and shoes before leaving the area with radiation monitors equipped with alpha and beta-gamma probes.
p Gloves in glove boxes are inspected routinely during surveys. Gloves are changed immediately if V deterioration or rupture is noticed. Even if deterioration is not noticed, gloves will be changed at least every second year. When high specific activity alpha emitters are present, more frequent changes may be necessary.
Common laboratory equipment is monitored routinely during the weekly survey. Any equipment that may contain radioactive contamination is reported to the laboratory workers and department managers for appropriate remedial action.
A general survey of the entire TBE-ES facility, including lunchroom areas, entrances, exits, halls, offices and lavatories is performed monthly.
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Radiation Saftty Code &
Quality Control Manual *[RO N NGINEERING Environmental Services i p 4.4.2 Contamination Limits The following limits for radioactive material contamination will not be exceeded on lab surfaces or l
equipment outside of hoods or glove boxes without prompt clean-up being initiated:
4.4.2.1 Alpha Contamination Fixed -
1,000 dpm/100 cm2 average 3,000 dpm/100 cm2 maximtun Removable -
200dpm/100cm2 maxunum 4.4.2.2 Beta Contamination Fixed -
5,000 dpm/100 cm2 average 15,000 dpm/100 cm2 maxunum Removable -
1,000 dpm/100 cm2 maximum
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'V 4.4.3 Procedure for Exiting the Precious Metals Decontamination Labs at TBE-ES
=
All workers must monitor their hands, feet and clothing prior to leaving the area with radiation monitors equipped with alpha and beta-gamma probes. If levels greater than twice background are detected, decontaminate, re-survey and contact the Health Physics Office. Under no circumstances should an individual who is contaminated in excess of twice background leave the controlled area without prior approval of the company Health Physicist, Radiation Safety Officer or Alternate
, Radiation Safety Officer.
Remove gloves and disposable clothing. Place contaminated items in the waste container.
Using the proper instrument for the isotope present, monitor hands while probe is still in the holder.
If the detector reading is greater than twice background, clean your hands and monitor them again.
If your hands are clean, check the response of the meter against the check source provided.
=
Sonitor the bottom of your shoes. If the detector reading is greater than twice background, clem y shoes and monitor them again. l i
i Proceed to monitoring your clothing using the same procedure outlined above.
L]
- Replace the detector in its holder, j
4 EXIT ONLY if you have completed the above.
i
- SPECIAL PRECAllTIONS \
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DO NOT place the probe face directly on the object to be surveyed.
DO NOT touch the probe handle without checking your hands for contamination.
DO NOT wear disposable clothing outside of the area.
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Radiation Safity Code & TTELED(NE i
Quality Control Manual BROWN ENGINEERING l
Environmental Services gk 4.4.4 Air Monitoring l
l 4.4.4.1 An air sampling system is set up to sample both breathing zone and effluent air at the TBE ES facility. Millipore filter air samples are used. Sampling locations are situated at breathing zone heights at or near glove boxes and hood faces to provide sampling points representative of the exposure that workers may receive. Sampling is performed continuously. An Eberline Instrument Alpha-1 air monitor with built-in single channel analyzer and audible alarm is also available and may supplement the stationary air monitoring system for projects where the possibility of airborne contamination could contribute to significant intemal exposure. Air samples are assayed using an Ludlum 2929 Alpha / Beta dual scaler or other comparable instrument. When an isotopic analysis is required, samples may be counted by alpha spectroscopy or gamma spectroscopy.
Air samples are assayed for the particular isotopes used during the preceding time interval. In the case where a mixture of nuclides was used, air samples are evaluated using the isotope with the most stringent maximum permissible concentration allowed. If airborne levels greater than 50 percent of the DAC's are detected, isotopic analysis of the sample will be performed and additional bioassays will be required. Calculation of internal deposition and exposure will be performed by the Health Physics Section using the most current assumptions and models available. Any incident requiring a detailed investigation will be discussed with the employee s involved prior to the resumption of work.
4.4.4.2 Effluent air monitoring of the stacks coming from the glovebox train will be performed. All are monitored continuously. Effluent air is filtered using a roughing prefilter and absolute filter rated 99.9% or better efficiency against D.O.P. smoke to 0.3 micron diameter.
Sample points for effluent monitoring are located beyond the HEPA filters at a point which represents the average air velocity. Sampling points employ fittings which curve in the direction of air movement. In the case of an emergency release or filter rupture, calculations for effluent release will be made using air sampling data and estimating the magnitude of particulate release that may have bypassed the sampling tube.
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Radiaticn Safety Cods & T Quality Control Manual BRO ENGINEERING Environmental Services O
U 4.4.5 Respiratory Protection Program A respiratory protection program will be instituted for certain work being done under this license.
Respirators fitted with radionuclide filter canisters will be used during the following procedures:
- 1) Bagging any material out of the glove boxes.
- 2) Opening any radwaste container.
- 3) Decontaminating the inside of a glove box or hood.
)
1
- 4) Changing the HEPA and roughing filters. '
- 5) Decontaminating any contaminated area in excess of the limits specified in 111-4.4.2.
i
- 6) Any other procedure the Radiation Safety Committee designates.
I The respirators will be fit-tested using irritant smoke to ensure a good fit. Personnel will be instructed as to the proper care, wear and maintenance of the respirator assigned to them.
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i Radiati:n Safsty Cods & NE Quality Control Manual R E GlNEERING s-Environmental Services l U 111-4.5 Shiprnents incoming and outgoing shipments of samples are controlled by the Manager, Mass Spectrometry Services. The drums are surveyed for compliance with all applicable laws, rules and regulations prior to opening.
f
!!!-4.6 Records Managernent The data received from all surveys, inventories, personnel dosimetry, and documentation pertaining to the receipt, use and disposal of radioactive materials are evaluated and retained by the Health Physics Office or the Office of the Manager, Mass Spectrometry Services of TBE-ES.
1 It is the primary responsibility of the Health Physics Office to obtain information of the exposure of each individual, location, or procedure employing radioactive material. The Health Physics Office is also responsible for observing trends or changes in the working habits of a single individual or department, and thus to measure the effectiveness of the radiation safety program.
Qualified members of the Health Physics Office responsible for these functions include the Alternate Radiation safety Officer ano the Radiation Safety Officer.
(n J
1
!!!-4.7 Material Control Provisions The procurement, receipt, use and disposal of all radioactive materials is maintained and controlled through strict administrative procedures by the Health Physics Department. All records and documents pertaining to these functions reside in appropriate files and are the responsibility of the Manager of the Mass Spectrometry Services Department.
The responsibility for maintenance of the radioactive material inventory for this license resides with the Manager of Mass Spectrometry Services Department.
v Version 5.0 November 27,1996 Page 111/4-8
Radiati n Saf:ty Code & T TELEDVNE Quality Control Manual BROWN ENGINEERING Environmental Services T
O 111-4.8 Safety Rules 4.8.1 General safety rules for work with radioactive materials are listed below. General safety l instructions for glove box use may be found in Section 4.8.2.
4.8.1.1 The doors to the laboratory and between individual labs should remain closed to ensure I proper air flow.
4.8.1.2 The blowers in all hoods and glove boxes shall be run continuously.
4.8.1.3 Work involving plutonium in excess of 1.0 micrograms must be perfonned in a glove box.
4.8.1.4 Hoods should not opened to a point beyond the 100 Ifm mark which is posted.
4.8.1.5 All work should be performed at least seven inches for the front of the hood, unless the size of the equipment placed in the hood prevents it.
4.8.1.6 Large objects placed into the hood will affect air flow. Contact the Health Physics Office for a re-evaluation if any large object is moved around or put into the hood.
f5 V 4.8.1.7 Never place your head in the hood unless you are wearing a respirator and your work requires such placement.
4.8.1.8 Do not rapidly rush up to or away from the hood as it may affect the air flow significantly.
4.8.1.9 Do not use explosive substances in any hood.
4.8.1.10 Upon noticing any deviation or deficiency in Items 4.8.1.1 through 4.8.1.9, please contact the Manager of Mass Spectrometry Services or the Health Physics Department.
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Version 5.0 November 27,1996 ibge III/4-9
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Radiati:n Saf:ty Ccde & TTELEENNE Quality Control Manual BROWN ENGINEERING m Environmental Services l 4.8.2 General Safety Instructions for Glove Box Use 4.8.2.1 Work involving plutonium in excess of 1.0 micrograms must be performed in the glove box unless written approval to the contrary is obtained from the Health Physics Section.
4.8.2.2 All material to be used in the glove box must be bagged in and bagged out. A Health physics
- representative must be present during bag-out operation.
4.8.2.3' Any time glove box containment is to be broken (i.e. a glove removed or a door opened without bagging), a Health Physics representative must be contacted.
1 4.8.2.4 Explosive or flammable material must not be taken into glove box.
t 4.8.2.5 An open flame cannot be used in the glove box without prior Health Physics approval.
4.8.2.6 Material which could produce fumes which could damage the glove box filter or containment seals must not be taken into the glove box.
4.8.2.7 Disposable gloves must be worn when inserting hands into the glove box gloves and when
't j performing bagging operations. Gloved hands must be checked with the alpha contamination monitor (or beta-gamma monitor, where appropriate) whenever removed from the glove box ;
gloves.
{
4.8.2.8 Upon loss of a glove, or containment in any manner, or upon detecting contamination, notify the Health Physics Department immediately.
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! Radiatica Safsty Ccde & T TELED(NE Quality Control Manual BROWN ENGINEERING Environmental Services 111-4. 9 Waste Management !
In addition to the Radioactive Waste Procedures in Section II, additional waste management I procedures are to be used for Precious Metals radwaste. i J
When bagging out the waste from the glove box, extreme care should be taken when transferring the waste to the radwaste container to ensure the poly liner does not rupture or tear. A respirator, shoe covers, lab coat and gloves are to be wom during this process. Immediately seal the radwaste container and make no attempt at compressing or compacting the poly liners as this could rupture the bag and release rirbome contamination.
Form IWL-FM-01 will be attached to each container on which the following is listed:
- 1) Lot Numbers
- 2) Isotopes
- 3) Quantities l
- 4) Concentrations l
- 5) Dates i gs 6) Physical forms
( 7) Chemical forms All by-products from the chemical processes will be stored in the U.S. DOT approved containers provided by TBE-ES and segregated from all other materials. These containers shall be removed by TBE-ES waste disposal personnel and transferred to TBE-ES . At TBE-ES these materials will be analyzed and l properly disposed or re-used. Please note that the reason that the materials are not disposed as radioactive I waste is that they are usually recyclable.
111-4.1 0 Decontamination Guidelines The release of equipment and/or materials for unrestricted use will be in accordance with Appendix A of the NRC's " Guidelines for the Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or TennMation of Licenses for Byproduct, Source or Special Nuclear Materials", latest issue.
Version 3.0 November 27,1996 Page 111/4-11
i Radiaticn Safsty Code & L NE R ENGINEERING l Quality Control Manual Environmental Services
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fil-4.11a Isotope Possession Lirnits - License 29-00055-15 I
A. Forpossession and use at 50 Van Buren Avenue, Westwood, NJ:
1 Element & Mass No. Chemical & Maximum Possession Limits Physical Forms Item 6 (a) Any By-Product material Item 7 (a) Any Its i.8 (a) No single nuclide to (73-Z83) exceed one millicurie and 1 25 millicuries total (b) AnyTransuranicisotope (b) Any (b) No single nuclide to (Z93 and higher, excluding exceed one millicurie and '
plutonium) 25 millicuries total B. For possession and use at 3901 South Clinton Avenue, South Plainfield, NJ:
1/100th of the limitc la ine above table.
l l p lil-4.11b isotope Possession Lirnits - License SNM-107 (This is a subset of the SNM-107 Isotope Possession U Limits found in Section 111-3)
Forpossession and use at 3901 South Clinton Avenue, South Plainfield, NJ:
l Element & Mass No. Chemical & Maximum Possession Limits Physical Forms l Item 6 (s1 U-235 Item 7 (a) Any item 8 (a) 1 gram (2.0 x10-3 mci)
(b) Pu-238 (b) Any (b) 0.00006 gram (1.0 x10-2 mci)
(c) Pu 239 (c) Any (c) 0.01 gram (6.0 x10-1 mci) i (d) Any other SNM not (d) Any (d) 0.01 gram detailed above I
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Radicti:n Safety C de & TTELEEWNE Quality Control Manual BROWN ENGINEERING Environmental Services (3
- ] 111-4.1 2 Disposal to the Sanitary Sewer Disposal of any liquids generated under this license will be done in accordance with the provisions of 10CFR Part 20.2003. As there is only one source of liquid under this license (an enclosed water scrubber) and no planned discharges, there is no current data on the solubility of the materials in the water. Upon request to discharge, the Manager of the Precious Metals Decontamination Lab will determine the solubility of the contaminants using a method approved in Information Notice 94-07 or by another suitable methodology. "Ihis written evaluation must be presented to the Radiation Safety Committee for approval. Any variation on an approved method must be submitted to the U.S. NRC for approval prior to the release.
111-4.1 3 Transfer of Materialfrom TBE-ES to Degussa Prior to release from the TBE-ES facility, each precious metals-lead button is monitored in the following manner. Sample drillings are taken and analyzed for gross alpha and gross beta activity. Maximum activity acceptable activity levels are less than 20 dpm per gram. In addition, the entire surface of the button is surveyed with a Eberline Instruments PAC-4G gas flow proportional surycy meter and must no have any discemible activity above background. The buttons are then smeared and each smear is counted to determine removable surface activity. These levels will not exceed 20 dpm/100cm2, Each shipment to Degussa would be comprised of approximately eight (8) lead platinum buttons i 1
weighing about 6 kg each. The ratio of Lead: Platinum is approximately 5:1 which results in approximately 42 j kg of lead and 8 kg of platinum. The residual radior.ctive contaminants that were not removed by the TBE-ES l processing a e homogeneously dispersed in a mass of roughly 50 kg of metal.
111 4.14 Release of Processed Material from Degussa TBE-ES will assay the final precious metals product for compliance with the Releasability Criteria shown below prior to unrestricted release by the Degussa Corpornion. i Dunng possession by the Degussa Corporation, all precious metal.s received from TBE-ES pursuant to
- the license will be segregated from all other precious metals at the facility.
l The below Releasability Criteria are based on contract specifications by the U.S. Department of Energy.
Limits for Alpha: 0.10 dpm/cm 2at a t 95% confidence level.
Limits for Beta: 0.40 dpm/cm 2at a 95% confidence level.
Limits for Gamma: The count rate for 50 grams of material distributed over the face of a Nal crystal shall not exceed 10% above virgin material at 95% confidence level.
O(./
Version 5.0 November 27,1996 Page 111/4-13
Radiation Safety Cede & T TELEW NE Quality Control Manual BROWN ENGINEERING Environmental Services
( \
b/ PM RADWASTE FORM Manifest Number:
Drum Identification:
IrtNumbers Isotope mci Concentration Date Physical Form Chemical Form 4
O l
1 IWL-FM-01 O
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I Radiation Saf:7 Code & T TELEDYNE Quality Control Manual BROWN ENGINEERING Environmental Services 29-00055-15 LICENSED ACTIVITIES EXAM .
l Multiple Choice l
- 1. hwrs of on-the-job training are required to satisfy the training requirements.
- a. 20 j
)
- b. 40
- c. 60
- d. 80
- 2. 'Ihe Precious Metals area is surveyed on a basis.
- a. daily
- b. weekly
- c. monthly j
- d. quarterly I l
- 3. Benches, floors, sinks and chairs are surveyed for fixed and contamination. l
- a. removable '
b, direct
- c. radioactive
- d. hot
- 4. A is used to determine general radiation levels in the laboratory.
- a. PAC-4G
- b. PAC-4G-3
- c. M S-2
- d. E-120 GM
- 5. Items found in excess of of the limits for contamination wih be decontaminated as soon as practicable.
- a. 10 %
- b. 25 %
- c. 50 %
- d. 100 %
- 6. A generel survey of the entire TBE-ES facility is performed
- a. daily
- b. weekly
- c. monthly
- d. quarterly
- 7. The limit established for removable alpha activity is
- a. 20 dpm/100cm2
- b. 50dpm/100cm2
- c. 100 dpm/100cm2
- d. 200 dpm/100cm2
- 8. The limit established for removable beta-gamma activity is
- a. 100 dpm/100cm2
- b. 500dpm/100cm2
/ c. 1000 dpm/100cm2
- d. 2000 dpm/100cm2 IWL-FM-02
I t
Radiation Safety Code &
ThyN ENGINEERING
, Quality Control Manual Environmental Services
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(> 9. Air sampling of breathing zone and effluent air is done
- a. sporadically
- b. occasionally
- c. when required
- d. continuously
- 10. The HEPA filters have a rating of efficiency against D.O.P. smoke to 0.3 nderons. <
- a. 9.99 %
- b. 99.9 % l
- c. 99.997%
- d. 100 %
i
- 11. Air flow characteristics on hood and glove boxes are done on a basis. {
- a. daily '
- b. weekly
- c. monthly
- d. quarterly
- 12. Respirators will be fit-tested using .
- a. DOP smoke
- b. amyl acetate
- c. benzol acetate
- d. irritant smoke IWL-FM-02 i
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4 Radiati:n Safsty Cod: &
TgQNpNGINEEAING Quality Control Manual Environmental Services i Ov 13. The doors between laboratories should be l to ensure proper air flow.
I a. open i
- b. closed
- c. blocked
- d. none of the above l 14. Hoods should not be moved above the Ifm mark.
- a. 50
- b. 100
- c. 110
- d. 150
- 15. Donot use substances in hoods.
- a. explosive
- b. acidic
- c. corrosive
- d. all of the above
- 16. of the materials to be used in the glove box must be bagged out.
- a. all
- b. most C. some
- d. none
- 17. Compressing or compacting of waste i ,
- a. is allowed
- b. can be done with HP approval
- c. mustnever be done +
- d. none of the above True or False
- 18. A respirator, shoe covers, lab coat and gloves must be worn at all times.
- 19. A form must be attached to each waste drum listing lot numbers, isotopes, quantities, concentration, dates, etc.
- 20. Physical and chemical forms are also required on the form to be attached to each waste container. _ _ _ _ __
TEST DATE:
TAKEN BY:
REVIEW WITH EXAMINER ON:
l EXAMINER:
t i-3 SCORE:
I k-i
d l Radiation Saft*Y Code & T TELENNE Quality Control Manual BROWN ENGINEERING Environmental Services ANSWERS TO IWL-FM-02
- 1. d 11, c l
3 2. b 12. d 1
- 3. a 13. b
- 4. d 14. b l 5. c 15. d
- 6. c 16. a r 1
- 7. d 17. c j
- 8. c 18. False
- 9. d 19. Tme
- 10. b 20. Tme d
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