ML20210D556
| ML20210D556 | |
| Person / Time | |
|---|---|
| Site: | 07000008 |
| Issue date: | 05/25/1999 |
| From: | Mccann G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| References | |
| 304830, NUDOCS 9907270273 | |
| Download: ML20210D556 (200) | |
Text
l u NUCLEAR RE!fA.ATORY COMMISslON MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10 Code of Federal Regulatione, Chapter 1, Parts 30. 31, 32, 33, 34, 35, 36, 39, 40, and 76, and in reLance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nucioar material d%ignated below; te use such material for the purpose (s) and Gt the place (s) designated below; to deliveror tra,'sfer such material to persons authorized to receive it in accordance with the regulations of the applicable Purt(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as armded, and is subject to all applicable rules, regulations, and orders of the iJuclear Regulatory Commission now or hereafter WW :t anno any conditions specified Licen*
In accordance with the letter dated January 11,1999,
- 1. Bittelle MemorialInstitute 3. Ucense number SNM-7 is amended in Battelle Columbus Operation its entirety to read as follows:
- 2. 505 King Avenue 4. Expiration dcte April 30,1988 (on timely renewal)
Columbus, OH 43201-2693 gg R E q No. 070-00008
,y Referen[e g.
S. Byproduct, source, and/or special nuclear material g[7. Chemical and/or physicalMaximum form ssess amount that licensee may at any one time under this
., a cense West Jefferson Site e ,
. . - O i A. Uranium enriched in%e U-235 isotope -IrradiEted A.p 4
,%n.
tQ is A. 025 grams of contained dA235 plus the associated j
F .. (X '
d). M '3'"d unseparated plutonium 50,ams-eteieee B. Uranium enriched in 50e l j/ B. 9 U-235 isotone - Unirragted . ,e eU-235
~
C. Uranium enriched in theO ~ S C.D 1 gram total of U-235 U-235 isotope - Unirradia D. Plutonium (any principal DJ An Q[' b[D. 0.1 gram total isotope Pu-236-244) %y %
E. Plutonium (Pu-238 principal E. Solid Oxi5e', with multiple E. 10.3 grams isotope) )
containments F. Plutonium (Pu-239 principal isotope)
F. Solid Metal or Oxide, with multiple containments F. 17.0 grams h1 I G Neptunium-237 G. Sealed Source G. 1.0 microcurie
/ !
H. Plutonium (Pu-238 princ:ple I H. PuBe Source H. 0.053 grams !
isotope) i 1. Plutonium (PU-238 principal 1. Solid Scrap l. 3.4 grams
) isotope) l J. Plutonium (Pu-239 principal J. Solid Scrap J. 3.0 grams isotope)
I J Q i
9907270273 990525
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s'DR E ADOCK 07000008 PDR f1 d
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NRC FORM 374A u.S. NUCLEM REIULAToRY CoMMISSloN
~
PAGE 2 d 9 PAGES Uonnse Number SNM-7 MATERIALS LICENSE W or Reference Nurnber SUPPLEMENTARY SHEET 070-00008 Amendment No.17
- 6. Byproduct. source, and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material possess at any one time under this I! cense K. Uranium-232 K. Any K. 0.99 grams L. Uranium-233 L. Any L. 0.99 grams M. Uranium-234 M. Any M. 0.99 gram N. Uranium-235 N. yg REGg N. 0.99 grams O. Plutonium-236 Oy Any d 0.04 micrograms 0 4 >O.
P. Plutonium-238 U P. Any 6 0.6 micrograms O. Plutonium-239 , Any Q@. A 82.0 micrograms R. Plutonium-240 f.O ny ) R. g2.0 micrograms I S. Plutonium-242
<C S. -
n
/P ,
he Y.. .t S. Q.4 micrograms
' 7 T. Any byproduct material j th.4
/ ,T. 9,000 curies total, not g) eI ' [Mtenal's'/); Enore than 5,000 curies of f $db dd# l' / eny one radioisotope
(> M(excluding items 6.M.
@ e pg' 4 ~
- .. 4 through 6.BB.)
U. Hydrogen-3 Y ,
? %
Any 4*J~L f), ' t). 500 curies V. Polonium-210 /,k@U. 4(V. 50,000 curies total, not Mgny g more than 5,000 curies of any one radioisotope (excluding items 6.M.
through 6.BB.)
I W. Califomium-252 W. Any W. 500 curies X. Sulfur-35 X. Gas X. 1,000 curies Y. Chlorine-36 Y. Gas Y. 1,000 curies Z. lodine-131 Z. Any Z. 1,000 curies AA. lodine-129 AA. Any AA. 60 curies BB. Cobalt-60 BB. Any BB. 5,000 curies CC. Cesium-137 CC. Any CC. 5,000 curies b
NPC FORM 374A u.S. NuCLERK REGULATORY CoMMISSloN " 1 PAGE 3 of 9 PAGES j Umnae Number i
SNM-7 MATERIALS LICENSE W or Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.17
- 6. Byproduct, source, and/or special T. Chemical and/or physical form 8. Maximum amount thatlicensee may I nuclear material possess at any one time under'.his license DD. Strontium-90 DD. Any DD. 5,000 curies EE. Carbon-14 EE. Any EE. 2 curies FF. Krypton-85 FF. Gas FF. 500 millicuries GG. Americium-241 GG yg GG. 10 millicuries R E e fj HH. Nicket-63 HS. Any d 0 4 h HH. 600 millicuries II. Any byproduct material D 11. Any Y @* 100 millicuries total not to g T4 ((
- p /exceed radionuclide 10 millicuries per Kino Avenue Site D "O ' v
': P O
}
i g i JJ. Uranium (enriched iq,the J ua g;.7,, gt mi JJ. micrograms of contained U-235 isotope,irrad%ed) ,
,, -235 plus the associated
, gy' Ig[,'e ety gnd unseparated plutonium l <- Jind mixed fission products KK. Any byproduct materk M g4 -
[Q' KKbD than-500 curies total, nct more 35 curies of any one f I l,, 4
[ radioisotope West Jefferson and King Avenue Y Slies LL. Any Source Meterial
/)
LL.
kAnywr **M-LL. 50 kilograms Temporary Job sites MM. Nickel-63 MM. Sealed source registe red MM. 600 millicurns total. No pursuant to 10 CFR 32.210 single source to exceed and incorporated into gas 40 millicuries.
chromatograph and/or aerosol /airbome contaminant gas acd vapor detector as specified in item 10.
o V/ ;
1
NRC FORM 374A U.s. NUCLEAR flElulAToRY CoMMISSloN PAGE 4 of 9 PAGES Ucense Number SNM-7 MATERIALS LICENSE W w Refwence Nunta SUPPLEMENTARY SHEET 070-00008 Amendment No.17
- 6. Byproduct, source, and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material possess at any one time under this hcense NN. Americium-241 NN. Sealed source registered NN. 500 millicuries total. No pursuant to 10 CFR 32.210 single source to exceed and incorporated into gas 50 millicuries.
chromatograph and/or aerosol /airbome congminpq1tgagand vapor 8
gV 6 etector ltem 10. as specnich'ir{ 4 ,
j
- 00. Hydrogen-3 D 00. Titanium tritide source 60. 3 curies total. No single I registered pursuant to source to exceed e @4 200 Q % millicuries.
id F.-
._.Q)corporaje(into,g 10 CFR 32.210 ; g and q %g. .J0,matographqanr,osoll O irbope % 4 l !!
, U) gQ b. 1 9 9 <fll' ;n 5 j
- g L i ,
t l PP. Americium-241 O eak (clt Ikigt,.e PP.U400 millicuries total. I to j M 4 single source to exceeJ l V a iiuah O'dFR42.$10 N incor [
gaugin%po'Sted irit$f 100 millicuries.
'Jf
/
O vides as pecified in item 10 l
QQ. Cesium-137 QQ. eah i ed QQ. 200 millicuries total. No i pursuant to 10 CFR 32.210 single source to exceed ard incorporated into 50 millicuries.
l gauging devices as specified in item 10.
n l RR. Americium-241 RR. Sealed source (CPN Model RR. One source not to exceed No.131) 50 millicuries PY
NRC FORM 374A u.S. NUCLEAR RLGulAToRY CoMMISSloN PAGE O of 9 PAGES t
Ucense Number
'. SNM-7 MATERIALS LICENSE dom or Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.17
- 9. Authorized places of use:
A. Licensed materials may be used in buildings and facilities approved by the licensee's Radiation Safety Committee, at sites indicated above under items 6,7, and 8. The licensee will submit final e,tatus surveys for buildings or areas which are to be released for unrestricted use via a license amendment.
B. Licensed materials listed in Subitems MM., NN.,00., PP., QQ. and RR. may be used at temporary job sites of the licensee anywhere in the UniLed States where the U.S. Nuclear Regulatory Commission maintains jurisdicti fKr@ulatfng@iGsgof licensed material. These items may be stored when not in use at the see's King and West Jdfegon sites. The possession of these devices are in addition to d6yi s authorized under Subitem KKp,
.D O g V .. _N CONDITIONS t eg' /
- 10. Authorized use:
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Q A. For use in accordaIce with sta . monts s in'd conditions 3ontained in the following
'~
portions of the licdnsee's a m October 23,1981,UBKeept bitio'fnts 1081gubmitted by letter dated p / %f thistidense:
- ==
- 1. Pages vi throuh xi, I ni U
- 2. Part I, License (Nnditi - ,
D
- 3. Appendix A, RadI6ipgical Safe C hatte ; and \
- 4. Letters dated June 2$1994, Augus 9.,994, July 6,1 excluding item 1), and August 3, 1995 (excluding item 1)?
B. The principal use for items A. and u r d3os 7, and 8, are as residual contamination in the Hot Cells of the West Jefferson Facility Building JN-1.
C. The principal uses for item LL. under Conditions 6. 7, and 8 are use as residual contamination at BMI's King Avenue and West Jefferson facilities, and as sealed source shielding.
D. Item H. under Conditions 6,7, and 8 has been transferred to the license from DOE inventory to be used for calibration.
E. Items K. through S. are for research and development, and support of Radiological Laboratory Operation as described in letters dated November 17,1994, March 21,1995, and October 20,1997.
t F. Item FF. is for storage only pending disposal.
-x1 I
MtC FORM 374A N s. NUCLEAR REIULAToRY COMMisSloN PAGE 6 of 9 PAGES Uconee Number SNM-7 M
~ ATERIALS LICENSE DocM w RWm Number SUPPLE'AENTARY SHEET 070-00008 Amendment No.17 G. Items GG., HH., and 11. are for research and development activities as described in letters dated June 29,1994, August 19,1994, and March 21,1995.
H. Item RR. is for us a in a Campbell Pacific Nuclear Model 503 portable moisture / density gauge,
- l. Item EE. is to bc used for research and development as described in 10 CFR 30.4.
J. Items MM. through OO. of items 6,7, and 8 are for use in compatible gas chromatograph devices and or aerosol /airbome contaminant gas an(vapor devices which have been registered pursuant to 10 CFR 32.210 and distributed in agjoSanMvdth e C or Agreement State specific license to k
persons specifically licensed tg eNRC to receive, po ss nd use the devices.
G >
K. Items PP. through RR. Nfor use in ccmpatible moisture / density @auges which have been registered pursuant tolb CFR 32.210 and distributed in acco opwith an NRC or Agreement State specific licensgjo ^ - Ily licensed by R'Cto dceive, possess and use the devices. ai ,*
M
- 11. The Radiation Safety Ugn:er for thi is C(alg E. dk , O
- 12. Notwithstanding Tablelitt and E
p"s 3.4 and).5, for the release of materials, equipment, Md fa i, --
Thall amere to the provisions of the L
NRC's " Guidelines for n o : ip i'rior t elease for Unrestricted Use of Termination of Licen or ,
ar M I," dated April 1993.
- 13. Item 10 above incorporatesMn x A d afehomm' harter)of thelicensee's renewal application (BCL-1081ps a condition nse lo ci nd define more fully cdministrative procedures for revi&, roval and audit of ivit covered by the license, as described in Section 1.3 and Section fgrt1 Th may make revisions to the provisions of Appendix A, based upon written evaluation 5 th a s, without NRC approval if it is determined that such changes will not decrease the effectiveness of the Committee in carrying out its functions.
Revisions to the Charter and supporting evaluations shall be submitted to the Director, Division of Fuel Cycle Safety and Safeguards, NRC, with a copy to the Administrator, Region lli Office, NRC, within 60 days following such changes.
- 14. In addition to the subjects identified in Section 5.1.1, Appendix A, the annual review and appraisal of freilities shall include an assessment of occupational radiation exposures and releases of radioactive j material over the past year with regard to maintaining such exposures and releases as low as is '
reasonably achievable, as stated in 10 CFR 20.1101.
- 15. Sactions 2.1 and 3s10, Part I refer to provisions for training and periodic retraining of employees, as cppropriate and related to employee work assignments with radioactive and fissionable materials. Such training shall be conducted, as appropriate, for new employees and prior to initiating new operations cpproved by the Radiological Safety Committee aro ' mining shall be conducted on topics appropriate to employee work assignments at least annually. Dc anontation of such training and retraining shall be maintained.
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i NRC FORM 374A u.S. NUCLEA RE!uLAToRY Commission PAGE 7 of 9 PAGEs Ucense Number SNM-7 MATERIALS LICENSE oxw or Rer.r.nc. Number SUPPLEMENTARY SHEET 070-00008 Amendment No.17
- 16. Section 5.0, Part 1, of the licensee's renewal application incorporates the text of previous amenoments issued by NRC to Special Nuclear Material License No. SNM-7 and Byproduct Materials License No.
34-06854-05 covering decontamination and decommissioning plans applicable to the Battelle Hot Cell Laboratory. It is hereby affirmed that the provisions to these decontamination and decommissioning plans, including financial arrangements, continue in effect under this renewed license, and also apply to the retired Battelle Research Reactor.
- 17. At such time that facilities' covered by this license are decontaminated for proposed unrestricted release (in accordance with Annex C), the licensee shally,ubmit a report that identifies the facilities where radioactive mater als were used and Js ogd,Sr ditipofeGrge site. The report shall briefly describe operations conducted and radioac(ivsmaterials used in theTadlijti s and shall assess the results of the decontamination activities. TheGeport shall provide the basis for anpestricted release of the facilities and the site, including a descrip i of sampling and survey methods and (ptrumentation used, and shall include final contamination tve data for the facilities and grounJs ,Tt)b licensee may segment the report to obtain release prth ' s of facilities or individuarstqictures'.if it is demonstrated that ongoing activities in othg areas ' lead to recontam atibak the area or structure proposed for release.
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- 18. Notwithstanding the poIessio lim in nd 8, the lignsee is authorized to Rio ^
possess as residual cdntaminat ' Tifs irradiated spent fuel. y) ;. 16 micorgrp= s of SNM contained in
- 19. Moisture density guages@ tai sed ; e used $9, or under the supervision End in the physical prese of, j), fE ve.' the trainid9 described in letters dated June 29,1994 and August $1994, or th inamTa'cturer o %rsons licensed to provide such training, and have been approv$d in writing by ,N iation safet icer.
Q
- 20. When performing tests at temporary it4the ut ser shall not leave the moisture / density gauge unattended. Upon completion o tedth vi hall be locked in the licensee's vehicle or a secure bui! ding to prevent unauthorized use, loss, or theft.
- 21. The licensee is authorized to transport the portable moisture / density gauge only in accordance with the j provisions of 10 CFR Part 71, " Packaging and Transportation of Radioactive Material." 1 l 22. Each portable nuclear gauge shall have a lock or outer locked container designed to prevent ur tuthorized or accidental removal of the sealed s Ice from its shielded position. The gauge or its coniainer must be locked when in transport, storage, or when not under the direct surveillance of an cuthorized user.
- 23. Sealed byproduct material sources shall be subject to the leak testing and actions specified in the licensee's procedure titled " License Condition for Leak Testing Sealed Byproduct Material Sources,"
dated April 1993. Sealed plutonium sources shall be subject to the leak testing and actions specified in the licensee's procedure titled " License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993.
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NRc FORM 374A u.S. NUCLEAR REIULAToRY COMMISSION PAGE 8 of 9 PAGEs Ucense Number SNM-7 MATERIALS LICENSE W r Reference Number SUPPLEMENTARY SHEET 070 4 0008 Amendment No.17
- 24. A. I Sealed sources and detector cells shall be tested for leakage and/or contamination at intervals not to exceed 6 months or at such other intervals as specified by the certificate of registration referred to in 10 CFR 32.210. ,
J B. Notwithstanding Paragraph A of this Condition, sealed sources designed to emit alpha particles I shall be tested for leakage and/or contamination at intervals not to exceed 3 months.
C. In the absence of a certificate from a transferor indicating that a leak test has been made within 6 months prior to the transfer, a sealed sour received from another person shall not be put into use until tested. gR egg -
D. Each sealed source fabric 4phy the licensee shall be inspeit9 d and tested for construction defects, leakage, and mination prior to any use or transfer q sealed source.
E. Sealed sources neegjiot leak tested if: .4 y
(i) they contain ly hydrog r .y O m ,,. r z. o (ii) they contain ly a radio 'as; orku g (iii) the half-life anhe is ci I '$. E p y (iv) they contain n ore or gamr$ emitting material or not more than 10 m ocun y ohtaa 4 (v) they arenenot desig&@o ~
EO) emitandalpha pa}'rt,i. &. die are not being used.
However, when they arOem ved from storage f s, are in'stor[ transferred to another p se or have not been tested with! rqgirje leap .erval, they shall be tested before use or transfer. No sealed source or dSctop Eli small be stored for a period of more than 10 years ;
without being tested for leakage and/or contamination. j l
F. The leak test shall be capable of detecting the presence of 0.005 microcuries of radioactive material !
on the test sample, if the test reveals the presence of 0.005 microcuries or more of removable contamination, a report shall be filed with the U.S. Nuclear Regulatory Commission in accordance ]
l with 10 CFR 30.50(b)(2), and the source shall be removed immediately from service and decontaminated, repaired, or disposed of in accordance with Commission regulations. The report l I
shall be filed within 5 days of the date the leak test result is known with the U.S. Nuclear Regulatory i Commission, Region Ill,801 Warrenville Road, Lisle, IL 60532, ATTN.: Director, Division of Nuclear !
Materials Safety. The report shall specify the source involved, the test results, and corrective action 1 taken. l G. Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically licensed by the Commission or an Agreement State to perform such services.
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NRC FORM 374A U.S. NUCLEAR CEIULAToRY COMMISSION PAGE 9 of 9 PAGEs Ucaise Number )
SNM-7 l MATERIALS LICENSE D det r Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.17 i
- 25. Except as specifically provided otherwise in this license, the licensee shall conduct its program in {
cccordance with the statements, representations, and procedures contained in the documents, including any enclosures, listed below. The U.S. Nuclear Regulatory Commission's regulations shall govern unless the statements, representations, and procedures in the licensee's application and j correspondence are more restrictive than the regulations.
A. Letters dated October 11,1995 (with attachments), September 29,1997, two letters dated 1 October 20,1997 December 24,1997, December 30,1997, September 15,1998, January i t, f 1999, January 26,1999, February 5,1999, F bruary 26,1999, April 12,1999, May 14,1999, and May 21,1999. gR egg 0 4A D O Y ._._ ,@
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- : INFORMATION FROM LTS EEMEEN:
- O License Fee Management Eranch, AFM $ Frogram Code: 21130 and Status Code: 2 Pegional Licensing Secticns : Fee Category: 14 ID JL 3P 30 2B
- Exp. Date: 19880430 0 : Fee Comments: REG TO DEL 30/25 9/1/94
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Q !. APPLICATION ATTACHED Applicant / Licensee: FATTELLE COLUMBUS DIVISION d
Received Date: 19990115 0 :S 1- L Docket No: 7000008 '--
O Controt No.: 304830 f '~
i License No.: SNM-7 / / k 9 Action Type: Amendment v L' Q 2. FEE ATTACHED Amount:
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o__,. o OBallelle Patting 7ec knology To Mbik 505 King Avenue Columbus, Ohio 43201-2693 -
Telephone (614) 424-6424 f acsimile (614) 424-5263 January 11,1999 Mr. Michael Weber U.S. Nuclear Regulatory Commission Region III 801 Warrensville Road Lisle,IL 60532-4351 j i
Dear Mr. Weber:
)
Requestfor Amendment to Materials License No. SNM-7, Docket 70-8 and Byproduct Materials License 34-26608-01 Battelle Memorial Institute (BMI) requests an amendment to the Byproduct Materials License SNM-7 and Byproduct Materials License 34-26608-01, for the addition of:
Special Use laboratories processing 100 mci or more of unsealed byproduct radioactive materials per experiment or process and, Iodination Laboratories which will label using 10 mci or more of radioactive iodine isotope (s) per experiment or process at one time, at our King Avenue Facility, specifically, Building 7C, rooms 329 and 340 as Special Use Laboratories, and Building 7C, room 341 as a Special Use and Iodination Laboratory. Laboratory facility specifies are provided in Attachment I.
Characterization of the fume hoods located in these laboratories was conducted on September 13,1995. The inspection results are provided as Attachment II.
Specifics regarding the types ofIodinations and the required experience and training to perform these iodinations in a Special Use Laboratory are located in Attachment Ill. Operational commitments are also provided in Attachment 111.
BMI requests the NRC grant the Radiation Safety Officer (RSO) and Radiation Safety Committee (RSC) l the ability to establish future Special Use and lodination Laboratories at our King Avenue and West i Jefferson facilities, as identified above, without prior NRC notification. RSO and RSC review and approval of new Special Use and lodination Laboratories will be conducted as specified in Battelle's 1994 Type A Broadscope Application and subsequent NRC correspondence regarding RSO and RSC Safety Evaluations and approvals for possession, use and storage of radioactive materials.
Documentation regarding the RSC review and approval will be maintained on file for NRC review. j RECEIVED
/
4;y- 7 g j_.//__cp[ JAN 151999 gEoMWsifia 3 0+ K30
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. ' Mr. Michael Weber 2 January 11,1999 BMI also requests an amendment to the Byproduct Materials License SNM-7 and Byproduct Materials j License 34-26608-01 to' authorize the storage and use of radioactive materials at BMI's King Avenue Campus, Building 3 for Research aad Development. Building 3 was previously licensed by the NRC for use and storage of radioactive materials but, at BMI's request, was removed from the license following completion of D&D activities. The addition of Building 3 to the license will not affect the current licensed possession limits, nor will it change Battelle's required financial assurance as specified in 10 l CFR 30.35. BMI's future Research and Development business projections require the ability to use and store radioactive materials in this building.
If you have any questions, please do not hesitate to call me at (614) 424-3885, or my Assistant RSO, Craig Jensen at (614) 424-5170.
I Sincerely, I l y Stephen J. Layendecker, CHP !
l
- Safety llealth and Environmental l Support Manager / Radiation Safety Officer l
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ATTACliMENT I The following are laboratory descriptions and specifications for labs 7C-329,7C-340 and 7C-341 Lab 7C-329 7C-329 is an animal housing laboratory located at the building 7C northwest corner, third floor.
The laboratory contains a free-standing Stainless Steel IIEPA-filtered exhaust unit. The IIEPA-filtered exhaust is directed to the liVAC exhaust system. Portions of the IIVAC system are exhausted to the environment and/or redirected into the Iluilding supply ventilation. The amount of redirection is based on the 13uilding ventilation flow balance.
The laboratory is smoke-tested prior to initial animal housing to ensme ventilation flows into the laboratory. The air changeout rate in the laboratory is approximately 10 room volumes per hour.
IiEPA filter and system testing are conducted in accordance with the attached Table 1.
Information presented in Table 1 is adapted from ANSI /ASME N510.
The floor is painted with an epoxy covering. A six-inch lip is installed on the floor edges to contain liquids. Gutters are installed on the east and west walls to contain and direct liquids. The lab contains three drains which drain to a common header. This header drains to the city sanitary sewer system. Operations involving radioactive materials require these drains be sealed or a discharge permit be approved in accordance with 10 CFR 20.2003 prior to discharge.
Lab 7C-340 7C-340 is located north of 7C-329 and is connected to lab 7C-341 via a removed wall.
The lab contains three exhaust vents. These exhaust vents are shut during radioactive material use. Exhaust ventilation is maintained by the fume hood negative ventilation located in lab 7C-341.
The floor is painted with an epoxy covering. A six-inch lip is installed on the floor edges to contain liquids. The lab contains three drains which drain to a common header. This header drains to the city sanitary sewer system. Operations involving radioactive materials require these drains be sealed or a discharge permit be approved in accordance with 10 CFR 20.2003 prior to discharge.
The laboratory is smoke-tested prior to use to ensure ventilation flows into the laboratory. The air changeout rate in the laboratory is approximately 10 room volumes per hour.
I I
)- .
Lab 7C-341
-- 7C-341 is located northwest of 7C-329 and is connected to lab 7C-340 via a removed wall.
The lab contains three exhaust vents. These exhaust vents are shut during radioactive material use. Exhaust ventilation is maintained by the fume hood negative ventilation.
The floor is painted with an epoxy covering. A six-inch lip is installed on the floor edges to contain liquids. The lab contains three drains which drain to a common header. This header drains to the city sanitary sewer system. Operations involving radioactive materials require these drains be sealed or a discharge permit be approved in accordance with 10 CFR 20.2003 prior to discharge.
The laboratory contains an installed operational fume hood. The fume hood exhausts to the outside environment through a HEPA- and charcoal-filtered exhaust train. This filter train is located on the roof of Building 7C. The fume hood exhausts to the outside environment.
The laboratory is smoke-tested prior to use to ensure ventilation flows into the laboratory. The air changeout rate in the laboratory is approximately 10 room volumes per hour.
Filter and system testing are conducted in accordance with the attached Table 1. Information presented in Table 1 is adapted from ANSI /ASME N510.
The fume hood has an installed magnehelic gauge with alarm to identify hood failure due to difTerential pressure.
l i
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O TA8's i O Test and Minimum Test Frequency (1)
Adapted from ANSI /ASME N510 Test Recommended Test Frequency VisualInspection Before any test Duct and housing leak test Acceptance (2)
Mounting frame pressure leak test Acceptance (2)
Airflow capacity, distribution and Acceptance (2) residence time tests Air-aerosol mixing uniformity test Acceptance (2)
In-place leak test, HEPA filters Acceptance, after each filter change, and at least every two years (2,3,5) l In-place leak test, absorbers Acceptance, after each adsorber change j and at least every two years (2,3,4,5) !
Laboratory testing of adsorbent Acceptance, before each adsorber change and at least every two years 1 (2,3,4,5) l Duct heater performance test Acceptance and at 2-year intervals (1)
In-place tests, moisture separators Not required In-place tests, prefilters Not required NOTES: (1) Field tests of motors, valve and damper actuators, and fire protective systems are not included in this standard.
(2) Acceptance tests to be made after completion ofinitial construction and after any major system modification or repair.
(3) More frequent (e.g.,6 months) testing rnay be required following initial start-up of the system until a pattern is l established. Tests can often be made without shutting down the entire air cleaning system if proper facilities for test
({g., prelocated aerosol injection and test ports) are provided.
(4) Adsorbents must be tested before installation or replacement of absorbers to establish suitability. Samples for l laboratory testing should be taken from the system at the same time as routine in-place testing of the installed system to verify the condition of the adsorber.t.
l (5) Periodic in-place leak tests of cells from 100% recirculation systems located within laboratories are not necessary if i the following are complied with:
! a. Periodic visual inspection and pressure-drop determination in accordance with this standard ofilEPA filters and absorbers are made every two years.
- b. IIEPA filters are replaced at no more than five-year intervals if dirt build-up, pressure-drop increase, or mechanical damage has not required earlier replacensent;
- c. Adsorbent is sampled and laboratory tests made to confirm performance every two years or at intervals not exceeding 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation for intermittently operated systems or for any system immediately following inadvertent exposure to solvent, paints, or other organic fumes or vapors which could degrade the performance of the adsorbent.
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NUCON Internationol, Inc. TELEPHONE: (614) 846-5710 OUTSIDE OHIO: 1-800-992 5192
-P.O. BOX 29151 7000 HUNTLEY ROAD TELEX: 6974415 COLUMBUS. OHIO 43229 U.S.A. FAX; (614) 4310858 e
t Characterization Study !
of Animal Resources Laboratory i Fume Hood Exhaust
, Rooftop Units j
)
located at Battelle MemorialInStitute 505 King Ave. -
Columbus, OH P.O.# 107862 DISTRIBUTION .
Battelle:(2) Mark Shumaker NUCON:(1) Master File (1) Field Senices l
1 12B986/01 l
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- On 13 September 1995, an inspection of six rooftop mounted fume hood exhaust filter units was performed by NUCON International, Inc. at the Battelle Memorial Institute in Columbus, OH. The filter units exhaust from the Ammal Resources Laboratory. Number designations for each unit correspond to the hood serviced by that unit. The inspection included both external and internal inspections of each filter housing and related components.
The Unit Summary sheets on the following pages summartze a single 61ter unit and includes blower, motor, and related filter data. Table 1 is summary of the prefilter, HEPA, and adsorber dimensions for the units spected. The comments and observations are based on the as-is conditiod of the units and contain no formal recommendations or remedial actions.
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i W l Summary of Filter Dimensions for Rooftop Units 1
Unit # Prefilter (Quantity) HEPA (Quantity) Adsorber (Quantity)
Manufacturer Model #
Model #
.40
' N/A 24" x 24" x 11 1/2"(1) N/A No mfg. or model # available Metal sides with gaskets on both sides j 341 : 23 3/8" x 23 3/8" x 17/8"(1) 24" x 24" x 11 1/2"(i upstream) 24" x 24" x 18" Flanders (2 filters /l per bank)
T-007-F-04-05-NU-51-13-GG-FUS Type 1 24" x 24" x 11 1/2"(I downstream) #2VC66F18-GG 18 Flanders T-007-0-04-05-SU-GG-F
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Unit Summary UNIT: 340 Blower - Motor Dats l Manufacturer Cincinnati Fan and Manufacturer Baldor Ventilator Co. gSF 1.5/1.15 Model No. Unknown Voltage / Phase /Hz 230-460/3/60 Amocrage/ RPM 5-2.5/1725 Insulation Class B ,
HEPA Filter Max. Amb. Temp. 40*C
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Manufacturer Unknown NEMA Des. B Model No. Unknown Dutv/ Power Factor Cont 172%
Rated Flow Unknown Frame 145T Dimensions 24" x 24" x 11 1/2" Gasket Type Both sides /Necorene Quantity 1
, . Gravity Damper a N Fan HEPA a
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y C Uru.t Summary 0
, N ' UNIT: 341.
, Blower l#4 HEPA Filter (upstream)
Manufacturer Buffalo Forge Manufacturer Flanders Size / Type 21/ MW ModelNo. T-007-F-04-05-NU-51-13-GG-FU5
, Motor Data Rated Flow 1000cfm Manufacturer Baldor Dimensions 24" x 24" x 11 1/2" bp/SF l.5/1.15 Gasket Tme Liquid seal Quantity Voltage / Phase /Hz 230-460/3/60 1
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Amperage / RPM - 5-2.5/1725 Insulation Class B #1 HEPA Filter (downstream)
Max. Amb. Temp. 40*C Manufac*arer Flanders
, NEMA Des. B Modei No. T-007-0-04-05-S U-Cont 172%
GG-F Dutv/ Power Factor _
Rated Flow 1000cfm Frame 145T Dimensions 24" x 24" x 11 1/2"
' #2 & #3 Adsorbers (upstream and downstream) Gasket Tvpe Liquid sea!
Flanders Quantity - 1 Manufacturer Model No. 2VC66F18-GG-18 #5 Pre-filter, Fumace type Rated Flow 1000cfm ' 23.375 x 23.375 x 1.875 Dimensions 24" x 24" x 18" Class 2 R7580 588R S Gasket Type Liquid seal Quantity 2 (1 per bank) a i N
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1 ATTACHMENTIII I
lodinations
- 1. Iodinations will be conducted in accordance with established protocols supplied by the Principal Investigator (P.I.). There are basically five lodination Methods which will be performed. These methods are:
A. Using iodine monochloride (ICI). This is a very gentle reagent and does not damage the molecule to be iodinated. However, its yields are low and results in low specific activity of the final preparation.
B. Using Chloramine-T (p-toluene sulphonchloramide). This is a very reactive molecule that easily iodinates molecules without the use of radiolabeled iodide.
Efficiency ofiodination can be almost 100% and result in low substitutions with very high specific activities. The chloramine-T however can damage the molecule to be iodinated because ofits strong oxidative properties. Careful control of the quantities to be used can result in a very successful and reproducible iodination.
A less stressful oxidizing agent is the use of hypochlorite instead of Chloramine-T.
Yields are slightly lower but the immunoreactivity of molecules is retained.
C. Electrolytic iodination. The molecule to be iodinated is placed in a platinum anodic vessel mixed with the radiolabeled iodide source. The ccthode consists of a platinum wire ;
separated from the anodic compartment by a semi permeable membrane. Judicious control of the iodide added and the current employed results in a slow iodination process I with no harsh chemical treatments and almost 90% efficiencies.
D. Enzymatic lodination (Iodobeads TM). This technique uses lactoperoxidase immobilized on glass beads which are capable of generating very small localized concentrations of hydrogen peroxide which in turn oxidizes iodide to a reactive species that iodinates the molecule. This gentle oxidative process causes little if any damage to the molecule however the yields by this technique tend to be low.
E. Cmdugation Labeline. This involves the use of an indirect labeling by first iodinating 3-(p-hydroxyphenyl) propionic acid N-hydroxy succinimide ester. This molecule can be ,
used to condense on to a free amino functional group of the molecule to be iodinated.
Once again on can achieve high specific activities and high yields with this method without the molecule coming in contact with a strong oxidizing environment. The major disadvantage is that the molecule is attached with a large p-hydroxyphenyl propionic acid moeity.
) n v Un
- 2. Iodinations however, will not be limited to the above methods. Since Battelle is a Research l and Development facility, future lodination Method Development studies may occur.
- 3. A Safety and ALARA Evaluation will be conducted on all Iodination and I :lination Method Development study protocols. The RSC and RSO will review all Iodination pi tocols and Safety and ALARA Evaluations. RSC and RSO approval will be granted based on license and procedural specifications. All records will be made available for NRC review.
- 4. Iodinations wEl be performed by personnel who have extensive experience and training in performing these operations. The RSO and RSC will determine what constitutes a trained individual and will approve the training and experience level of all individuals who perform Iodinations. Training will be evaluated as specified in Battelle's 1994 Type A Broadscope Application,34-26608-01, and subsequent NRC correspondence regarding RSO and RSC Safety Evaluations and approvals for possession, use and storage of radioactive materials. Personnel who do not possess the experience will be trained by an experienced person prior to performing lodinations.
Training records will be made available for NRC review.
- 5. Thyroid bioassays will be evaluated and performed in accordance with Reg Guide 8.20,
" Application of Bioassays for I-125 and I-131."
- 6. Air sampling for iodine will be performed in accordance with Reg Guide 8.25," Air Sampling in the Workplace," and NUREG-1400, " Air Sampling in the Workplace."
- 7. All lodinations will be performed in an operational fume hood which exhausts through a HEPA and activated charcoal filter. The filter trains will be tested and maintained as specified in Table 1 provided in' Attachment I.
- 8. Iodinations will be conducted in a Type III laboratory. Type III laboratory specifications are stated in the Byproduct License Application,34-26608-01.
- 9. In addition to the established protocols, ALARA reviews, and RSO and RSC review and approvals, Battelle currently maintains a mature radiation protection program with established procedures. Battelle also conducts operations as specified in Battelle's Radiation Safety Manual.
The Battelle Radiation Safety Manual has been recently revised to reflect all the operational commitments made to the NRC in Battelle's 1994 Type A Broadscope Application,34-26608-01, and subsequent NRC correspondence.
I
- . /'h
- - V - (d
Special Use Facilities Processing 100 mci or more of Unsealed Radioactive Materials per Experiment or Process.
- 1. All operations in a Special Use Laboratory will be conducted in accordance with established l protocols supplied by the Principal Investigator (P.I.).
- 2. A Safety and ALARA Evaluation will be conducted on all study protocols. The RSC and RSO will review all protocols and Safety and ALARA Evaluations. RSC and RSO approval will be granted based on license and procedural specifications. All records will be made available for NRC review.
- 3. Operations in a Special Use Laboratory will be performed by personnel who have extensive experience and training in working with these quantities of Radioactive Materials. The RSO and RSC will determine what constitutes a trained individual and will approve the training and experience level of all individuals. Training will be evaluated as specified in Battelle's 1994 Type l A Broadscope Application,34-26608-01, and subsequent NRC correspondence regarding RSO and RSC Safety Evaluations and approvals for possession, use and storage of radioactive materials. Personnel who do not possess the experience will be trained by an experienced person prior to performing operations with this amount of radioactive material. Training records will be made available for NRC review.
- 4. Air sampling will be performed in accordance with Reg Guide 8.25," Air Sampling in the !
Workplace," and NUREG-1400, " Air Sampling in the Workplace."
- 5. All operations which fall into this Special Use category will be conducted in a Type Ill laboratory. Type Ill laboratory specifications are stated in the Byproduct License Application, 34-26608-01.
- 6. In addition to the established protocols, ALARA reviews, and RSO and RSC review and approvals, Battelle currently maintains a mature radiation protection program with established procedures. Battelle also conducts operations as specified in Battelle's Radiation Safety Manual.
The Battelle Radiation Safety Manual has been recently revised to reflect all the operational commitments made to the NRC in Battelle's 1994 Type A Broadscope Application,34-26608-01, and subsequent NRC correspondence.
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601 WARRENVILLE ROAD "4 JSLE, ILUNotS 605324351
.....* GAY Z 51999 i
Craig E. Jensen Radiation Safety Officer Battelle Memoria! Institute Battelle Columbus Operations ,
505 King Avenue Columbus, OH 43201-2693
Dear Mr. Jensen:
Enclosed is Amendment No.17 to your NRC Material License No. SNM-00007 in accordance with your requests. Since your license has been revised in its entirety, and encompasses several programmatic changes, please review the enclosed document carefully and be sure that you understand all conditions.
Should you have any questions regarding your license amendment, please do not hesitate to contact me at (630) 829-9856 Sincerely, a e George M. McCann, Senior Radiation Specialist Decommissioning Branch fI License No. SNM-00007 Dockei No. 070-00008 j
Enclosure:
As Stated l
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l George McCann - R;r Telephona Documantation on conversation regirding BPT . Prgy 1]
[- .
1 From: George McCann To: "jensen@BATTELLE.ORG"@ GATED.nrcsmtp
Subject:
Re: Telephone Documentation on conversation regarding BPT Craig:
You do not need to amend your license for this activity. As discussed, I do not consider your present situation to be any different than that of a visiting researcher at a broadscope University. That is, they are approved users, and are under the control of your license.
Let me know if you need anything else.
l i
Mike McCann 05/21/99
fG4rge McCann - Telephana Documentation en conversation reg rding BPT Pzg31 l 4
From: "Jensen, Craig E" <jensen@BATTELLE.ORG)
To: "'G. Mike McCann'" <GMM@NRC. GOV > l Date: Fri, May 21,1999 2:01 PM
Subject:
Telephone Documentation on conversation regarding BPT Mike, j J
As we had discussed, I am sending you what had originally been a preliminary l amendment request, but is now just a request for e-mail documentation of I concurrence that activities described are within the scope of a normal Type I A broad scope license and no amendment or other specific authorization is I required.
Thanks, Craig Jensen Battelle Columbus SNM-7 Battelle Memorial institute (BMI) hereby requests an amendment to the Materials License SNM-7 and pending Byproduct Materials License 34 26608-01.
In 1998, BMI began the process for" spinning-off" a subsidiary company, Battelle Pulmonary Therapeutics (BPT) which became a business entity in March 1999. The business of BPT is research and development in the areas of medicine and pharmaceuticals, with an emphasis on inhalation technologies.
BPT is a wholly owned subsidiary of BMI, is co-located with BMI, and is staffed by both BPT and BMI personnel. Since the movement of BMI radioactive mat? rial researchers to BPT is planned to occur shortly, BMI would like to request that BPT staff be authorized to use radioactive materials under the BMI license and radiation safety program.
Therefore, BMI requests that NRC grant amendment to the above identified licenses (byproduct research and development uses only), allowing the use of radioactive materials by BPT staff, under those licenses and the auspices of the BMI Radiation Safety Committee (RSC), Radiation Safety Officer (RSO),
Radiation Safety Manual (RSM) and radiation safety program.
The BMI license, RSO, RSC, RSM, and radiation safety program are well established, and will be the authority for all uses of radioactive materials by BPT, Radiation safety policy issues, Pl and user evaluations, facility an<j equipment evaluations, requests for the use of radioactive materials, and other license-related items will be handled by the BMI RSC in the same manner as for BMi activities. Since this work is currently being performed by BMI staff in BMI facilities, there will be no significant increase in work-load for the RSO and staff and will result in no negative impact on the radiation safety program as a whole. BPT work under Batteile's license will not involve activities covered by 10 CFR 35 nor is human use contemplated.
BMI will be fully responsible for ensuring that the terms of the license are I met, the training of staff as radiation workers, that exposures to personnel i are maintained ALARA, for the management of spills or radiation-related J
l George McCb " TJeph:n1 Documen8'on on conversation reg;1 ding BPT e l Pag 22 1
emergencies, and for the decommissioning and decontamination of faci lities used for work involving radioactive materials.
)
If you have any questions, please call my Associate Radiation Safety Officer, Craig Jensen, at (614) 424-5170. I l
1 i
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t-l Bruce Jorgensen - Re OHIO CASES - -
Pags 1]
\ kG N t.(/34R -
From: Carole Ariano V... .\
To: Messier, Maurice ~"" NM -
Date: Tue, May 18,1999 9:38 AM
Subject:
Re: OHIO CASES hl maurice, sorry about the delay -I was out most of last week. I've contacted our DNNS staff and have forwarded your message to John Madera who is the h*.aterials inspection Branch Chief (630-829-9834)- he should be contacting you shortly. let me know if you need any other info or help from me.
thanks, carole DOdk M hudefrig
>>> Maurice Messler OSli31:31 PM >>> [
Carole- We would like to have a copy of the master list of licenses that are being transferred to Ohio._in addition we need to bill all the full cost cases such as Battelle decommissioning and BP Chemicals (
control no. 4007604 which I understand was voided on 4/10/97). I know that Battelle was authorized decom. w/ Amd. 4 issued 10/5/93, however, I haven't received any hrs. to bill. There have been several
~
applications / letters filed by them since, but I can't locate them in NU OCS. l think it will be necessary for !
someone to go over the file since Amd. 4 to determine who and wha rs. have been spent reviewing the I decom. work. I have been billing inspection hrs. regularly. If you hav ny questions please j call-301-415-6087. Thanks. !
euewhM & RW hG cm CC: Crutchfield, Shirley, Weiss, Douglas 3dd we. Agx 6%
I
M Y-21-1999 ~ 14:54 P.02/06 cJ o v ,
OBattelle
. . Putting Tcchnology la Work l
l 50s King Avenue ~
Columbus, Ohio 43201-2693 Telephone (614)4244424 Facsimile (614)424-s263 I l
May 21,1999 tf Mr. G. Mike McCann U.S. Nuclear Regulatory Commission Region III 801 Warrensville Road Lisle,IL 60532-4351
Dear Mr. McCann:
l l
Record of Telephone Conversation Regarding Amendment 17 to Materials License No. SNM-7 As promised, the following is a synopsis of our phone conversadons conducted on Thursday, May 20, 1999.
The following modifications were incorporated into license amendment 17:
- 1. The Licensee was changed to Battelle Memorial Institute, Battelle Columbus Operations. I
- 2. The Radiation Safety Officer was changed to Craig Jensen with no alternate specified at this j time. l Sections 6,7, and 8 l 1
- 1. Section 6. 7 and 8 of the license was reformatted to group all King Avenue and West ) '
Jefferson SNM and Byproduct categories together by location. A separate Item was specified for material use at Temporary Job Sites.1he moisture density gauge specified for use at 29 Palms CA was transferred to this Item. 4
- 2. The SNM material which Battelle possesses, as specified in our February 5,1999, letter, has been incorporated into the license.
- 3. The 3 Curies of C-14 used for Field Studies at the West Jefferson site has been deleted.
- 4. 'Ihe authorized amount for Kr-85, was lowered from 2 Curies to 500 mci. At one time, Battelle believed that all Kr-85 had been removed from the West Jefferson site. However, due to the D&D process, Battelle has identified containers containing small amounts of Kr-85. To
@-N MN -
P.03/06
,O O !
Mr. O. ' Mike McCann 2 May 14,1999 preclude excWg hcense limits during D&D activities, Battelle requested the limit be lowered to 500 mCl.
- 5. 'Ibe 80.7 gram PuBe source referenced in Section 6.F of the SNM license has been transferred to the DOE Pu program at LANL and deleted from the license.
- 6. U-232 and U-234 were specified in items 6, 7, and 8 for the West Jefferson site only. Use and storage of these isotopes at the King Avenue site was deleted.
~7. The Iridium-192 specified for use at the King Avenue site has been removed from the license. This source was transferred from Battelle.
Authorised Places of Use
- 1. Section 9, Authorized Places of Use, was changed to state, " Licensed material may be used in Buildings and Facilities approved by the Rathation Safety Committee (RSC) at the sites j indicated in Section 6, 7, and 8. The licensee will submit a final status survey for Buildings or :
Areas which are to be released for unrestricted use via a license amendment. Battelle will notify the NRC when Buildings are authorized as new licensed material use and storage locations.
f
- 2. In addition, the moisture damity gauge was added to the Item authorizing use at Temporary I Job Sites.
J Conditions
- 1. Battelle requested that license Condition 13, regarding the Radiation Safety Committee Charter, be deleted. The Charter was incorporated into Battelle's Radiation Safety Manual (RSM). You indicated that this condition could not be deleted prior to your review of Battelle's previous Charter and the new Radiation Safety Manual (RSM). Battelle committed to providing you with copies of these documents. In addition, Battelle commits to providing the NRC copies of future RSM revisions which significantly change the safety envelope established by the RSM.
- 2. We discussed if license Condition 14 should f4 deleted. It was determined that this license condition is only applicable to the broad scope ilcense and will be deleted as an explicit condition as part of the approval and issuance of tha broad scope license. Battelle commitments to annual reviews are presented in Batte11e's resp as: to the NRC dated, February 14, 1995, and until the license is approved the NRC deems " , commitment is not enforceable.
- 3. A review oflicense Condition 15 determined that this condition could be deleted as long as Battelle committed to providing the NRC with copies of the Site Environmental Report. The Site Environmental Report currently is generated as a contractual obligation to DOE. This condition has been deleted.
- 4. Battelle has determmed that we do not have enough material to require a contingency plan as required in Condition 17. As per our phone conversation, this candition has been deleted.
i MAY-21-1999 14:55 P.04/06 Mr. G. Mike McCann 3 May 14,1999
- 5. Condition 20 has been deleted. Battelle las already backfilled the filter beds. Before the site can be released for unrestricted use, these filter beds will have to go through the existing D&D process with a final status survey.
- 6. Condition 21 has been deleted. The retired mactor is now part of the BCLDP S&M program. Removing this license condition elimmates the requirement for Battelle to submit to the NRC the annual Retired Reactor Facility Status Report.
- 7. We had a discussion as to Battelle's future pians for the field studies referenced in license Condition 22. Battelle does not plan to perform field studies in the future therefore, license Condition 22 has been deleted.
- 8. Condition 23 was deleted as a condition for use. The material was listed in Section 6, 7 and 8, located at the King Avenue site as, " Uranium enriched in the U-235 isotope-irradiated, any form,10 micrograms of contained U-235 plus the associated and unseparated plutonium and mixed fission products."
- 9. Condition 24 has been modified to allow user training from a vendor who is deemed qualified by the NRC. This allows Battelle to have flexibility in obtaining user training from a vanety of vendors. In addition, license Condition 24 now references all moisture density gauges.
- 10. Condition 25 was deleted. Battelic has a broadscope license which contains authorized amounts for unsealed material. Should Battelle decide to open sources, the material would then fall under the requirements specified for unsealed material.
- 11. We discussed license Condition 31. Specifically, the statement, " NRC regulations shall govern unless the statements, representations, and procedures in the licensce's application are more restrictive than the obligations." It was deemed that the referenced letters did not deviate from the existing NRC regulations and therefore, were approved by the NRC as license conditions.
Battelle requests the RSC be allowed to authorize use and storage of licensed material in special use facilities as defined in Reg Guide 10.5, for Research and Development, with the following upper bounds established.
- 1. The RSC will approve the use and storage of byproduct material up to 5 Curies per study not to exceed 1 Curie in use 'per study at one time.
- 2. The RSC will approve the use and storage of unsealed alpha material, not to exceed 50 mci per study. 4
- 3. '!he RSC will approve the initial installation and operation of compactors and other special use facilities not included in Items 1 and 2 directly above, evaluating the criteria specified in Reg Guide 10.5. The RSO will have the authority to grant movement of the compactors to
, iW-21-1999 14:55 P.05/06 Mr. G. Mike McCann 4 May 14,1999 different locations as long as the safety envelope and conditions established by the RSC are not changed.
- 4. The RSC will only approve interim storage locations for short-lived licensed material used in Research and Development.
- 5. As previously agreed, Battelle will periodically notify the NRC when the RSC approves special use facilities.
In addition to the above, Battelle requests that the license explicidy state that the retired reactor facility is not subject to any separate requirements from the rest of the BCLDP. The discharge of all retired reactor facility requirements would reside within the umbrella of BCLDP, e.g., that no additional or separate financial assurance vehicle or wh=iam would be required, for example, those from 10CFR50.
I have also reviewed with you, the current possession limits. The isotopes and amounts appear to be correct except the updates as noted in Attachment 1 from the Battelle letter dated February 5,1999.
The isotopes and limits are consistent with previous license amendments and the original license application.
Sincerely, f, hetew Stephen J. Layendecker CHP Safety Health and Environmental Support Manager / Radiation Safety Officer Attachments (1) i
. Gr/-24-8%w 14:55 P.06/06 Mr. G. Mike McCann 5 May 14.1999 ATTACHMENT I SpecialNuclear Material Chemicalor Physical Marimum amount to be Form Possessed at one time A. Uranium enriched in the A. Any A.125 grams of contained U-235 U-235 isotope 4 plus the associated and unseparated
-Irradiated plutonium B. Uranium enriched in the B. Any B.10 grams of contained U-235 U-235 isotope
- Unirradiated {
C. Uranium enriched in the C. Plated / Sealed C. I gram of U-235 to:al U-235 isotope
- Unirradiated
]
D. Plutonium (any principal D. Any . D. 0.1 gram total f isotope Pu 236-244 )
E. Plutonium (Pu-238 principal E. Solid Oxide, with E.103 grams isotope) multiple containments F. Plutonium (Pu-239 principal F. Solid Metal or Oxide, F.17 grams isotope) with multipic containments G. Neptunium-237 G. Scaled Source G.1.0 microcurie H. Phitonium (Pu-238 principal H.PuBe Source H. 0.053 grams isotope)
I. Plutonium (Pu-238 principal I. Solid Scrap I. 3.4 grams isotope)
J. Plutonium (Pa-239 principal J. Solid Scrap J. 3.0 grams isotope)
Notes: Item 6.D is identical to Items 6.I through 6.M from Amendment 10, Radioanalytical Lab consumable materials and standards. Ifit duplicates the other items, it may be deleted.
Items 6.E and 6.F forms were clarified to state that the materials were solid forms, and were in multiple ,
containments, with a sealed " fruit can" style outer containment which is typical for such materials from l this era. Item 6.E and Item 6.I were reported together in Amendment 10 Item 6.C.
Items 6. I and 6J fonns were changed to mare clearly reflect the true nature of the holdings. 71mse items are sealed bins and drums of solid wastes containing recoverable amounts of Pu scrap from JN-4 D&D being held at DOE direction for Pu recovery or disposition as directed by DOE.
TOTAL P.06
f W 1999 09:00 P.02/07 u .' O O OBallelle Putting Tetknology To Wark 505 King Avenue Columbus Ohio 432612693 Telephone (61414244424 FacsWile (614)4:45263 May 14,1999 Mr. G. Mike McCann U.S. Nuclear Regulatory Commission RegionIII 601 Warrensville Road Lisle,IL 60532-4351
Dear Mr. McCann:
Notificationfor Use of Compactor underMaterials License No. SNM-7 Battelle MemorialInstitute (BMI) is writing to notify you of the relocation and use of a compactor at the l West Jefferson site. Specifically, the compactor use and storage location in the Building JN-1 Waste Storage Shed.'
Since this is a new compactor location, specifications, as well as compaction opetutional specifics, are provided in Attachment I. Battelle has followed the manufacturer's guidelines for installation, and has I an operatmg procedure which includes the manufacturers recommended operation procedures.
If you have any questions, please do not hesitate to call Craig Jensen of my s'aff at (614) 424-5170. l Sincerely, i
Steph yen sker CHP Safety Health and Environmental Support Manager / Radiation Safety OtTicer
W;W;TWsT TMrTig P.03/07 Mr. G. Mike McCann o 2 o May 14,1999 ATTACHMENT I
" Consolidated Baling Machine" Compactor Model DOS-RAW-W1 The compactor is a 55-gallon drum compactor.
The compactor is operated at a main control station located on the compactor. The control station has a UP, DOWN, EMERGENCY STOP and STOP FAN button. De compaction cycle is activated and the fan motor energized by pushing the DOWN button. This lowers the platen and starts the HEPA filtered exhaust ventilation blower. When the compactor reaches the design compaction pressure, the pump motor
= stops which stops the compaction process. The exhaust ventilation blower continues to operate. The platen is raised by pushing the UP button. The compaction cycle can be interrupted by pushing the EMERGENCY STOP butten or pulling the electrical disconnect knife switch. At the end of compaction operations, the ventilation blower motor is denergized by pushing the S'lVP FAN button. The blower motor will not shut off until this button is pushed. The disconnect switch is installed to secure electrical power to the compactor in an emergency. There is one access door to the compactor drum area. This door is used for both drum and wt . Nading between compaction cycles. A safety interlock prevents the compactor trom compacting when this access door is open.
The compactor is located in a HEPA ventilated enclosure located in the JN 1 Waste Storage Shed. The compactor has a 1/3 HP fan motor with attached blower that ventilates the compaction area to 1000 linear feet per minute through an installed HEPA filter. The exhaust of this HEPA filter is sampled during compaction for airbome activity. In addition, the exhaust from the enclosure is also HEPA-filtered. This exhaust is sarr. pled during compaction as well as monitored continuously with a Continuous Air Monitor.
A pre filter is installed upstream of both HEPA filters to minimize HEPA-filter loading. In place leak testing of the HEPA-fiher is conducted as specified an ANSl/ASME N510 not to exceed every two years.
Pre-filter or HEPA filter changeouts occur when the HEPA-filter differential pressure reaches 5 inches water. in addition, if the HEPA filter dose rate reaches 5 mrem /hr at 30 cm, as rncasured with an appropriate dose rate instrument, the HEPA-filter is changed.
- A personal breathing air sample is collected each time the compactor is in operation. Breathing zone air sampling are supplemented with high or low volume air samples as previously specified. In addition, personnel are required to wear respiratory protection during compaction.
Compliance with the constraint level specified in 10 CFR 20. I 101(d) is verified using the COMPLY
. computer code as specified in Reg Guide 4.20, " Constraint on Releases of Airborne Radioactive Materials to the Environment for Licensees other than Power Reactors."
Contamination and radiation surveys are performed of the compactor, the compacted drums, the HEPA.
filter, and surrounding area daily during use. An approved RWP sets forth the requirements for air sampling, radiation and contamination monitoring and PPE for compaction operations. Approved Work Instructions contain the procedures for checking equiprnent functiening, methods for handling waste which did not compact, and examining drums for defects.
The type of waste which are compacted are Low Level, Dry Active Waste (DAW) which consists of Personal Protective Equipment, plastic, paper and small metal items. The estimated yearly compacted volume is approximately 10,000 ft' .
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O CONSOLIDATED BALING MACHINE COMPANY, m. l 5, D R A if L 1 C 3,I Cl A t i g 13
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i 5400 Ric Grance Avenue ? Jacksonville, Rorida 32205 Sales Offlee P.O. Box 61025
- Jacksenville, Florica 3223G (718) 6254928 (904) 356-7411 * (800) 231-9286 Telex: 804468 ATL PROPOSAL FOR BATTELLE COLUMBUS, CHIO ONE CONSOLIDATED BALING MACHINE MODEL DOS-RAW-W1 TWO-COLUMN, DOWNSTROKE HYDRAULIC PRESS for use'with 55-GALLON DRUMS BASE SIZE: Front to Back: 25
Between Columns: 30" l
DAYLIGHT OPENING: 47" COMPRESSION FORCE: 25,000 lbs. (max.) I COMPRESSION PRESSURE ON MATERIAL: 80 PSI (max.)
PUMP MOTOR: 5 HP, 208/230 Volts, 3 Phase, 60 Cycles FAN MOTOR: 1/3 HP CYLINDER: 4" Bore, 3S" Stroke COMPRESSION TIME: 24 Seconds RETURN TIME: 12 Seconds .
Cornplete with motor, pump, all electric and hydraulic components, all steel, arc-welded construction and with stainiess steel (12 gaugo) Hood, stainless steel platen, chrome plated cylinder rod, shroud (10 gauge HR sheet) and with Ventilation System Consisting of Prefilter, 40%; Nuclear Grade HEPA filter (99,97% eff.; 9.3 Micron. and larger particles) , fan and necessary stainless steel ducts, also with colling drurn support plate and front extensions.
NET PRICE ---- S 17,435.00 DOS-RAW-W1 - CB-2702 - 372490 PAGE ONE OF TWO
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< s m . n. ~ e < y, 7 1 ATTACHMENT TO TELEPHONE CONVERSATION RECORD DATED MAY 6,1999, WITH LARRY SANDERS, OF BATTELLE MEMORIAL INSTITUTE LICENSE NO. SNM-7
/1. Clarify the licensee name The licensee name shoald be:
BatteDe MemorialInstitute Battene Columbos Operations
- 2. Your license indicated two PuBe sources before, now only one? Do you still need both?
Larry indicated the 80.7 gramas PuBe souree had been disposed of.
d Aq e h a oo ut~'
~
- 4. Are you still doing field studies. I thou5 ht your new application didn't authorize this activity anymore? we c s,+ otom ,7 /rc(d W M es q w e.
According to Larry Jensen, they are no longer perforanlag field studies. This was connrased by Larry Sanders.
- 5. We docussed if heense conditions 14 and 15 should be deleted?
At present this condition wW be left in. The above is addreas in a letter seat la response to Kevin Nell's letter. Das, natu that liccese is issued we can't delete the condition.
Dese activities art part of the Heensee's prograan, and was cosandtted to la letter dated February 141995 It was agreed that Condition 15 oould be deleted This condition is no longer necessary. The ,
DOE wlE contisse the requiressent for the Decomunissiosing project, and BCDLP will g
provide a copy to the Region as a coartesy.
- 6. Do you still need a contingency plan? Does your cu:
Tent application call for one? Y . g-l' Condition 17 will be deleted. They no longer have saffseiest quantities which weald require a contingency pine os site say longer. We will delete this condition.
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- 7. Is condition 20 still necessary? They have completed the becMilling. This condition can be deleted. They will have to addreas this area as part of their Mnal status survey.
FPON : RSSSTS 25/0s/19% 15: 46 O 63P55 V T/
PH0tE to. ' 614 424 4770 ptNwlilu M.a y. 12 1999 03:56PM P3
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- 8. Should cond6aon 21 be deleted? These serveys are now part of their BCDLP survey prograan. This survey is enere than sufracient to address this facility.
- 9. Should be condition 22 (regardag the comiuct of Seld studies) be deleted? Mr. Sanders l Will check this with the RSO sod get back to me. /> e /ete W . s e ,, aa I
- 10. Is condition 23 needed any longer? 23. . . possession limits stated in Conditions 6,7, and 8. the licensee is authonzed to possess and use, at its King Avenue site, up to 6tr i "$1.- 1 l
milligrams of SNM. contained in irradiated spent fuel, provided such use is limited to /0 # f ,j
- g activities cefined in the endosure to the licensee's letter detod Septernber 7,1gG3, !
g#j/T '{ (from Gregory Foss to NRC's Chief, Licensing Branch, Division of Fuel Cycle Safety w "' ~U )
v-%p and Safeguards). Larry wHl review the above condities with the RSO, Craig /eM ,
6 Jamaa= And get back with me. .f.__.'1 L-Ta, s Ae /
- 11. Discussed possession limits and conditions We discussed the fouowing possession limits dad and conditions to ascertain if they still are appropriate.
A. Uranium ennched in the U-235 isotope -Imndiated 2r'/ d #
fem } - A. Any 3 g fg c, A. 125 grams of contained U-235 plus the associated and um;e ^ d plutonium y
'c .cr ~p B. Any e B. 10 grams of contowsed U 235 ne Uranium enriched in the U-235 isotope -Uninadiated
)
p C.
C. Plated / Sealed Sources i P
- 5' **' c. 1 gram fi~. fi D. Plutonium (any principal isotope Pu.238 244)
Hc D. Sealed Sources
'#'ll D. 0.1 grams total !
fet kl E. Plutonium (Pu-238 principalisotope) g[y E. Onde E. 10.3 grams F Plutonium (Pu-239 principal isotope)
F. Metal or oxide F. 1.7 grams G. Neptuneum-237 G. Sealed Source G. 1.0 microcurie
I FRCt1 : RSSATS PH tE F O. : 614 424 4770 tt39 121999 03:57Pr1 P4
. 0% C6/1999 M:46 bWED" ' '~ "****
3 H. Plutonium (Pu 238 principle isotope)
H. PuBe Source H. 0.53 grams I. Plutonium (PU-236 pnncipal isotope)
- 1. Diffuse Westa
- 1. 3.4 grams J. Plutonium (Pu-239 prinopelisotope)
J. Diffuse Wasta J. 3.0 grams K. Any Source Material , /*
K. Any p' f t' J K. 50 kilograms total l wenu.a. mon sne lj L. Any byproduct material L frradiated fuel matenal, activated roector materials and components 1 j
L 10,000 curies total, not more than 1,000 curies of any one radioisotope (exduding ltems P through Y below)
M. Hydrogen 3 M. Any M. 500 curies N. Po6orwum 210 N. Any N. 500 curves O. Any O. 500 curies O. CaI4fomium-252 P. Gas P. 1,000 curies P. SuWur-35 Chlorine-30 Q. Gas O. 1,000 cunes Q.
R. lodem-131 R. Any R. 1.000 curies lodine-129 S. Any S. 60 curies S.
T. Any T. 5,000 cunes T. Cobah-00 Cosium-137 u. Any U. 5,000 curies U.
Any V, 5,000 curies V. Strontium 90 V.
PHJNE NO. : 61,Qf,pm tw.121999 03,:{ePt1 g b)th 15:46 but //
4 W. Carbon 14 W. Any W. 3 curies X. Kry p 85 X. Gas X. 2.0 curies Y. Amencium 241 Y. Any Y. 10 millicustes I
Z. Neckeb43 Z. Any Z. 600 milEcurtes
. AA .Ameridum-241 AA. j Seeted source (CPN Model No.131) l AA. One source not to exceed 50 mdt6 curies BB. Carbon-14 99 Any BB. 2 cunes I
l CC. Any byproduct material CC. Any j CC. 100 millicuries total not to exceed 10 millicunes por radionuclide i
Kinn Avenue Site J DD. Any byproduct material DD. Any
- 00. 500 cunes total, not more then 36 curies of any one radioisotope EE. Iridium-192 EE. Any EE. 160 curies West JeNerson und Kirm Avenue Sites FF, NicW-63 FF. Sealed soumes registered pursuant to 10 CFR 32.210 and incorporated into gas chromatograph and/or aerosovairborno contaminant gas and vapor detodor as specstled in item 10.
FF. 600 rnithcunes total. No single source to exceed 40 milhcunes.
GG Amendum-241 GG. Scaled sources registered pursuant to 10 CFR 32.210 and incorporstod into gas chromatograph and/or aerosoVeirbome contaminant gas and vapor detector as specified in item 10.
GG. 500 millicuries total. No sogle source to exceed 50 millicuries.
HH. Hydrogen-3 .
HH. Titanium tnbde sources registered pursuant to 10 CFR 32.210 and incorporated into gas chromatograph and/or aerosol /sirbome contaminant gas atW vapor detector as specified in llam 10.
HH. 3 Curtes total. No single source to exceed 200 millicunes.
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- 11. Amencium-241
- 11. Seeled sources registered pursuant to 10 CFR 32.210 and incorporated into gauging devM:es as specified in item 10.
II. . 400 millicunes total. No single source to exceed 100 millicunes JJ. Cesium-137 JJ. Sealed sources regletered pursuant to 10 CFR 32.210 and incorporated into gauging devices as specifled in item 10.
JJ. 200 millicortes total. No single source to exceed 50 milheuries.
Mr. Sanders was requested to cortfirm if the Autherteed places of Use are as fosows:
xfg AW
- g. gThe d'W in pageslicensco's wie through West Jefferson xi and pages Site2.5, 2.1 through and partKing Avenue II, of the Laboratones licensee's application y Llocated as p.' jM for renewal submitted by letter dated October 23,1981.
t nyu ru m-k h~ sn wp a m an aur 6, w. Ar-rr Jm>.
/.B Licensed matenal listed in item 6.X. may be stored only at the licensee's racility located g at the BMI West Jefferson Facility. 3 ,, w s
.BB) may be used only at the ,y, a/r
/C. Licensed material listed in items 6 Y., S.Z., an licensee's West Jefferson facAity, y-
/ D. Licensed materiallisted in item 8.AA. may be stored et the 20 Palms Marine Base,29 Palms Califomia and used at temporary job sites of the licensee anywhere in the United States where the U.S. Nudeer Regulatory Commission maintains jurisd6ction for regulatmg the use of licensed material.
/. E Licensed materials listed in SubAmms FF., GG., HH.,11.. and JJ. may be used at temporary job sites of the Iscensee anywhere in the United States where the U.S.
Nucieer Regulatory Commission maintains jurisdiction for regulatmg the use of Ikansed material. These items may be stored when not in use at the boonsee's King and West Jefferson sites. The possession of these derices are in addition to devices authortred under Subitem GG.
Authorised use, The fenowing were discussed. The tioensee wel confirm if I have matched the uses with their requested possession limits.
} t Mr. JenserWSanders will confirm whether field studsee le required any longer.
\. @y B. Conduct contmeed field studies at ... West Jefferson, Ohio site. Me< /*/ c f/me-M e> 44*
f C. The principal use for items A. and B F
are as residual contamination in the Hot Celts of the West Jefferson Faditty Building JN-1.
D. The pnncipal uses for item K. are use as residual contaminetson et BMI's King Avenue and West Jefferson facilities, and as sealed scu cm shielding.
FROM : RSS4TS PHDHE to. : 614 424 4770 Ma y. 121999 03:59PM P7
- .- 25/06/1599 15: 45 E3055 97 MON 111D ' - ' *
6 E. Item H. have been transferred to the license from DOE inventory to be used for calibraten.
l F. Iterns G, through M.,00, and PP. are for research and development, and support of Radiological 1.aboratory Operation as desenbad in 'N dated November 17,1994 ;
0 g [$1Aerch 21,19e5, and October 20,1997.
- G7 This has ben confirmed by Mr. Sanders as needing to ty jned.
}
, H. Items Y. and Z. are for research and development l
J. Item BB. is to be used for research and development K ltem CC. is to be used for ressertti and developenant L Subitems FF., GG., and HH. are for use in compatible gas chromatograph devices and or aerosollairtiome contaminant....
nye is ^* &
M. Items ll, and NN. are for use in compatible moisture / density gauges whicts have been registered pursuant to 10 CFR 3..
We discussed the current lleense conditions tied down in the $NM-716 cense and their j letters requesting deletion or change of certain conditions. I seked Mr. Sanders to 1 confirm it the foltoenne conditions reflect our discussions. Just the beginning part of the emoting conditions have be provided for referenes enfy.
12, Notwithstanding Table lit and Table IV presented in Part I, Sections 3.4 and 3.5, for the release of materials, eq j ltem 10 above MT,0reitos Appendix A (Red;otogical Safety Commdtee Charter) of the y 13
@ g g licensee's renewal application (BCL-1061) as a conddeon of the license to clarify and l
In ad& tion to the subpects 6dentified in Sec6cn 5.1.1, Appendix A, the annual review k/14.d and appraisal of fooldies shellindude an assessment of occupationui radiation exposures
- 15. Sections 2.1 and 3.10, Part i refer to provisions for training and penodec retraining of employoos. es appropriate and related to employee work assignments with radioactive
- 16. Secuon 5.0, Part I, of the Licensee's renewal applicatx>n incorporates the text of previous amendments issued by NRC to Special Nuclear Matenal Uconsa No. SNM 7 and 17 At such tirne that tecdities covered by this license are decontaminated for proposed unrestncied release (in accordance with Annex C), the locenoce shall submit a report i
FR0t1 : RSS ATS \ PH3 tie t O. : 614 424 4770 tta y. 12 1999 03:59PM P8
- - 05/06/1939 15: c6 E3073 d 7 MU* A 1 W ' " ' -
7 that identifies the facilities where radioactive materials were used and stored, or disposed on the site. The report shall briefly describe operations conducted and radioactive materials he licensee shall conduct controlled field studies using carbon-14 labeled compounds
)
Licensee will get back to me regarding condition 18 above, may be no longer needed.
- 19. Notwithstanding the possesseon limits stated in Conditions 6,7,,ande,- licensee is authorized to possess and use, at its King Avenue site, up tq@ milligrams SNM.
gmp So m a w h~N d Mr. Sanders not sure it the above condit6on is correct. He will review and get back to me.
- 20. Licensoc material listed under Sutntem AA. shall only be used by, or under the supervision and in the physical presence of, individuals who have received the training described in letters dated June 29,1994 and August 19,1994, or by the device f manufacturer or persons licenood to provide such training, and have been approved in writing by the Radiation Safety Officer.
Mr. Sanders requested that the above,in bold print, be added to the condMaon. They are currentty tied to using the servloes of a consultant.
- 21. Sealed sources listed under Y., Z., and AA. of item 6 shes not be opened
- 22. When performing tests at temporary job..
- 23. The licensee is authortzed to transport the...
- 24. Each portable nudear gau9e shall have a lo...
- 25. The RSO is Craig E. Jensen
- 26. LEAK TEST CONDITION NO CHANGE
- 27. TIE DOWN PORTON OF PROPOSED UCENSE. VERIFY LETTERS Letters dated October 11,1995 (with attachments) September 29,1997, two letters dated October 20,1997, December 24,1997. December 30,1997. September 15,1996, January i t, 1999, January 26,1999, February 5,1999. February 26,1999, and April 12,1999..
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TELEPHONE CONVERSATION RECORD PERSON CALLED: Larry Sanders, Health Physicists Battelle Labs.
Columbus, OH Radiation Technical Support License No. SNM-7 Docket No. 070-00008 l TELEPHONE No.: 614 424 4857 TELEPHONE FAX NO: 614 424 3954 1
CALLER: Mike McCann, Senior Radiation Specialist Decommissioning Branch DATE OF CALL: May 6,1999
SUBJECT:
DISCUSSION REGARDING THE BATTELLE LICENSE, FORMAT, POSSESSION LIMITS, ETC.
We discussed their license its, format, possession limits and conditions.
Mr. Sanders was requested to review the attachment and confirm if the items discussed reflected correctly our discussions.
A copy of this telephone conversation record was faxed to the licensee.
No further.
Mike McCann May 6,1999 k . .
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ATTACHMENT TO TELEPHONE CONVERSATION RECORD DATED MAY 6,1999, WITH LARRY SANDERS, OF BATTELLE MEMORIAL INSTITUTE LICENSE NO. SNM-7
- 1. Clarify the licensee name.
The licensee name should be:
Battelle Memorial Institute Battelle Columbus Operations
- 2. Your license indicated two PuBe sources before, now only one? Do you still need both?
Larry indicated the 80.7 grams PuBe source had been disposed of.
- 3. Do you still have the .2 curies of krypton 857 Larry indicated that they still possess the Kr-85.
- 4. Are you still doing field studies. I thought your new application didn't authorize this activity anymore?
According to Larry Jensen, they are no longer performing field studies. This was confirmed by Larry Sanders.
- 5. We discussed iflicense conditions 14 and 15 should be deleted?
At present this condition will be left in. The above is address in a letter sent in response to Kevin Null's letter. Thus, until that license is issued we can't delete the condition.
These activities are part of the licensee's program, and was committed to in letter dated February 141995 It was agreed that Condition 15 could be deleted. This condition is no longer necessary. The DOE will continue the requirement for the Decommissioning project, and BCDLP will provide a copy to the Region as a courtesy.
- 6. Do you still need a contingency plan? Does your current application call for one?
Condition 17 will be delated. They no longer have sufficient quantities which would require a contingency plan on site any longer. We will delete this condition.
- 7. Is condition 20 still necessary? They have completed the backfilling. This condition can be deleted. They will have to address this area as part of their final status survey.
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- 8. Should condition 21 be deleted? These surveys are now part of their BCDLP survey program. This survey is more than sufficient to address this facility.
- 9. . Should be condition 22 (regarding the conduct of field studies) be deleted? Mr. Sanders will check this with the RSO and get back to me.
' 10. Is condition 23 needed any longer? 23. ... possession limits stated in Conditions 6,7, .
and 8, the licensee is authorized to possess and use, at its King Avenue site, up to 50 milligrams of SNM contained in irradiated spent fuel, provided such use is limited to activities defined in the enclosure to the licensee's letter dated September 7,1993, (from Gregory Fess to NRC's Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards). Larry will review the above condition with the RSO, Craig Jensen. And get back with me.
I 1. Discussed possession limits and conditions. We discussed the following possession limits and conditions to ascertain if they still are appropriate.
A. Uranium enriched in the U-235 isotope - Irradiated A. Any
-A. 125 grams of contained U-235 plus the associated and unseparated plutonium B. Uranium enriched in the U-235 isotope - Unirradiated B. Any B. 10 grams of contained U-235 C. Uranium enriched in the U-235 isotope -Unirradiated
'C. Plated / Sealed Sources C. 1 gram D. _ Plutonium (any principal isotope Pu-238-244)
D. Sealed Sources D.~ 0.1 grams total E. Plutonium (Pu-238 principal isotope)
E. Oxide .
E. 10.3 grams F. Plutonium (Pu-239 principal isotope)
F. Metal or Oxide -
F. 1.7 grams
~ G. Neptunium-237 G, Sealed Source G. 1.0 microcurie I
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- H. Plutonium (Pu-238 principle isotope)
H. PuBe Source
- H. 0.53 grams
- 1. Plutonium (PU-238 principal isotope)
- 1. Diffuse Waste )
' l. 3.4 grams J .- Plutonium (Pu-239 principalisotope)
J. Diffuse Waste l J. ; 3.0 grams K. Any Source Material K. 'Any K. 50 kilograms total West Jefferson Site L. Any byproduct material.
L. Irradiated fuel material, activated reactor materials and components L. 10,000 curies total, not more than 1,000 curies of any one radioisotope (excluding items P thrww a Y below)-
M. Hydrogen-3 i M. ~Any l M. 500 curies N. Polonium-210 N. Any
-N. 500 curies O. Califomium-252 - O. Any- O. 500 curies P. ~ ' Sulfur-35 P. Gas P. 1,000 curies Q. Chlorine-36 Q.' Gas Q. 1,000 curies >
R. - lodine-131 R. -Any R. 1,000 curies S. lodine-129 S. Any S. 60 curies T. Cobalt 60 T. Any T., 5,000 curies U. Cesium-137 u. Any U. 5,000 curies V. . Strontium-90 V. -Any V. 5,000 curies
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' W. Carbon-14 W. Any W. 3 curies I
X. Krypton-85 X. Gas X. 2.0 curies Y. Americium-241 Y. ' Any Y. - 10 millicuries Z. Nickel-63 Z. Any Z. 600 millicuries AA . Americium-241 AA. Sealed source (CPN Model No.1131)
AA. One source not to exceed 50 millicuries l
l BB.~ Carbon-14 BB.- Any BB. 2 curies CC. . Any byproduct material CC. Any.
CC. 100 millicuries total not to exceed 10 millicuries per radionuclide
. Kino Avenue 5'ig DD. Any byproduct material DD. Any i DD. 500 curies total, not more than 35 curies of any one radioisotope EE. Iridium-192 i l EE. Any l EE. 150 curies l
West Jefferson and Kina Avenue Sites i l
FF. Nickel-63 FF. - Sealed sources registered pursuant to 10 CFR 32.210 and incorporated into gas l chromatograph and/or aerosol /airbome contaminant gas and vapor detector as l . specified in item 10.
' FF. 600 millicuries total. No single source to exceed 40 millicuries.
GG. Americium-241 GG. Sealed sources registered pursuant to 10 CFR 32.210 and incorporated into gas ;
chromatograph and/or aerosol /airbome contaminant gas and vapor detector as specdied in item 10.
I GG. 500 millicuries total. No single source to exceed 50 millicuries.
HH. Hydrogen-3 HH.- Titanium tritide sources registered pursuant to 10 CFR 32.210 and incorporated into gas chromatograph and/or aerosol /airbome contaminant gas and vapor detector as
. specified in item 10.
HH. 3 curies total. No single source to exceed 200 millicuries.
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- 11. Americium-241 II. . Sealed sources registered pursuant to 10 CFR 32.210 and incorporated into gauging devices as specified in item 10.
II. 400 millicuries total. No single source to exceed 100 millicuries.
JJ. Cesium-137-JJ.- Sealed sources registered pursuant to 10 CFR 32.210 and incorporated into gauging devices as specified in Item 10.
JJ. 200 millicuries total. No single source to exceed 50 millicuries.
Mr. Sanders was requested to confirm if the Authorized places of Use are as follows:
A. The licensee's West Jefferson Site and King Avenue Laboratories located as described in pages vil through xi and pages 2.1 through 2.5, part 11, of the license 9's application for renewal submitted by letter dated October 23,1981.
B. Licensed material listed in item 6.X. may be stored only at the licensee's facility located at the BMI West Jefferson Facility..
C. ' Licensed material listed in items 6.Y.,6.Z., and 6.BB. may be used only at the licensee's West Jefferson facility.
D. Licensed material listed in item 6.AA. may be stored at the 29 Palms Marine Base,29 Palms Califomia and used at temporary job sites of the licensee anywhere in the United States where the U.S. Nuclear Regulatory Commission mtnintains jurisdiction for regulating the use of licensed material.
E. Licensed materials listed in Subitems FF., GG., HH.,11., and JJ. may be used at temporary job sites of the licensee anywhere in the United States where the U.S.
Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material. These items may be stored when not in use at the licensee's King and West Jefferson sites. The possession of these devices are in addition to devices authorized under Subitem GG.
Authorized use. The following were discussed. The licensee will confirm if I have matched the uses with their requested possession limits.
' Mr. Jensen/ Sanders will confirm whether field studies is required any longer.
B. Conduct controlled field studies at ... West Jefferson, Ohio site.
C. ' The principal use for items A. and B are as residual contamination in the Hot Cells of the West Jefferson Facility Building JN-1. q D. The principal uses for item K. are use as residual contamination at RMI's King Avenue and West Jefferson facilities, and as sealed source shielding.
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E. Item H. have been transferred to the license from DOE inventory to be used for I calibration.
F. Items G. through M., OO.' and PP. are for research and development, and support of Radiological Laboratory Operation as described in letters dated November 17,1994, March 21,'1995,'and October 20,1997.
G. This has ben confirmed by Mr. Sanders as needing to be retained.
H. Items Y.'and Z. are for research and development -
- 1. - Item AA is for use in a Campbell Pacific Nuclear gauge.
J. Item BB. is to be used for research and developm'ont K. Item CC. is to be used for ;esearch and development i
L._ . Subitems FF., GG., and HH. are for use in compatible gas chromatograph devices and i or aerosol /airt>orne contaminant....
M. Items ll. and NN; are for use in compatible moisture / density gauges which have been registered pursuant to 10 CFR 3.,
We discussed the current license conditions tied down in the SNM-7 license and their ;
letters requesting deletion or change of certain conditions. I asked Mr. Sanders to confirm if the following conditions reflect our discussions. Just the beginning part of the ,
existing ctMitions have be provided for reference only. ;
1
- 12. Notwithstanding Table ill and Table IV presented in Part I, Sections 3.4 and 3.5, for the release of materials, eq
- 13. Item 10 above incorporates Appendix A (Radiological Safety Committee Charter) of the i licensee's renewal application (BCL-1081) as a condition of the license to clarify and 14.- In addition to the subjects identified in Section 5.1.1, Appendix A, the annual review
. and appraisal of facilities shall include an assessment of occupational radiation exposures
- 15. Sections 2.1 and 3.10, Part I ref6 to provisions for training and periodic retraining of employees, as appropriate and related to employee work assignments with radioactive
- 16. Section 5.0, Part I, of the licensee's renewal application incorporates the text of previous amendments issued by NRC to Special Nuclear Material License No. SNM-7 and.
- 17. At such time that facilities covered by this license are decontaminated for proposed unrestricted release (in accordance with Annex C), the licensee shall submit a report j
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7 that identifies the facilities where radioactive materials were used and stored, or disposed on the site. The report shall briefly describe operations conducted and radioactive materials
- 18. The licensee shall conduct controlled field studies using carbon-14 labeled compounds in Licensee w;ll get back to me regarding condition 18 above, may be no longer needed.
- 19. . Notwithstanding the possession limits stated in Conditions 6,7, and 8, the licensee is authorized to possess and use, at its King Avenue site, up to 50 milligrams of SNM . .
Mr. Sanders not sure if the above condition is correct. He will review and get back to me.
- 20. Licensed material listed under Subitem AA. shall only be used by, or under the j supervision and in the physical presence of, individuals who have received the training described in letters dated June 29,1994 and August 19,1994, or by the device manufacturer or persons licensed to provide such training, and have been approved in writing by the Radiation Safety Officer.
l Mr. Sanders requested that the above, in bold print, be added to the condition. They are currently tied to using the services of a consultant.
- 21. Sealed sources listed under Y., Z., and AA. of item 6 shall not be opened
- 22. When performing tests at temporary job..
- 23. The licensee is authorized to transport the..
- 24. Each portable nuclear gauge shall have a lo...
- 25. The RSO is Craig E. Jensen
- 26. - LEAK TEST CONDITION NC CHANGE
- 27. TIE DOWN PORTION OF PROPOSED LICENSE. VERIFY LETTERS Letters dated October 11,1995 (with attachments), September 29,1997, two letters dated October 20,1997, December 24,1997, December 30,1997, September 15,1998, January 11, 1999, January 26,1999, February 5,1999, February 26,1999, and April 12,1999..
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. O o TELEPHONE CONVERSATION RECORD PERbON CALLED: Craig Jensen, Radiation Safety Officer Bettelle MemorialInstitute Battelle Columbus Operations License No. SNM-7 Docket No. 070-00008 TELEPHONE No.: 614 424 5170 ,
= CALLER: Mike McCann, Senior Radiation Specialist
. Decommissioning Branch DATE OF CALL: April 26,1999 I
SUBJECT:
DISCUSSION REGARDING THE ISSUANCE OF AMENDMENT OF BATTELLE'S LICENSE IN ITS ENTIRETY Mr. Jensen and I discussed the 5 letters which would be involved in amending their SNM-7 license. Additionally, we discussed the need for us to issue a new amendment which would update the license'in its entirety.
The last time the SNM-7 license was done in its entirety was 1993. In order to insure that I had captured all the aspects of Battelle's requests contained
.in the 5 letters, I faxed a draft of the proposed amendment request to Mr.
Jensen, and requested that he review the document and confirm that the possession limits and conditions reflect their requests.
Mr. Jensen called back and indicated that he would have one of his staff I health physicists review the document and get back to me.
No further.
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Attachment:
draft license document i
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u.s. NUCLEAR REGULATORY CoMMl3sioN Amendment No.16 Liewater MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34, 35, 36, 39,40, and 70, and in reliance on statements and representations birttofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to d;livtr or transfer such material to persons authorized to receive it in accordance wrth the regulations of the applicable Part(s) This license shill be deemed to contain the con- . specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all tpplicable rules, regulations, and of u of the Nuclear Regulatory Commission now or hereafter in effect and to any condrtions specified below.
Licensee in accordance with the letter dated September 15,1998
- 1. Battelle Columbus Division 3. License number SNM-7 is amended in ;
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- 2. 505 King Avenue 4. Expiration date April 30,1988 (on timely renewal)
- 5. Docket No. 070-00008 Columbus, OH 43201-2693 Reference No.
- 6. Byproduct, source, and/or special 7. Chemical and/or physical form 8 Maximum amount that licensee may nuclear material possess at any one time under this i l
license Soecial Nuclear Material West Jefferson Site A. Uranium enriched in the A. Any A. 100 grams of contained U-U-235 isotope - irradiated 235 plus the associated and unseparated plutonium B. Uranium enriched in the B. Any B. 50 grams of contained U-235 isotope - unirradiated U-235 C. Plutonium (Pu-238 principal C. Sealed source C. 13 grams isotope)
D. Plutonium (Pu-239 principal D. Oxide D. 17 grams isotope)
E. Plutonium (Pu-238 principal E. PuBe Source E. 0.053 grams isotope)
F. Plutonium (Pu-239 principal F. PuBe Source F. 80.7 grams isotope)
G. Uranium-233 G. Any G. 0.99 grams H. Uranium-235 H. Any H. 0.99 grams
- 1. Plutonium-236 1. Any 1. 0.04 micrograms )
i J. Plutonium-238 J. Any J. 0.60 micrograms K. Plutonium-239 K. Any K. 82.0 micgrograms C&T j
UQff NRC FORM 374A U.S. NUCLEAR REGULIcTORY COMMISSION PAGE 2 of 10 PAGES ucense Number SNM-7 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.16 4
- 6. Byproduct, source, and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may I nuclear material possess at any one time under this license L. Plutonium-240 L. Any L. 22.0 micrograms M. Plutonium-242 M. Any M. 6.40 micrograms Kina Avenue Site
- 11. Uranium enriched in the 11. Any 11. 50 grams of contained U-235 isotope - unirradiated U-235 Source Material West Jefferson and Kina Avenue Sites N. Uranium (natural and N. Any N. 300 kilograms depleted) and thorium OO. Uranium-232 00. Any 00. 0.99 grams PP. Uranium-234 PP. Any PP. 0.99 grams Byoroduct Material West Jefferson Site
- 1. Any byproduct material O. Irradiated fuel material, O. 10,000 curies total, not activated reactor materials more than 1,000 curies of and components any one radioisotope I (excluding items P through Y below)
P. Hydrogen-3 P. Any P. 500 curies Q. Polonium-210 Q. Any 4 Q. 500 curies R. Califomium-252 R. Any R. 500 curies ,
i S. Sulfer-35 S. Gas S. 1,000 curies T. Chlorine-36 T. Gas T.1,000 curies C 'f
NRC FORM 374A U.S. NUCLEAR REOuLAToRY commission PAGE 3 of 10 PAGES License Number SNM-7 MATERIALS LICENSE Docket r Reference Number SUPPLIiMENTARY SHEET 070-00008 Ogh4 Amendment No.16
- 6. Byproduct, source, and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material possess at any one time under this license g U. lodine-131 U. Any U. 1,000 curies V. lodine-129 V. Any V. 60 curies W. Cobalt-60 W. Any W. 5,000 curies X. Cesium-137 X. Any X. 5,000 curies Y. Strontium-90 Y. Any Y. 5,000 curies Z. Carbon-14 Z. Any Z. 3 curies AA. Krypton-85 AA. Gas AA. 2.0 curies BB. Americium-241 BB. Any BB. 10 millicuries CC. Nickel-63 CC. Any CC. 600 millicuries DD. Americium-241 DD. Sealed source (CPN Model DD. One source not to exceed No.131) 50 millicuries EE. Carbon-14 EE. Any EE. 2 curies FF. Any byproduct material FF. Any F" 100 millicuries total not to exceed 10 millicuries per radionuclide Kina Avenue Site GG. Any byproduct material GG. Any GG. 500 curies total, not more tha,35 curies of any one raddsotope HH. Iridium-192 HH. Any HH. 150 curies West Jefferson and Kino Avenue Sites Q
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O dg+ O NRC FORM 374A U.S. NUCLEAR REGULATORY COMM1881oN PAGE 3 of 10 PAGES Ucense Number SNM-7 MATERIALS LICENSE D cW r Refwence Numbw SUPPLEMENTARY SHEET 07 4 00008
- Amendment No.16
- 6. Byproduct, scurce, and/or speclaf 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material possess at any one time under this license U. lodine-131 U. Any U. 1,000 curies V. lodine-129 V. Any V. 60 curies W. Cobalt-60 W. Any W. 5,000 curies X. Cesium-137 X. Any X. 5,000 curies Y. Strontium-90 Y. Any Y. 5,000 curies Z. Carbon-14 Z. Any Z. 3 curies AA. Krypton-85 AA. Gas AA. 2.0 curies BB. Americium-241 BB. Any BB. 10 millicuries CC. Nickel-63 CC. Any CC. 600 millicuries DD. Americium-241 DD. Sealed source (CPN Model DD. One source not to exceed No.131) 50 millicuries EE. Carbon-14 EE. Any EE. 2 curies FF. Any byproduct material FF. Any FF. 100 millicuries total not to exceed 10 miilicuries per radionuclide Kino Avenue Site GG. Any byproduct material GG. Any GG. 500 curies total, not more than 35 curies of any one radioisotope HH. Iridium-192 HH. Any HH. 150 curies West Jefferson and Kino Avenue Sites C v' - L '
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l NRC form 374A U.S. NUCLEAR REGULATORY COMMISSloN PAGE O of 10 PAGEs Ucense Numt,ar SNM-7 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 070-00008 {
dy _p Amendment No.16
- 6. Byproduct, source, and/or special 7. Chemical and/or physical form 8. Maximum amount that licensee may nuclear material possess at any one time under this license i
JJ. Nickel-63 JJ. Sealed sources registered JJ. 600 millicuries total. No pursuant to 10 CFR 32.210 single source to exceed 40 and incorporated into gas millicuries.
chromatograph and/or aerosol /airbome contaminant gas and vapor detector as specified in item 10.
4 KK. Americium-241 KK. Sealed sources registered KK. 500 millicuries total. No j pursuant to 10 CFR 32.210 single source to exceed 50 and incorporated into gas millicuries.
chromatograph and/or aerosol /airbome contaminant gas and vapor i detector as specified in l Item 10.
LL. Hydrogen-3 LL. Titanium tritide sources LL. 3 curies total. No single registered pursuant to 10 source to exceed 200
{'
CFR 32.210 and millicuries.
incorporated into gas chromatograph and/or i aerosol /airbome l contaminant gas and vapor detector as specified in item 10.
MM. Americium-241 MM. Sealed sources registered MM. 400 millicuries total. No l pursuant to 10 CFR 32.210 single source to exceed 100 l and incorporated into millicuries. l gauging devices as specified in item 10.
NN. Cesium-137 NN. Sealed sources registered NN. 200 millicuries total. No pursuant to 10 CFR 32.210 single source to exceed 50 1 and incorporated into millicuries. j gauging devices as l l specified in item 10., o, !
p_._
1 i
(NOTE: The licensee is also authorized to possess any source material that may be contained in the 1
l
1 J
NRC $oRM 374A u.s. NUCLEAR REGULATORY COMM18SION PAGE s of 10 PAGEs Ucense Number SNM-7 MATERIALS LICENSE Dxket or Reference Number SUPPLEMENTARY SHEET 070-00008 Amendment No.16 irradiated uranium of item A above.) Y [
l
- 9. Authorized places of Use:
A. The licensee's West Jefferson Site and King Avenue Laboratories located as described in pages vii through xi and pages 2.1 through 2.5, part II, of the licensee's application for renewal submitted by letter dated October 23,1981, (excluding Building KA-3 as described in letter dated January 31, 1996).
B. Licensed material listed in item 6.AA. may be stored only at the licensee's facility located at the BMI West Jefferson Facility.
C. Licensed material listed in Items 6.BB.,6.CC., and 6.EE. may be used only at the licensee's West Jefferson facility. '
D. Licensed material listed in item 6.DD. may be stored at the 29 Palms Marine Base,29 Palms Califomia and used at temporarv job sites of the licensee anywhere in the United States where the U.S. Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material.
E. Licensed materials listed in Subitems JJ., KK., LL., MM., and NN. may be used at temporary job sites of the licensee anywhere in the United States where the U.S. Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material. These items may be stored when not in use at the licensee's King and West Jefferson sites. The possession of these devices are in addition to devices authorized under Subitem GG.
CONDITIONS
- 10. Authorized use:
A. For use in accordance with statements, representations, and conditions contained in the following portions of the licensee's application for renewal (BCL Document 1081) submitted by letter dated October 23,1981, except as may be modified by the conditions of this license:
- 1. Pages vi through xi, introduction;
- 2. Part I, License Conditions;
- 3. Appendix A, Radiological Safety Committee Charter, and
- 4. Letters dated June 29,1994, August 19,1994, July 6,1995 (excluding item 1), and August 3,1995 (excluding item 1)..
B. Conduct controlled field studies using up to a maximum of 3 curies of carbon-14 labelled compound at the lice.nsee's West Jefferson, Ohio site.
i-
- ^
NRc koRM 374A u.8. NUCLEAR REGULATORY CoMMISSloN PAGE O of 10 PAGES License Number SNM-7 .
MATERIALS LICENSE Dxket or Reference Number SUPPLEMENTARY SHEET 070-00008 l hh Amendment No.16 20555, and the Region til NRC Regional Office at the address specified in Appendix D of 10 CFR Part 20, a report containing a description of each change within six months after the change is made.
- 18. Section 5.0, Part I, of the licensee's renewal application incorporates the text of previous amendments issued by NRC to Special Nuclear Material License No. SNM-7 and Byproducts Materials License No.
34-06854-05 covering decontamination and decommissioning plans applicable to the Battelle Hot Cell Laboratory, it is hereby affirmed that the provisions to these decontamination and decommissioning l plans, including financial arrangements, continue in effect under this renewed license, and also apply to the retired Battelle Research Reactor.
- 19. At such time that facilities covered by this license are decontaminated for proposed unrestricted release (in accordance with Annex C), the licensee shall submit a report that identifies the facilities where radioactive materials were used and stored, or disposed on the site. The report shall briefly describe l operations conducted and radioactive materials used in the facilities and shall assess the results of the decontamination activities. The report shall provide the basis for unrestricted release of the facilitiers and the site, including a description of sampling and survey methods and instrumentation used, and shall include final contamination survey data for the facilities and grounds. The licensee may segment the report to obtain release of certain areas of facilities or individual structures if it is demonstrated that ongoing activities in other areas will not lead to recontamination of the area or structure proposed for release.
- 20. The licensee is authorized to backfill and retired filter bed area on the West Jefferson site where cor'aminatt. 6 oil was removed as described in the licensee's letter of May 13,1981. The homogenized beu containing low levels of residual contamination shall be covered with approximately three feet of soil as stated in the letter of May 13,1981. ,
- 21. The licensee shall perform quarterly surveys, not to exceed 4 months, for radiation, contamination, and integrity of physical barriers at the retired Battelle Research Reactor. Records of such surveys shall be maintained by the licensee.
- 22. The licensee shall conduct controlled field studies using carbon-14 labelled compounds in accordance with the statements and representations contained in the licensee's application for amendment submitted by letter dated August 5,1988. -
- 23. Netwithstanding the possession limits stated in Conditions 6,7, and 8, the licensee is authorized to possess and use, at its King Avenue site, up to 50 milligrams of SNM contained in irradiated spent fuel, provided such use is limitied to activities defined in the enclosure to the licensee's letter dated September 7,1993, (from Gregory Fess to NRC's Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards).
- 24. Licensed material shall only be used by, or under the supervision and in the physical presence of, individuals who have received the training described in letters dated June 29,1994 and
NRC IoRM 374A U.S. NUCLEAR REGULATORY CoMMIS&loN PAGE 7 of 10 PAGES License Number SNM-7 MATERIALS LICENSE Dxket w Refem Numbe SUPPLEMENTARY SHEET 0 4 00008
, Amendment No.16
- 12. Notwithstanding Table 111 and Table IV presented in Part I, Sections 3.4 and 3.5, for the release of materials, equipment, and facilities for unrestricted use, he licensee shall adhere to the provisions of the cttached " Guidelines for Decontamination of Facilities ano Equipment Prior to Release for Unrestricted Use of Termination of Licenses for Byproduct, Source, or Special Nuclear Material," dated April 1993.
- 13. It:m 10 above incorporates Appendix A (Radiological Safety Committee Charter) of the licensee's r:newal application (BCL-1081) as a condition of the license to clarify and define morc My cdmiristrative procedures for review, approval and audit of activities covered by the I c.sns% as described in Section 1.3 and Section 2.0 of Part 1. The licensee may make revision to tha proMons of Appendix A, based upon written evaluationj of the changes, without NRC approvalif it 6 determir9d that such changes will not decrease the effectiveness of the Committee in carrying out its functions.
Revisions to the Charter and supporting evaluations shall be submitted to the Director, Division of Fuel Cycle Safety and Safeguards, NRC, with a copy to the Administrator, Region ill Office, NRC, withir 60 drys following such changes.
- 14. in addition to the subjects identified in Section 5.1.1, Appendix A, the annual review and appraisal of fIcilities shall include an assessment of occupational radiation exposures and releases of radioactive material over the past year with regard to maintaining such exposures and releases as low as is reasonably achievable, as stated in Section 20.1(c),10 CFR Part 20.
- 15. The licensee shall provide three copies each year of its annual environmental report to the Director, Division of Fuel Cycle Safety and Safeguards, NRC, and a copy to the Administrator, Region lli Office, NRC.
- 16. Sections 2.1 and 3.10, Part I refer to provisions for training and periodic retraining of employees, as cppropriate and related to employee work assignments with radioactive and fissionable materials. Such training shall be conducted, as appropriate, for new employees and prior to initiating new operations cpproved by the Radiological Safety Committee and retraining shall be conducted on topics appropriate to employee work assignments at least annually. Documentation of such training and retraining shall be m intained.
- 17. The licensee shall implement, maintain, and execute the response measures of its Radiological Contingency Plan submitted to the Commission on March 5,1982. The licensee shall also maintain implementing procedures for its Radiological Contingency Plan as necessary to implement the Plan.
This Radiological Contingency Plan and associated implementing procedures incorporate the emergency plInning requirements of 10 CFR 70.22(i) as they refer to onsite planning and notification procedures.
The licensee shall make no change to its Radalogical Contingency Plan that would decrease the response effectiveness of the Plan without prior Commission approval as evidenced by a license cmendment. The licensee may make changes to its Radiological Contingency Plan without prior Commission approvalif the changes do not decrease the response effectiveness of the Plan. The licensee shall maintain records of changes that are made to the Plan without prior approval for a period of two years from the date of the change and shall fumish the Chief, Fuel Cycle Safety Branch, Division of Fuel Cycle Safety and Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC
'F~
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NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 11 of 10 PAGES Ucense Number SNM-7 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 07 4 00008 Amendment No.16
}
w i N FOR THE U.S. NUCLEAR RE TORY COMMISSION N
s y D ts _ ^~ - -
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\
Geor McCann Ma als Lic sing Branch aion til
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- REGut.AToRA""" SNM-7
' un.NUC A oocketor Refer NRC FDRM 37 070 00008 MATERIALST LICENSE Amendment No.16 SUPPLEMENTARY FHEE PF""*" *"# ination in x a sguese puwvu= d v' '"* Conditions 6,7, and C.
The principal use f or items A. and B. un erFacility Buildingat JN-1.
l contamination the Hot Cells of the West Aanditiene Jefferson R,7, and A are uso as raciduaan f ii THn nrinHnul nupt fnr item f+ nnderosus'e tsane A.=num .ma w..e r"r f m DOE
,7, and 8 have been transferred to the license ro i v ntory to be used fo a on.
p y e
/ MnrnNfduch 8 M.: 00.: and[M gr(fgegrch and o**= no, S"a7,h"" ** da=er G. Item AA. Is for storage only pending disposal.
H. Items BB. and U. are for research and development activities as described in letters dated June 29,1994 and August 19,1994.
- l. Item DD. is for use in a Campbell Pacific Nuclear Model 503 portable moisture / density gauge.
J. Item EE. is to be used for research and development as described in 10 CFR Part 30, Section 30.4.
K. Item FF. is to be used for research and development as described in 10 CFR 30, Section 30.4 and support of Radiological Laboratory Operations as described in letter dated March 21,1995.
L. Subitems JJ., KK., and LL. of items 6,7, and 8 are for use in compatible gas chromatorgraph devicess and or aerosol /airbome contaminant gas snd vapor devices which have been registered pursuant to 10 CFR 32.210 and distributed in accordance with an NRC or Agreement State specific license to persons specifically licensed by the NRC to receive, possess and use the devices.
M. Items MM. and NN. are for use in compatible moisture / density gauges which have been registered pursuant to 10 CFR 32.210 and distributed in accordance with an NRC or Agreement State specific license to persons specifically li:ensed by the NRC to receive, possess and use the devices.
- 11. Scaled byproduct material sources she', be subject to the leak testing and actions specified in the attached procedure titled " License Co ,dition for Leak Testing Sealed Byproduct Material Sources," dated April 1993. Scaled plutonium sourees shall be subject to the leak testing and actions specified in the attached procedure titled License Jondition for Leak Testing Sealed Plutonium Sources," dated April 1993.
~
I NRC' FORM 374A u.S. NUCLEAR REGULATORY CoMMISSloN PAGE 9 of 10 PAGES Ucense Number SNM-7 MATERIALS LICENSE DocM m Refence Number SUPPL EMENTARY SHEET 070-00008 g Aniendment No.16 August 19,1994, and have been approved in writing by the Radiation Safety Officer.
- 25. Sealed sources listed in Subitems BB., CC., and DD. of item 6 shall not be opened by the licensee.
- 26. When performing tests at temporary job sites, the authorized user shall not leave the moisture / density gauge unattended. Upon completion of tests the device shall be locked in the licensee's vehickle or a secure building to prevent unauthorized use, loss, or theft.
- 27. The licensee is authorized to transport the portable moisture / density gauge only in accordance with the provisions of 10 CFR Part 71, " Packaging and Transportation of Radioactive Material."
- 28. Each portable nuclear gauge shall hav0 a lock or outer locked container designed to prevent unauthorized or accidental removal of the sealed source from its shielded position. The gauge or its container must be locked when in transport, storage, or when not under the direct surveillance of an authorized user.
- 29. A. The Radiation Safety Officer for this license is Stephen J. Layendecker.
B. The Altemate Radiation Safety Officer for this license is Craig Jensen.
- 30. A. Sealed sources and detector cells shall be tested for leakage and/or contamination at intervals not to exceed 6 months or at such other intervals as specified by the certificate of registration referred to in 10 CFR 32.210.
B. Notwithstanding Paragraph A of this Condition, sealed sources designed to emit alpha particles shall be tested for leakage and/or contamination at intervals not to exceed 3 months.
C. In the absence of a certificate from a transferor indicating that a leak test has been made within 6 months prior to the transfer, a sealed source received from another person shall not be put into use until tested.
D. Each sealed source fabricated ay the licensee shall be inspected and tested for construction defects, leakage, and contamination prior to any use or transfer as a sealed source.
E. Sealed sources need not be leak tested if:
(i) they contain only hydrogen-3; or (ii) they contain only a radioactive gas; or l
1 (iii) the half-life of the isotope is 30 days or less; or ,
1 J
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I NRC FORM 374A u.S. NUCLEAR REOULATORY COMM18SloN PAGE 10 of 10 PAGES Ucense Number SNM-7 MATERIALS LICENSE D chat r Reference Number SUPP EMENTARY EET 070-00008 Amendment No.16 (iv) they contain not more than 100 microcuries of beta and/or gamma emitting material or not more than 10 microcuries of alpha smitting material; or (v) they are not designed to emit alpha particles, are in storage, and are not being used.
However, when they are removed from storage for use or transferred to another person, and have not been teste1 within the required leak test interval, they shall be tested before use or transfer. No sealed source or detector cell shall be stored for a period of more than 10 years without being tested for leakage and/or contamination.
i F. The leak test shall be capable of detecting the presence of 0.005 microcuries of radioactive material on the test sample. If the test reveals the presence of 0.005 rnicrocuries or more of removable contamination, a report shall be filed with the U.S. Nuclear Regulatory Commission in accordance with 10 CFR 30.50(b)(2), and the source shall be removed immediately from service and I decontaminated, repaired, or disposed of in accordance with Commission regulations. The report !
shall be filed within 5 days of the date the leak test result is known with the U.S. Nuclear Regulatory l Commission, Region lil, 801 Warrenville Road, Lisle, IL 60532, ATTN: Director, Division of Nuclear Materials Safety. The report shall specify the source involved, the test results, and corrective action taken.
G. Tests for leakage and/or contamination shcIl be performed by the licensee or by other persons specifically licensed by the Commission or an Agreement State to perform such services.
l
- 31. Except as spacifically provided otherwise in this license, the licensee shall conduct its program in I tecordance with the statements, representations, and procedures contained in thedocuments, including i
any enclosures, listed below. The U.S. Nuclear Regulatory Commission's regulations shall govem unless the statements, representations, and procedures in the licensee's application and correspondence are more restrictive than the regulations.
A. Letters dated October 11,1995 (with attachments), September 29,1997, two letters dated October 20,1997, December 24,1997, December 30,1997, and September 15,1998.
(
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APP-26-19?3 17:00 P.0F06 )
,' L . O Q 3 i
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---> UPDATED VERSION 15 April 1999 Craig Jensen CORRECTED COPY TELEPHONE CONVERSATION RECOP,D PERSON CALLED: Craig Jensen, Assistant RSO Battelle Labs.
> UPDATE: Battelle Columbus Columbus, OH License No. SNM-7 Docket No. 070-00008 TELEPHONE No.: 614 424 5170 CALLER: Mike McCann, Senior Radiation Specialist Decommissioning Branch DATE OF CALL: April 12,1999
SUBJECT:
- 1. STATUS OF DECOMMISSIONING SCHEDULE
- 2. LICENSE POSSESSION LIMITS
- 3. AMENDMENT REQUEST TO CHANGE RSO
- 4. AMENDMENT REQUEST TO ADD HIGH LEVEL LABORATORIES
- 5. REQUEST FOR CERTAIN EXEMPTIONS FROM REQUIREMENTS FOR RETIRED DECOMMISSIONING REACTOR
- 6. REQUEST TO RELOCATE COMPACTOR FROM KING AVENUE SITE TO THE WEST JEFFERSON SITE On the above date i called Mr. Jensen to discuss the above subjects.
The discussion was as follows:
Subject Item 1:
APR-26-1993 17:01 P 03/06 I o .o. p DOE and Battelle are still in negotiation regarding the contract for L
BCLDP Project. Mr. Jensen indicated that they probably will need some additional time. He will get back to us within the next week.
-- 7 UPDATE 1!
L 1 talked w'ith Tom Baillieu! on Wednesday and got some notes on his i draft response. Ovemight I concluded that, as you had said, it was better to request that DOE CEMP (Columbus Environmental Management Project) provide its own input in writing in its own words.
I called Tom today and requested that he provide the project a response which he would have to have approved up his management chain at least as far as the Ohio Field Office. I got the impression from Tom that a reasonable time frame to receive this letter from him is 2 -
weeks. I will be calling you to talk about what he said and the next step forward on this issue. Battelle is unable to provide detailed planning without DOE guidance, and there will be some lag time to
-build the planning once the guidance is available. Tom believes that with WIPP opening to receive TRU waste there is now a path forward l to conclusion, and the potential for BCLDP shipment of its TRU l
wastes to an interim site like Hanford is now much more politically viable.
Craig Jensen' Battelle Labs Telephone Conversation Recoreage 2 Sublect item 2-Advised Mr. Jensen that we have reviewed their February 5,1999, letter which contained Battelle's revised material possession limits.
l Ms. Frazier has been provided a copy of the letter and is to get back to me regarding our findings, i.e., do we agree with the calculations and assumptions.
I A COMMENT 2: Battelle wishes to request that this issue be resolved '
soon, so that we can plan on a course of action, Currently, Battelle is a
ffR-26-1999 17:01 o P. N/06
. ,o p3 relying on the' unconfirmed but strongly held opinion by some at Region lll that Battelle will remain with the Region and not " roll over" to State of Ohio.
Subiect Item 3:
I advised Mr. Jensen that we are combining this request with the
. January 11,1999, request and have no problem with adding him to license. Therefore, once they respond to my questions listed in Subject item 4, we can amend license ASAP.
Subiect item 4:
A. Will Battelle commit to providing Rlli a periodic report identifying special, i.e, high activities or unique use labs?
The report should indicate the lab location, brief description of work, length of time lab will be in operation, and i quantities of materials to be used. If they agree to this we I will not require more information and will not require this information in the form of individual amendments.
A RESPONSE TO 4.A: Yes, Battelle will commit to providing a periodic
' report that identifies special, i.e., high activities or unique use labs (. 7 Battelle request that this be extended to the D&D license, so that we can utilize resources efficiently , e.g., new and relocation of existing compactors.
B. Regarding Building 3, storage of Radiological Waste. Is this short term? E.g., decay in storage? ' Not long term interim waste storage? Characterize the waste to be i stored? Describe the storage area. Are special features I required for waste? Fire protect? High activities?
Shielding necessary?
C. Will there be any waste processing performed in this are? l Describe. Procedures in license for this? j
- RESPONSE TO 4.B & C: As previously discussed, Building 3 would ,
be used for normal R&D radioactive materials use under the 34- !
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pfR-26-1999 17:02 P.05/06 O .O J ;
e i byproduct materials license.
Craig Jensen
' Battelle Labs l
Telephone Conversation' RecordPage 3 k i
- 5. Subiect Item 5:
Licensee requests, in letter dated January 26,1999, relief from FSAR requirements. Licensee feels not necessary since Reactor decommissioned, and facility covered under Battelle's
-Decommissioning License. Talked with John House, NRC Rlli !
inspector who has been to site and former reactor facility. John j agreed with me, that there is no need for the former '
requirements. !
- 6. Mr. Jensen inquired about amending their license to authorize i the movement of a compactor from the King Avenue Site to the '
West Jefferson site. He indicated that he would fax me a letter requesting this. 'l received letter dated April 12,1999, which 1 will review on the 13 and get back to Mr. Jensen. It appears initially that I will be able to incorporate this request into the January 11,1999, license amendment request.
4 UPDATED ITEM 7: Battelle wishes to add its newest, soon to be cpened laboratory building, No. 20 to the byproduct materials license.
Battelle assumes that this action does not take an amendment, but simply notification.
. A copy of this Telephone Conversation Record was E-mailed to Mr.
Jensen per his request.
A revised copy of this record was sent to Mr.' Jensen correcting the record date from April 11 to April 12,1999 No further J
APR-26-lo!9 17:02 P.06/06
,' .; '. O O fr Mike McCann April 12,1999 CORRECTED COPY fN c
a% r W 80 i
TOTAL P.06
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O O OBattelle Putting Technology la WL -
r s05 King Avenue Columbus, Ohio 43201-2693 Telephone (614) 4244424 racsimile (614) 424-5263 April 12,1999
. Mr. G. Mike Mc Cann U.S. Nuclear Regulatory Commission
. Region III -
801 Warrensville Road' Lisle, IL 60532 '4351.
Dear Mr; McCann:
Requestfor Amendment to Materials License No. SNM-7, Docket 70-8 and Byproduct Materials License 34-26608-01.
~Battelle Memorial Institute (BMI) requests an amendment to the Byproduct Materials License SNM-7
' and Byproduct Materials License 34-26608-01, for the installation and remote operation of a " Slugger" compactor in the JN-1 hot cells; Mechanical Test Cell (MTC), Low-Level Cell (LLC), IIigh-Level Cell
- (HLC) and Iligh Energy Cell.
The " Slugger" compactor is currently installed and operated at Battelle's King Avenue facility, Building XP as specified in Battelle's Byproduct License Application correspondence, dated, February 14,1995, section 14.C. A picture of the compactor and specifications are provided in Attachment I.
. Battelle intends to remove the compactor from the King Avenue, Building XP, and transfer it to the West Jefferson JN-1 hot cells for compaction of TRU and low level waste. Modifications will be made to the compactor to allow remote loading and compaction usmg hot cell manipulators. The modifications are as follows and are illustrated in Attachment I: '
- l. .The Emergency Stop button will be moved to a remote operating location outside the hot cell.
' 2. The Key controlled Off/Run/ Start switch will be moved to a remote operating station located outside the hot cell.
- 3. The rubber ram sealing gasket / skirt will be removed to facilitate compaction in a drum liner.
This gasket / skirt is installed to minimize airborne contamination due to the compaction process. Ilowever, due to the compaction process being performed in the hot cells, this skirt
'is not needed. In addition, the skirt diameter is too large to effectively minimize airbome
, contamination when compacting drum liners.
APR 161999
q V
q V
G. Mike McCann April 12,1999 Page 2
- 4. The installed drum safety proximity switch will be disabled. This safety switch is an interlock which combined with a key function allows the compaction ram to lower. This safety feature has to be disabled to allow compaction in drum liners. The drum liners have a smrller diameter than the 55 gallon drums for which the compactor was designed therefore, would not actuate the switch.
- 5. The compactor base will be modified because of the limited strength of the manipulator arms. Drums are loaded onto a cart which is then positioned onto the compactor base. T1.e j compactor base is located at a higher elevation than the cart therefore. The cart has to be rolled up to the compactor base. The compactor is designed in this manr er to prevent the cart wheels from absorbing any compaction force. To facilitate drum liner installation by the manipulator arms, Battelle will install reinforced cart wheels to raise the cart elevation to just I above the compactor base plane. This will give the manipulators arms the ability to load the cart onto the compactor base. The cart base will be approximately 1/16 inch higher than the 1 compactor base therefore, the reinforced cart wheels will absorb a portion of the compaction j force.
j i
The remaining interlock will be the key interlock. The key switch has three positions; off, run and start.
Prior to compaction, the key has to be inserted and switched to run. To compact, the key is positioned to the spring return start position. Once the key is postitioned to start, the compactor will go through a 30 second compaction cycle by specification sheet. The cycle time is modified only by the emergency stop button or when the compaction process reaches a maximum compaction pressure. At that point, the RAM will return to the up position. The compaction key controlled switch will be operated at a remote station located outside the hot cell. All drum liners will be installed and compaction operations will be performed using the hot cell manipulator arms.
The compactor has no ventilation system associated with the device. A ventilation line runs from the drum area out the back of the compactor. At the King Avenue site, this line is cornected via ducting to the XP Building HEPA filtered ventilation system. As the compactor will be operated in the hot cell, l there is no need to redirect the compaction exhaust. The compaction exhaust will exhaust at the !
compaction site and be directed by the current hot cell ventilation system through a prefilter and double IIEPA filter exhaust system. The hot cell exhaust system is monitored on a continuous basis. Should ,
contamination levels reach the monitoring system setpoints, the respective hot cell ventilation blower l will shutdown and the exhaust dampers will shut. The hot cell ventilation system is described in Battelle's 1988 Deemed Timely filed application license, SNM-7, Docket 70-8, and the Building JN-1,
" Decontamination Work Plan", submitted to the NRC in November 1990.
This amendment is prepared as specified in Reg Guide 10.5 section11.e. Because the compactor will be ^
operated inside the hot cells, radiation surveys of the compacted drum liners will be performed remotely until removal from the hot cell. Upon removal from the hot cell, radiation and contamination surveys will be performed and the drum liner exterior will be deconned for storage and eventual disposal. All survey requirements will be specified in an approved Radiation Work Permit (RWP). i Air samples will not be conducted during compaction operations in the hot cell. Breathing zone and general area air samples will be perfomaed as specified in an approved RWP.
t
O O G. Mike McCann -
April 12,1999 Page 3 The compactor will be operated 'as specified in an approved work instruction. The operators will be provided and trained on a Compaction in the Hot Cell operational procedure. This procedure will include i checks for proper functioning of the compactor, actions for removal of a damaged drum liner from the
. compactor and examining containers for defects..
l Ifyou have any questions, please do not hesitate to call Mr. Craig Jensen of my staff at (614) 424-5170.
~ Sincerely, b
Stephen J. Lay ecker- '
l - Environment, Safety & liealth Support ll - Manager / Radiation Safety Officer .
1 i
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C's O ATTACHMENT 1 I
1 St.UCCER SPECIFICATIONS Compaction Force (Maximum) 14,000 1.bs.
Ram Tace Pressure 70 PSI Motor i Horsepower totally enclosed i
Electrical i15 volt, 60H2, 20 Amp, Single Phase, must be on dedicated 20 Amp elsetric service 1
Power Drive system Hydraulic )
System Pressure (Maximum) 2l00 PSI Ram Stroke 2 5'"
compaccion Cycle Time Approximately 30 seconds Weight 950 Pounds '
1 Machine Size
- 76 " High ~
, 25" Wide i . 35" Deep l l
Compaction Ram 1/2" sesel plate supporting corrosica rasistant compaction ]
drtun i Hachine Base 1/4" reinforced with coluem extending into base integrally
, welded into a high strength unit.
Compaction Chambe'r , 34"'high x 22" in diameter (appror. 7.25 cubic feet). Clam shell opening using continuous t chrome hing sad two heavy duty ;
toggle locks. Container is equipped l vith a heavy duty polyethylene split liner and dirp pan.
Compaction Ratie Will compact up tp 10:1 and will-
' produce bag weights that can be l adjusted from 30 to 150 pounds. l Bass Heavy duty, 4 mil poly bags Push Button Operation Machine supplied with key operating switch to prevent unauthorised use
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l March 19,1999 i Mr. Tim Vitkus Oak Ridge Institute for Science and Education 1299 Bethel Valley Road P.O. Box 117 Oak Ridge, TN 37831-0177
DearMr. Vitkus:
Enclosed are the final status tables for the . Building KA-2 Outside West Line soil populations prepared by the Battelle Columbus Laboratory Decommissioning Project (BCLDP) as discussed in your telephone conversation with Joe Poliziani. The sampling and interpretation of the analytical results was performed per the criteria used in the " Draft Building KA-2 Characterization and FinalStatus Report" sent to ORISE by the BCLDP on October 19,1998.
However, these tables will ultimately be included in a report for all three segments of the external lines removed on Tisdale Avenue. The issuance of the KA-2 final report should proceed as scheduled.
If we may be of any assistance in any way, please contact Joe Poliziani (614/424-7776) of my staff.
Sincerely, k.}. [
L'. F. Ermold '
Program Manager i Decontamination and Decommissioning Operations l LFE:tpt Enclosure cc: Thomas Baillicul(US DOE)
. G. Mike McCann (USNRC) -
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O TABLE 1.
KING AVENUE MEAN ACTIVITY hOj CONCENTRATIONS FOR BACKGROUND SOIL SAMPLES Mean Activity Concentration ' 2o-Analytical Parameter (pCilg)- (pCl/g) -
1 RAL Ganuna Spectroscopy Results Be-7 ' <MDA <MDA K-40 1.31E +01 1.81E+00 Co-60 ' < MDA < MDA
-- Sb-125
<MDA < MDA
. Cs-137 9.26E-02 2.82E-02 Ce-139 <MDA < MDA Eu-152 <MDA < MDA
. Eu-154 < MDA <MDA TI-208 2.94E-01 5.02E-02 Bi-212 1.07E+00 4.23E-01 Pb-212 7.72E-01 9.68E-02 Bi-214 1.53E+00 1.33E-01 Pb-214 ' l.64E+ 00 1.63E-01 Ra-226* 1.64E+00 1.63E-01 Ac-228 9.31E-01 1.14E-01 Th-234 1.69E+00 3.84E-01 U-235 - 3.31E-01 4.64E-02 Am-241 < MDA < MDA
- Ra-226 assumed to be in secular equilibrium with Pb-214.
I i
l Tables for Final Status Sod Populations for 13u11 ding KA-2 West Line Revision 0 March 1999 Page1 i l
~
T (vT TABLE 2.
BUILDING KA-2 O' fSIDE WEST LINE SOIL POPULATION IDENTIFIC EL., Soil Pop; .WorkInstruction Location - . Characterization Number Number: ' Number '
Number Tisdale 99-KA2-O/S-11784 99-0150 1 941 Tisdale 99-KA2-O/S-11785 99-0151 2 941 Tisdale 99-KA2-O/S-11786 99-0152 3 941 Tisdale 99-KA2-O/S-11787 99-0153 4 941
. Tisdale 99-KA2-O/S-11788 99-0154 5 941 Tisdale 99-KA2-O/S-11789 99-0155 6 941 Tisdale 99-KA2-O/S-11790 99-0156 7 941 Tisdale 99-KA2-O/S-11791 99-0157 8 941 Tisdale 99-KA2-O/S-11792 99-0158 9 941 Tisdale 99-KA2-O/S-11793 99-0159 10 941 Tisdale 99-KA2-O/S-11794 99-0160 11 941 Tisdale 99-KA2 0/S-11795 99-0161 12 941 Tisdale 99-KA2-O/S-11796 99-0140 13 941 Tisdale 99-KA2-O 'S-11797 99-0141 14 941 Tisdale 99-KA2-O/S-11798 99-0142 15 941 Tisdale 99-KA2-O/S-11799 98-0143 16 941 Tisdale 99-KA2-O/S-11800 98-0144 17 941 Tisdale 99-KA2-O/S-11801 98-0145 18 941 Tisdale 99-KA2-O/S-11802 98-0146 19 941 Tisdale 99-KA2-O/S-11803 98-0147 20 941 Tisdale 99-KA2-O/S-11804 98-0148 21 941 Tisdale 99-KA2-O/S-11805 98-0149 22 941 Tisdale 99-KA2-O/S-11806 98-0168 23 941 Tisdale 99-KA2-O/S-11807 98-0169 24 941 Tisdale 99-KA2-O/S-11808 98-0170 25 941 l
l l
l Tables for Final Status Soil Populations for Building KA-2 West L'e Revision 0 March 1999 Page 2 1
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... Proposed 8 Soit population locations BUILDING KA-2 OUTSIDE WEST LINE SOIL POPULATION LOCATIONS Tabics for Final Status Soil Populations for Building KA.2 West Line Revision 0 Mach 1999 Page 3
O O TABLE 3. h d BUILDING KA2 OUTSIDE WEST LIST SOIL POPULATION ANALYTICAL RESULTS
. EL# 99-0150 EL# 99-0151 EL# 99-0152 Analytical - Result 2a . Result 2c Result . 20-Parameter - l(pCi/g) - ' (pCi/g) (pCi/g) .pCi/g) - (pCilg) (pCi/g)
. Be 1.00E-01 0.00E+00 < l.14E-01 0.00E+00 < l .00E-01 0.00E +00
' K-40 1.13E+01 9.55E-01 1.12E +01 1.10E+00 1.12E+01 1.06E +00
- Mn-54 < l .43E-02 0.00E+00 < l .43 E-02 0.00E+00 < 1.17E-02 0.00E+00
' Co-58 < l .28E-02 0.00E+00 < l .33E-07 0.00E + 00 < 1.12E-02 0.00E+00 Co 60 < l .50E-02 0.00E +00 < l .46E-02 0.00E +00 < 1.10E-02 0.00E+00 Zu < 3.44E-02 0.00E +00 < 3.43E-02 0.00E + 00 < 2.43 E-02 0.00E+00 Sb-125 ' < 3.38E-02 0.00E +00 < 3.91E-02 0.00E+00 < 3.38E-02 0.00E+00 I-131 < l .32E-02 0.00E +00 < 1.71 E-02 0.00E+00 < 1.50E-02 0.00E+ 00
' Cs-134 < l .16E-02 0.00E + 00 < l .34E-02 0.00E+ 00 < 1.13 E-02 0.00E+ 00 Cs-137 - 3.15E-02 1.21E-02 3.16E-02 1.32E-02 2.63E-02 9.14E-03
. Eu-152 - < 2.40E-02 0.00E +00 < 3.21 E-02 0.00E+ 00 < 3.22E-02 0.00E +00
- Eu-154 . < l .66E-02 0.00E +00 < 2.29E-02 0.00E+00 < 2.28 E-02 0.00E+00
'Il-208 2.43E-01 2.39E-02 2.81E-01 2.71E-02 2.51E-01 2.38E-02 3
Bi-212 - 7.94E-01 1.87E-01 6.44E-01 2.12E-01 9.08E-01 1.92E-01 Pb-212 9.51E-01 4.30E-02 9.45E-01 5.12E-02 9.30E-01 5.30E-02
- Bi-214 ! 1.35E+00 7.45E-02 1.31E + 00 7.23E-02 1.45E+00 7.00E-02 Pb-214 1.42E+00 8.56E-02 1.40E+ 00 9.24E-02 1.45E+ 00 9.04E-02 Ra-226' l.42E+00 8.56E-02 1.40E +00 9.24E-02 1.45E + 00 9.04E-02 Ac-228 - 7.70E-01 5.27E-02 7.53E-01 5.34E-02 7.23E-01 4.87E-02
- Th-234 1.50E +00 1.64E-01 1.33E + 00 1.84E-01 1.24E+00 1.77E-01 U-235 ~ 1.89E-01 0.0187 2.11E-01 2.76E-02 1.78E-01 2.45E-02 Am-241 < 4.90E-02 0.00E + 00 < 2.87E-02 0.00E+ 00 < 2.60E-02 i 0.00E+ 00 Tables for Final Status Soil Populations for Building KA-2 West Line Revision 0 March 1999 Page 4
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NJ TABLE 3. uOO d (Continued)
> EL#994115L EIJ 99-0154 J - EL# 99-0155
" Analytical' Result ' 20- . Result 120'- Result - 20 --
Parameter / - (pCilg)1 -- (pCllg) - ~ (pCl/g) - foCUg) (pCl/g) . (pC1/g) -
. Be-71 < 9.52E-02 0.00E+00 < 9.16E-02 0.00E+ 00 < 9.92E-02 0.00E +00 K 40 - 9.80E+ 00 1.15E+00 1.20E +01 9.24E-01 1.29E+01 1.39E +00 Mn-54 . < l .24E-02 0.00E+00 < l .21E-02 0.00E + 00 < l .23E-02 0.00E+00
' Co < l .09E-02 0.00E +00 < l .13E-02 0.00E+00 < 1.12E-02 0.00E+00 i Co-60. ~ < 1.16E-02 0.00E+00 < l .24E-02 0.00E +00 < 1.10E-02 0.00E +00 Zn . < 2.69E-02 0.00E +00 < 2.94E-02 6.00E +00 < 2.68E-02 0.00Et00
' Sb-125
< 3.21E-02 0.00E+ 00 < 3.21 E-02 0.00E +00 < 3.50E-02 0.00E + 00 L I-131 < 1.43E-02 0.00E+ 00 < l .33 E-02 0.00E +00 < l.55E-02 0.00E+00 Cs-134 ' < l .06E-02 0.00E +00 < 1.06E-02 0.00E+ 00 < l .17E-02 0.0GE +00
- Cs-137 - - < 1.27E-02 0.00E +00 2.37E-02 9.62E-03 < 1.26E-02 0.00E+00
'Eu-152- < 2.87E-02 0.00E +00 < 2.70E-02 0.00E+00 < 3.14E-02 0.00E+00 Eu 154 < 2.02E-02 0.00E+00 < l .90E-02 0.00E+00 < 2.23E-02 0.00E +00 t 'I1-208 2.35E-01 2.28E-02 2.55E-01 .2.41E-02 2.70E-01 2.62E-02
- B1212: 7.64E-01 2.01E-01 9.15E-01 2.14E-01 8.75E-01 1.74E-01 Pb-212: 9.06E-01 4.58E-02 9.64E-01 4.89E-02 1.05E + 00 5.13E-02 Bi-214 1.27E +00 6.90E-02 1.52E +00 7.41E-02 1.93E+00 9.26E-02
- Pb-214 .- 1.26E+00 8.15E-02 1.52E+00 8.80E-02 '2.03E + 00 1.21 E-01
- Ra-226' l.26E+ 00 8.15E-02 1.52E +00 8.80E-02 2.03E + 00 1.21E-01 Ac 228 ' 6.76E-01 4.75E-02 7.95E-01 5.04E-02 7.46E-01 5.02E-02
{
Th-234 1.17E+ 00 1.71E-01 1.78E+00 2.35E-01 1.52E + 00 1.77E-01 1 U-235 " 1.80E-01 2.44E-02 1.54E-01 5.65E-02 2.38E-01 2.68E-02 Am 241:' < 2.67E-02 0.00E +00 < 7.53E-02 0.00E+00 < 2.82E-02 0.00E + 00 Tables for Final Status Soil Populauons for Building KA-2 West Line Revision 0 March 1999 Page 5
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TABLE 3.
i") [D d' ~
(Continued)
EL# 99-0156 - EL# 99-0157 EL# 99-0158 :
Analytical Result 2a - Result - 2a~ Result - 2a Parameter'- (pC1/g) (pC1/g) - (pCilg) (pCi/g) (pCilg) (pCi/g)
- Be < 1.07E-01 0.00E + 00 < 9.08E-02 0.00E+00 < 1.18E-01 0.00E+00
- K-40 8.77E+00 7.65E-01 8.79E +00 8.37E-01 9.14E+00 1.09E+00 Mn < 1.47E-02 0.00E+ 00 < 1.04 E-02 0.00E+00 < l .51 E-02 0.00E +00 Co-58 ; < l .34E-02 0.00E+00 < 9.340-03 0.00E + 00 < 1.38E-02 0.00E+00 Co-60 < 1.51 E-02 0.00E+ 00 < 9.16E-03 0.00E+00 < 1.47E-02 0.00E+00 Zn 65 < 3.32E-02 0.00E +00 < 2.05E-02 0.00E+00 < 3.35E-02 0.00E+00 Sb-125 ~ < 3.58E-02 0.00E+00 < 2.92E-02 0.00E+ 00 < 3.93E-02 0.00E+00 1-131 < 1.47E-02 0.00E+00 < 1.86E-02 0.00E+00 < 2.55E-02 0.00E+00
. Cs-134 < l .25E-02 0.00E+00 < 9.28E-03 0.00E+00 < 1.36E-02 0.00E + 00 Cs-137 6.77E-02 1.45E-02 9.67E-03 6.99E-03 6.42E-02 1.35E-02 Eu 152 < 2.52E-02 0.00E+00 < 2.79E-02 0.00E +00 < 3.46E-02 0.00E+00 Eu-154 < l .76E-02 0.00E+ 00 < 1.94E-02 0.00E+00 < 2.43E-02 0.00E +00 TI-208 _ 2.85E-01 2.56E-02 2.00E-01 2.08E-02 3.00E-01 2.88E-02
. Bi-212 . 8.87E-01 2.07E-01 4.38E-01 1.54E-01 1.12E+00 2.21E-01 Pb-212 1.10E+ 00 4.88E-02 7.09E-01 4.19E-02 1.19E + 00 5.90E-02 Bi-214 1.44E +00 7.62E-02 1.37E +00 6.53E-02 1.52E+00 8.57E-02 Pb-214 -- 1.51E+00 9.15E-02 1.40E+00 8.67E-02 1.49E + 00 9.85E-02 Ra-226* 1.51E +00 9.15E-02 1.40E +00 8.67E-02 1.49E +00 9.85E-02 Ac-228 8.91E-01 5.71E-02 5.64E-01 3.98E-02 9.26E-01 6.02E-02 Th-234 1.65E +00 1.83E-01 1.07E+00 1.56E-01 1.74E+ 00 2.21E-01 U-235. 2.15E-01 1.99E-02 2.11E-01 2.61E-02 2.17E-01 3.00E-02 Am-241 - < 5.25E-02 0.00E +00 < 2.24E-02 0.00E + 00 < 3.23 E-02 0.00E + 00 Tables for Final Status Soll Populations for Building KA-2 West Line Revision 0 March 1999 Page 6
r O
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TABLE 3.
O C'Y
.. ~
l' (Continued) ..
s EL# 994159 ElJ 994160 l 1 EL# 994161=
. Result. f2a[i iReadt? / l 20! ' JResultj L 20 .:
Paraanster 2(pCi/g); e (pC1/g) : - (pCi/g) ~ * (pCi/s) L(pC1/g)t ;(pCi/g)s fm i Be-7 V > ' < 9.24E-02 0.00E+00 < 9.38E-02 0.00E+00 - < l .12E-01 0.00E+00 f .K-40.1 9.12E +00 7.13E 1.03E+01 1.llE+ 00 1.10E +01 9.41E-01 tMA 54 : < 1.21E-02 0.00E+00 < 1.10E-02 . 0.00E+00 < 1.52E-02 0.00E+00 5C$-58 : < 1.12E-02 0.00E+00 < l .04E-02 0.00E+00 < l.44E-02 0.00E +00 TCo40I ' < 1.20E-02 0.00E+00 < 9.61E43 0.00E+00 < l .61E-02 0.00E+00 Zn45 < 2.69E-02 0.00E+00 < 2.33E-02 0.00E+00 < 3.29E-02 0.00E+00
> Sb-125b < 2.99E-02 0.00E+00 < 3.03E-02 0.00E+00 < 3.63E-02 0.00E+00 l I-1310 < 1.86E-02 0.00E+00 < l .97E-02 0.00E+00 < 2.16E-02 0.00E+00
? CA 134 < 1.01E-02 0.00E+00 < l .03E-02 0.00E+ 00 < 1.26E-02 0.00E+00 l
6 Cs-1372 < 1.13E-02 0.00E +00 < 1.23E-02 0.00E+00 4.90E-02 1.18E-02 l
>Eu152i < 2.55E-02 0.00E+00 < 2.85E-02 0.00E+00 < 2.52E-02 0.00E+00 7 Eu-154 ' < l .80E-02 0.00E +00 < 2.00E-02 0.00E+00 < l .80E-02 0.00E+00 fl1-200 3 3.02E-01 2.60E-02 2.49E-01 2.37E-02 2.91E-01 2.54E-02 l
e Bi-2121 1.03E+00 2.29E-01 9.87E-01 1.88E-01 9.34E-01 2.24E-01 !
- Pb-2121 9.22E-01 ~ 4.72E-02 9.84E-01 4.70E-02 1.12E + 00 4.%E-02 1B1-214 J 1.41E +00 7.04E-02 1.42E +00 7.26E-02 1.58E+00 8.11E-02
( Pb-214 x 1.46E +00 8.62E-02 1.51E+00 9.23E-01 1.61E+00 9.70E t Ra-226'z 1.46E+00 8.62E-02 1.51E+00 9.23E-02 1.61E+00 9.70E-02 l i Ac-228 9 8.02E-01 4 96E-02 7.61E-01 4.93E-02 8.05E-01 5.42E-02 I ETh-234 -~ 1.65E +00 2.24E-01 1.35E+00 1.67E-01 1.74E+00 1.87E-01 U-2355 1.81E-01 1.78E-02 1.87E-01 2.37E-02 2.04E-01 2.00E-02 1Am-2411 < 7.16E-02 0.00E+00 < 2.48E-02 0.00E+00 < 5.19E-02 0.00E+00 I
Tables for Final Status Soil Pupulations for Building KA-2 West Line Revision 0 March 1999 Page 7
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TABLE 3. /g (Continued) u EW 994140 ~- : EM 994141N El> 9941422
~
Analyticali Result . 20 ~ i Result!' E20 i iResult L ,
20~
Parsunster 1(pCi/g) - (pCi/s)1 J (pCi/g) < . (pCl/s) L !(pCi/s)-' (pCi/g) -
( Be-70 < 8.30E-02 . 0.00E+00 < 9.17E-02 0.00E+00 < 6.33E-02 0.00E+00 1 K42 1.03E+01 9.76E-01 9.34E+00 1.10E+00 1.00E+01 7.60E-01
!MS54i <1.00E-02 0.00E +00 < l .18E-02 0.00E+00 < 8.94E-03 0.00E+00
? Co-58 : < 8.92E-03 0.00E+00 < 1.04 E-02 0.00E+00 '<8.04E-03 0.00E+00
- CA40? < 9.19E-03 0.00E+00 <1.12E02 0.00E+00 < 9.20E-03 0.00E +00 Zn45 < 2.03E-02 0.00E+00 < 2.75E-02 0.00E+00 < 2.09E-02 0.00E +00 j fS$-125) - < 2.88E-02 0.00E+00 < 3.05E-02 0.00E+00 < 2.25E-02 0.00E +00 1-131? < 1.14E-02 0.00E+00 < l .22E-02 0.00E+00 t 8.18E-03 0.00E+00
? CA-134 : < 9.05E-03 0.00E+00 < 1.07E-02 0.00E+00 < 7.51E-03 0.00E+00
[Cs-1375 ' 3.91E-02 9.31E-03 < 1.32E-02 0.00E+00 1.43E-02 6.01E-03 J En-152.; < 2.80E-02 0.00E+00 < 2.78E-02 0.00E+00 < 2.01E-02 0.00E+00 1Eu-154 i < 1.97E-02 0.00E +00 < l .97E-02 0.00E+00 < 1.43E-02 0.00E+00 iTI-2081 2.71E-01 2.40E-02 2.33E-01 2.27E-02 2.18E-01 1.79E-02 1
~
' 6 Bi-212 2 8.73E-01 2.00E-01 6.68E-01 1.73E-01 7.71E-01 1.38E-01 LPli-212 9 9.02E-01 5.01E-02 8.35E-01 4.21E-02 7.42E-01 3.74E-02 i Bi-2142 1.23E+00 5.89E-02 1.15E+00 6.46E-02 1.17E+00 5.37E-02
' Pb-214 s 1.24E+00 7.71E-02 1.13E+00 7. 41E-02 1.16E+00 6.75E-02 fl3Ra-2267 .1.24E +00 7.71E-02 1.13E+00 7.41E-02 1.16E+00 6.75E-02
$ Ac-228( ' 7.81E-01 4.74E-02 6.53E-01 4.56E-02 6.65E-01 3.94E-02
- 'Ih-234 1.25E+00 1.64E-01 1.14E+00 1.67E-01 1.12E+00 1.62E-01 i U-235 i 1.83E-01 2.35E-02 1.21E-01 5.55E-02 1.53E-01 1.42E-02 lam-241! < 2.30E-02 0.00E+00 < 2.58E-02 0.00E+00 < 5.46E-02 0.00E+00 l
i I
Tables for Final Status Soil Populations for Building KA-2 West Line Revise March 1999 Page 8 )
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D ()
hO /J TABLE 3. E-(Continued)
EL# 99-0143 EL# 99-0144 - EL# 99-0145 Analytical . . Result . .20 Result 20 _ .20-Result _
Parameter -- - (pCI/g) - (pCi/g) (pCl/g) (pCi/g) (pC1/g) (pCi/g)
- Be-7 < 7.68E-02 0.00E+00 < 1.01E-01 0.00E +00 < 9.90E-02 0.00E +00 K 1.01E +01 1.09E +00 1.16E+01 9.80E-01 9.87E+00 9.65E-01 Mn-54 < 9.64E-03 0.00E +00 < 1.46E-02 0.00E + 00 < 1.25E-02 0.00E+00
. Co-58 < 8.42E-03 0.00E +00 < 1.33 E-02 0.00E +00 < 1.07E-02 0.00E +00
' Co < 8.66E-03 0.00E +00 < 1.55E-02 0.00E +00 < 1.21E-02 0.00E+ 00
- Zn-65 < 2.05E-02 0.00E+00 < 3.37E-02 0.00E +00 < 2.97E-02 0.00E+00
. Sb-125 < 2.69E-02 0.00E +00 < 3.39E-02 0.00E+00 < 3.36E-02 0.00E +00 I 131 < l .02E-02 0.00E+00 < 1.23 E-02 0.00E +00 < 1.39E-02 0.00E+00
' Cs-134 - < 8.75E-03 0.00E + 00 < 1.22E-02 0.00E+00 < 1.16E-02 0.00E+00 Cs-137 2.48E-02 9.22E-03 < 1.43E-02 0.00E+00 3.35E-02 1.30E-02 j Eu-152 ' < 2.49E-02 0.00E +00 < 2.46E-02 0.00E + 00 <2.93E 02 0.00E+00 Eu-154 - < 1.77E-02 0.00E +00 < 1.74E-02 0.00E+00 < 2.06E-02 0.00E + 00 TI-208 2.44E-01 2.24E-02 2.69E-01 2.59E-02 2.40E-01 2.25E-02 l Bi-2121 7.96E-01 1.61E-01 8.53E-01 2.03E-01 7.11E-01 2.16E-01
. Pb-212 9.03E-01 4.24E-02 9.50E-01 4.40E-02 8.47E-01 4.55E-02 Bi-214 1.26E+ 00 6.31E-02 1.36E +00 7.62E-02 1.32E +00 6.79E-02 Pb-214 1.29E+ 00 7.82E-02 1.52E +00 9.llE-02 1.28E + 00 8.38E-02 Ra-226* - -
1.29E +00 7.82E-02 1.52E+00 9.11E-02 1.28E +00 8.38E-02
- Ac-228 6.94E-01 4.18E-02 7.19E-01 5.24E-02 6.89E-01 4.84E-02 l l
- Th-234 1.28E + 00 1.43E-01 1.56E +00 1.84E-01 1.09E +'X) 1.64E-01
.U-235 1.76E-01 2.03E-02 1.96E-01 1.87E-02 1.74E-01 2.27E-02 Am-241 < 2.23E-02 0.00E +00 <5.09E02 0.00E +00 < 2.55E-02 0.00E +00 Yables for Final Status Soil Populations for Building KA-2 West Line Revision 0 March 1999 Page 9
O O TABLE 3.
(Continued) gO 3 /G f Li
~ EL# 99-0146 EL# 99-0147 EL# 99-0148
- Analytical ' Result c 20; - Result 20 Result 20-i
' Parameter - . (pC1/g) 1 (pCilg) (pC1/g) - (pCi/g) ' (pCl/g)' (pCi/g)
Be-7 ' < 9.25E-02 0.00E+00 <1.I1E-01 0.00E+ 00 < 9.07E-02 0.00E +00 1640.- 1.26E +01 1.18E+00 1.llE +01 1.30E+00 1.08E+01 8.36E-01 Mn-54.. < 1.14E-02 0.00E +00 < 1.41E-02 0.00E + 00 < 1.24E-02 0.00E+00 Co-58 ' < 9.95E-03 0.00E +00 < l .23E-02 0.00E+00 < l .13 E-02 0.00E+00 t
~Co40; < 1.07E-02 0.00E+00 < l .35E-02 0.00E +00 < l.24 E-02 0.00E +00 Zn45L < 2.35E-02 0.00E+00 < 2.99E-02 0.00E+ 00 < 2.84 E-02 0.00E +00 I
- Sb-125 < 3.35E-02 0.00E +00 < 3.62E-02 0.00E+00 < 3.09E-02 0.00E +00 I-131 < 1.34E-02 0.00E +00 < 1.50E-02 0.00E+00 < 1.21E-02 0.00E+ 00 Cs-134 < l .09E-02 0.00E+00 < 1.26E-02 0.00E+00 < 1.03E-02 0.00E + (, j Cs-137 < 1.22E-02 0.00E +00 4.44E-02 1.27E-02 < 1.28E-02 0.00E+00 Eu 152 < 3.13E-02 0.00E +00 < 3.20E-02 0.00E+00 < 2.58E-02 0.00E +00 Eu-154 < 2.22E-02 0.00E +00 < 2.29E-02 0.00E+00 < 1.82E-02 0.00E+00 c TI-208 2.74E-01 2.51E-02 2.60E-01 2.61E-02 2.68E-01 2.42E-02
. Bi-212; 8.00E-01 1.82E-01 6.45E-01 1.92E-01 8.57E-01 1.86E-01 Pb-212 - 9.40E-01 5.32E-02 1.03E + 00 5.08E-02 8.17E-01 4.32E-02
. Bi-214 1.64E+00 7.53E-02 1.53E+00 8.39E-02 1.53E+00 7.49E-02
' Pb-214 i 1.69E +00 1.03E-01 1.54E +00 9.89E-02 1.52E+ 00 8.95E-02 Ra-226' l.69E+00 1.03E-01 1.54E+ 00 9.89E-02 1.52E +00 8.95E-02
. Ac-228 ' 7.93E-01 5.13E-02 7.28E-01 5.29E-02 7.17E-01 4.72E-02 Th-234 1.32E +00 1.96E-01 1.48E+00 1.97E-01 1.58E+00 2.24E-01
. U-235 - 2.36E-01 2.89E-02 2.33E-01 3.04E-02 2.00E-01 1.86E-02
' A.m-241 < 2.57E-02 0.00E +00 < 3.00E-02 0.00E +00 < 7.39E-02 0.00E +00 3
Tables for Final Status Sotl Populations for Building KA-2 West Line Revision 0 March 1999 Page 10
x._,- V TABLE 3.
(Continued)
[Dg :
u EL# 99-0149 EL# 99-0168 EL# 99-0169 -
Analytical Result to Result ' 20 Result -20 Parameter - (pCi/g) - (pCi/g) (pCilg) - (pCilg) - (pCilg) - :(pCi/g)
Be-7 < 1.07E-01 0.00E +00 < l .22E-01 0.00E+00 < 9.82E-02 0.00E+ 00 K-40 1.24E+01 1.34E+00 10.2 8.13E-01 1.06E+01 1.15E+00 Mn-54 < l .28E-02 0.00E +00 < l .56E-02 0.00E +00 < l .10E-02 0.00E +00 Co-58 < 1.11E-02 0.00E+ 00 < 1.41E-02 0.00E +00 < 1.00E-02 0.00E+00
- Co40 <l.18E-02 0.00E +00 < 1.53E-02 0.00E+00 < l .01E-02 0.00E+00 Zn45 < 2.73E-02 0.00E +00 < 3.24E-02 0.00E +00 < 2.41E-02 0.00E+ 00 Sb-125 < 3.56E-02 0.00E +00 < 3.88E-02 0.00E+00 < 3. I 1E-02 0.00E+ 00 I-131 - < 1.49E-02 0.00E+00 < 2.33E-02 0.00E+00 < l .97E-02 0.00E+00 '
Cs-134 < l .19E-02 0.00E +00 < l .33E-02 0.00E +00 < 1.05E-02 0.00E +00 Cs-137. 1.21E-01 1.51E-02 < 1.61 E-02 0.00E+00 2.27E-02 7.92E-03 i Eu-152 < 3.17E-02 0.00E+00 < 3.21E-02 0.00E+ 00 < 2.86E-02 0.00E +00 Eu-154 - < 2.25E-02 0.00E + 00 < 2.26E-02 0.00E +00 < 2.04E-02 0.00E +00 TI-208 2.62E-01 2.76E-02 5.71E-01 4.18E-02 2.73E-01 2.59E-02 Bi-212 8.44E-01 1.93E-01 1.85E +00 2.89E-01 1.09E+00 1.92E-01 i Pb-212 - 1.02E+00 5.03E-02 1.77E+00 8.28E-02 1.13E+ 00 5.23E-02 Bi-'214 1.33E +00 7.28E-02 1.45E+00 7.78E-02 1.64E +00 7.78E-02 Pb-214 '- 1.39E +00 8.70E-02 1.48E + 00 8.99E-02 1.67E + 00 1.01E-01
- Ra-226' l.398 +00 8.70E-02 1.48E +00 8.99E-02 1.67E +00 1.01E-01 ,
l Ac-228 7.76E-01 5.12E-02 1.58E + 00 8.06E-02 8.06E-01 4.99E-02 Th-234 ' l .31E+00 4.43E-01 2.19E +00 2.85E-01 1.36E+ 00 1.70E-01 U-235 < 2.60E-02 0.00E+00 1.94E 01 1.96E-02 2.15E-01 2.45E-02 Am-241 - < 2.81E-02 0.00E+ 00 < 9.30E-02 0.00E+00 < 2.57E-02 0.00E+00 Tsbles for Final Status Soil Popula: ions for Bmlddig KA-2 West Line Revmon0 March 1999 Page!I
~ -
O TABLE 3.
O (Continued) l EIJ 98 0170 L AnalyticalJ .Readt i20!
Paran=*ar -(pCi/s)i
- -(pCUg) :-
- Be-7;< < 1.02E-01 0.00E+00
- E-40 -l 1.02E +01 8.73E-01 Sin 54l < 1.45E-02 0.00E+00
' 1 Co-58).: < 1.35E-02 , 0.00E+00 gCo40[ < 1.44E-02 0.00E+00
. Zn 45:; < 3.29E-02 0.00E+00
' Sb-125 i < 3.32E-02 0.00E+00 I-131:. < 2.01E-02 0.00E+00
- Co-1343 < 1.19E-02 0.00E+ 00 1C5-137/ < 1.42E-02 0.00E+00 -
Eu-152 ? < 2.41E-02 0.00E+00
'; En-1541 < 1.69E-02 0.00E+00
- TI-208 : 2.87E-01 2.67E-02 1 81-2121 9.12E41 ~ 2.00E-01 M Pb-2123 1.03E+00 - 4.53E l Bi-2142 1.46E +00 7.71E-02 i Pb-214:'- 1.54E+00 9.10E-02
- RaL226' : 1.54E +00 9.10E-02 i' Ac-2281 7.92E-01 5.18E-02 Th-2340 1.55E +00 1.81E-01
? U'-235 1.85E 1.85E-02 l T Am-241 S < 4.91E-02 0.00E +00 Ra 226 assumed to be in seguilar equilibrium with Pb-214.
o W.
2 .
4 m ,, , -
m , -
Tables for Rnal Status Soil Populations for Building KA-2 West Line Revision 0 March 1999 Page 12
O TABLE 4.
O BUILDING KA-2 OUTSIDE WEST LINE SOIL POPULATION ESTIMATED ACTIVITIES {
g
- Net Activity Conc'entration (pCi/g):1 n;.
'EL89 0150 t - EL#99-0151 EL#99-01521 FL#99 4153 c ' EL#99-0154I EL#99-0155 i Radionuclide JPop #1 : i Pop #2 L Pop #3 : - Pop #4 ? - Pop #5 -- ' Pop #6 i
- U-234*0 < 0.16 < 0.19 < 0.18 < 0.16 < 0.19 <0.19 i
LU-2356;! <0.01 . < 0.02 < 0.02 < 0.02 < 0.01 < 0.02
, U-238' <0.16 '<0.19 < 0.18 < 0.16 <0.19 < 0.19 c'Ih-228d-3: 0.18 0.11 0.17 0.11 0.16 i 0.11 0.13 i 0.11 0.19 i 0.11 0.28 0.11
, Th-232'i <0.05 <0.05 < 0.04 < 0.04 < 0.05 < 0.04 1 Total Ut 0.33 0.40 0.38 0.34 0.39 0.40 l
- Total Th - 0.23 0.22 0.20 0.17 0.24 0.32
' Cs-137 - < 0.01 < 0.01 < 0.01 < 0.01 < 0.01 ' <0.01 Co 60 c < 0.02 < 0.01 < 0.01 - < 0.01 < 0.01 <0.01
== ,
- Fraction ob 0.04 0.04 0.03 0.03 0.04 0.05 1the I. ins'-
Estimated, based on U-238 to U-234 activity ratio of 1:1 for processed uranium with natural uranium activity ratios.
6 Activity concentration assumed to be the MDA value in the absence of a positive result.
U-238 assumed to be in secular equilibrium with Th-234.
8 Th-228 assumed to be in secular equilibrium with Pb-212.
Th-232 assumed to be in secular equilibrium with Ac-228.
' Fraction of Limit is calculated using the standard mixture equation: sI where A, = activity i L, !
concentration of nuclide in pCi/g and 4 = limit of nuclide in pCi/g. Limits are: Total U = 30 pCi/g; Total Th =
10 pCi/g (Th-228 @ SpCi/g + Th-232 @ 5 pCi/g); Cs-137 = 15 pCi/g: Co-60 = 8 pCi/g.
Tables for Final Status Soil Populations for Building KA-2 West Line Revision 0 March 1999 Page 13 l
.r Ns\}
TABLE 4. ,
hO zj (Continued) [~
Net Activity Concentration (pCi/g)
~
EL#99-0156 : EL#99-0158 ' EL#99-0159 EL#99-0160 ELh99-0161 EL#99-0140 Radionuclide L Pop #7; Pop #9 Pop #10 Pop #11 Pop #12 ' Pop #13 -
l- U-234' ' < 0.17 < 0.20 < 0.18 < 0.17 <0.17 < 0.16 L U-2356 ~ < 0.01 < 0.02 < 0.01 < 0.02 < 0.01 < 0.01
' U-238' .-
< 0.17 <0.20 <0.18 < 0.17 < 0.17 < 0.16 cTh-2288. 0.33 0.11 0.42 t 0.11 0.15 0.11 0.21 0.11 0.35 0.11 0.13 0.11
- Th-232' ' < 0.05 < 0.05 < 0.04 < 0.04 < 0.06 < 0.03
? Total .U -. 0.35 0.42 0.37 0.36 0.35 0.33 TotalTh : 0.38 0.47 0.19 0.25 0.41 0.16 J Cs-137 - < 0.02 <0.02 <0.01 < 0.01 < 0.01 < 0.01
' Co < 0.02 < 0.01 < 0.01 < 0.01 < 0.02 <0.01 Fraction of1 0.05 0.06 0.03 0.04 0.06 0.03 the Limit' Estimated, based on U-238 to U-234 activity ratio of 1:1 for processed uranium with natural activity ratios.
6 Activity concentration assumed to be the MDA value in the absence of a positive result.
U-238 assumed to be in secular equilibrium with Th-234. {
d Th-228 assumed to be in secular equilibrium with Pb-212.
Th-232 assumed to be in secular equilibrium with Ac-228.
' A Fraction of Limit is calculated using the standard mixture equation: s1 where Ai = activity
!= Li concentration of nuclide in pCi/g and41 = limit of nuclide in pCi/g. Limits are: Total U = 30 pCilg; Total Th =
10 pCug Th-228 @ SpCi/g + Th-232 @ 5 pCi/g); Cs-137 = 15 pCi/g; Co-60'= 8 pCi/g.
I 8
Tables for Final Status Soil Populations for Butiding KA-2 West Line Revision 0 March 1999 Page 14 I
]
~
O TABLE 4.
O .
(Continued) hOj
.J Net Activity Concentration (pCilg)
EL#99-0143 ' EL#99-0144 'EL#99-0146 EL*99-0147 EL#99-0149 - EL#99-0166 Radlunuclide Pop #16 : Pop #17 Pop #19 Pop #20 ' Pop #22 Pop #23 -
U-234' " <0.15 <0.16 < 0.18 < 0. I 8 <0.17 0.50 0.48
- U-2356) < 0.01 < 0.01 <0.02 <0.02 < 0.03 <0.02 U-238*; <0.15 < 0.16 < 0.18 < 0.18 < 0.17 0.50 i 0.48 Th-228 d~ 0.13 t 0.11 0.18 i 0.11 0.17 i 0.11 0.26 i 0.11 0.25 i 011 1.00 0.13 Th 2321 < 0.03 < 0.05 < 0.04 <0.05 < 0.05 0.65 i 0.14
. Total U - 0.31 0.33 0.38 0.38 0.37 1.02 Total Th - 0.16 0.23 0.21 0.31 0.30 1.65 Cs-137 :- < 0.01 < 0.01 < 0.01 <0.01 < 0.01 < 0.02
' Co <0.01 < 0.02 < 0.01 < 0.01 < 0.01 <0.02 Fraction of 0.03 0.04 0.04 0.05 0.04 0.20
' the Limit' :
Estimated, basca on U-238 to U-234 activity ratio of 1:1 for processed uranium with natural activity ratios.
Activity concentration assumed to be the MDA value in the absence of a positive result.
U-238 assumed to be in secular equilibrium with Th-234 d
Th-228 assumed to be in secular equilibrium with Pb-212.
Th-232 assumed to be in secular equilibrium with Ac-228.
A Fraction of Limit is calculated using the standard mixture equation: dsI where A, = activity a: L i concentration of nuclide in pCi/g and iL = limit of nuclide in pCi/g. Limits are: Total U = 30 pCi/g; Total Th =
10 pCi/g (Th-228 @ SpCi/g + Th-232 @ 5 pCi/g); Cs-137 = 15 pCi/g; Co-60 = 8 pCi/g.
l Tat)les for Final Status Soil Populations for Building KA-2 West Line Revision 0 March 1999 Page 15
_ )
O TABLE 4.
O (Continued) hO A Net Activity Concentration
- (pCi/g)
., j .
EL#99-0169 ' EL#99-0170 Radionuclide - Pop #24 - Pop #25:
L U-234' < 0.17 < 0.15 l
' U-2356 < 0.02 < 0.01
.U-238'i < 0.17 < 0.15 1 Th-228d 0.36 i 0.11 0.26 0.11 Th-232' . -'_ < 0.04 < 0.05
- Total UL 0.36 0.31 1 Total Th - 0.40 0.31 Cs-137 < 0.01 < 0.01 l Cc-60 L < 0.01 < 0.01 Fraction of e 0.05 0.04
' the Limit' '
Estimated, based on U-238 to U-234 activity ratio of 1:1 for processed uranium with natural activity ratios.
Activity concentration assumed to be the MDA value in the absence of a positive result.
U-239 assumed to be in secular equilibrium with Th-234.
Th-228 assumed to be in secular equilibrium with Pb 212.
Th-232 assumed to be in secular equilibrium v ith Ac-228.
' AI Fraction of Limit is calculated using the standard mixture equation: s1 where Ai = activity ii L, concentration of nuclide in pCi/g and 4 = limit of nuclide in pCi/g. Limits are: Total U = 30 pCi/g; Total Th =
10 pCi/g (Th-228 @ SpCi/g + Th-232 @ 5 pCi/g); Cs-137 = 15 pCi/g; Co 8 pCi/g.
l l
t I
Tables for Final Status Soil Populations for Building KA-2 West Line Revision 0 March 1999 Page 16
i O O OBaHelle Puttmg lechnology To Work 505 King Avenue Columbus, Ohio 43201-2693 Telephone (614) 4244424 facsimile (614) 424-5263 February 26,1999 Mr. G. Mike McCann Senior Radiation Specialist Decommissioning Branch U.S. Nuclear Regulatory Commission Region III 801 Warrensville Road Lisle, IL 60532-4351 '
I
Dear Mr. McCann:
Amendment Request to Battelle Memorial Institute's Special Nuclear Material License, SNM-7, and Hyproduct Materials License 34-26608-01 Battelle Columbus Operations (Battelle) requests amendments to its licenses SNM-7 and (soon to be issued) 34-26608-01, to move Craig E. Jensen from Associate Radiation Safety Officer to Radiation Safety Officer (RSO) for both licenses. In conformance with the NRC requirement that licensees both request and obtain a license amendment prior to changing its RSO, I will continue to be Battelle's RSO in the interim period.
Since Mr. Jensen is a long time member of Battelle's Safety organization, and has acted for me on numerous occasions, this change will have vinually no impact to the radiation protection organization. I have accepted a temporary long-term assignment that takes me away from Battelle'vColumbus, Ohio operations area for periods of time. With major licensing actions nearing completion on both licenses, it was felt that initiating a change at this time would preclude the appearance of degradation in radiological control, and would provide Battelle with ,
the on-site level of radiation protection support that was appropriate for the operations being conducted. I will continue to be available to consult with Mr. Jensen, and do and will plan to continue to be physically available to attend required meetings, e.g., Quarterly RSC meetings during this changeover period.
Mr. Craig Jensen is a health physicist certified in the comprehensive practice of health physics by the American Board of Health Physics, with over 16 years of experience in the Radiation Protection field, including both the NRC R&D, life sciences, and the DOE regulatory arenas.
Since Mr. Jensen is already listed on the licenses as Associate Radiation Safety Officer, his resume and qualifications are on file with the NRC. Mr. Jensen is eligible for the position according to Commission guidelines.
MAR 0 21999
0 0 Mr. G. Mike McCann February 26,1999 Page 2 In anticipation of a usual NRC approval cycle on this matter, the effective date of this change will be April 1,1999. This also serves as the notice to the NRC in writing when the RSO permanently discontinues performance of duties under the license (s). If you have any questions regarding Mr. Jensen or his qualifications, please do not hesitate to call me at 516-344-7921 or 614-424-3885. '
i l f Sincerely, 7
Stephen J, Layendecker, CHP Safety Health and Environmental Support Manager / Radiation Safety Officer F
7 ..
g g
,s.
OBaHelle
. Puning lechnology la Work s05 King Avenue Columbus, Ohio 432012693 Telephone (614)424-6424 Facsimile (614)424 s263 Mr. G. Mike McCann Senior Radiation Specialist Decommissioning Branch U.S. Nuclear Regulatory Commission Region III 801 Warrensville Road Lisle, IL 60532-4351
Dear Mr. McCann:
Subject:
Battelle Memorial Institute Special Nuclear Materials License SNM-7, Docket 070-00008
Reference:
- 1. Letter from George M. McCann to Steve Layendecker,"Battelle Columbus Laboratories Decommissioning Project (BCLDP)- Request to Change Decommissioning Schedule, Review of BCLDP Procedure, ' Control of Revisions to Radiation Protection Program Documents'(HP-AP-36.0), Clarification of Radioactive Material License Possession Limits," dated January 21,1999
- 2. Letter from Steve Layendecker to George M. McCann, " Request for a Schedule Revision to the BCLDP," dated December 8,1998 The following are Battelle Memorial Institute's responses to the NRC correspondence dated, January 21, 1999, Mail Control Number 397559, with regard to the Battelle Memorial Institute Decommissioning License SNM-7, Docket 070-00008.
Revision to BCLDP Decommissionine Schedule Battelle has provided the local Department of Energy (DOE) Project Manager, Mr. Thomas Baillieul, a copy of the January 21,1999 referenced letter. The BCLDP Manager, Mr. Len Ermold and Mr. Baillieul have talked on this issue. Since this is a complex issue with significant ramifications, Battelle requests a
' 60-day extension be granted to respond to this subject.
FEB 0 8189
i ,.
1..
Pronosed IIealth Physics Administrative Procedure GIP-AP-36.0)
Attached, please find the two finalized procedures you had previously reviewed in draft, HP-AP-36.0, Rev 0, Control ofRevisions to Radiation Protection Documents, and QD-AP-6.1, Rev 10, Document Control. The QD-AP-6.1 procedure contains the forms not in the HP-AP-36.0 procedure and is the only cross-referenced procedure.
Clarification of License Possession Limits Battelle has reviewed its recent submissions to the NRC on SNM and Source possession limits, specifically, SNM-7 major amendment submission dated September 1,1994 to Mr. Kevin Null and the last complete presentation of Battelle's possession limits in Amendment 10 dated April 27,1995.
Battelle has updated the possession limits to reflect current knowledge. Please note that they are not significantly different than either of the previously identified quantities, except for the shifting of the majority of the unirradiated fuel inventory to irradiated, and decreasing the source material inventory due to progress in clean up of the major locations of source material use, which were almost entirely at King Avenue.
Special Nuclear Material Chemical or Physical Maximum amount to be Form Possessed at one time A. Uranium enriched in the A.Any A.125 grams of contained U-235 U-235 isotope plus the associated and unseparated
- Irradiated plutonium B. Uranium enriched in the B.Any B.10 grams of contained U-235 U-235 isotope
- Unirradiated C. Uranium enriched in the C. Plated / Sealed C. I gram of U-235 total U-235 isotope
- Unirradiated D. Plutonium (any principal D. Sealed Sources D. 0.1 gram total isotope Pu 238-244 )
E. Plutonium (Pu-238 principal E. Oxide E.10.3 grams isotope)
F. Plutonium (Pu-239 principal F. Metal or Oxide F.17 grams isotope)
G. Neptunium-237 G. Sealed Source G.1.0 microcurie I
H. Plutonium (Pu-238 principal H. PuBe Source H. 0.053 grams i isotope)
I. Plutonium (Pu-238 principal I. Diffuse Waste 1. 3.4 grams I isotope) i
.r.
4
~'
N
(
() V
~
J. Plutonium (Pu-239 principal J. Diffuse Waste J. 3.0 grams isotope)
Source Material Chemical or Physical Form Maximum amount to be j
~
Possessed at one time A. Any Source Material A.Any A. 50 kilograms total
.As you had requested, I am also providing a summary 10 CFR 150.11 calculation.
U-235 Components Pu Components A.125 grams A.131.2 grams B.10 grams B. O grams C. I grams - C. O grams D. O grams D. 0.1 grams E. O grams E.10.3 grams F. O grams F.17 grams II. O grams II. 0.1 grams I. O grams I. 3.4 grams J. O grams J. 3.0 grams Sum divided by 350 = 136/350 = 0.389 Sum divided by 200 = 165.1/200 = 0.826 Grand Total (U + Pu Subtotals) = 1.215 i Since the formula yields a sum of fractions greater than 1.0, the exception granted in Section 150.10 does not apply. As you recall, the plutonium in Item A was generated from the irradiation of U-235 which to approximately 33 kMWD/MTU.
If you have any questions, please do not hesitate to call me at (614) 424-3885, or my Associate RSO, Craig Jensen at (614) 424-5170.
Sinc ,
S.
Stephen J. L endec r, P Safety IIealth and En ironmental Support Manager / Radiation Safety Officer Attachment (2)
o o
%)Banelle
. . . Putting Technology To %k HP-AP-36.0 Resision 0 DECONTAMINATION AND DECOMMISSIONING OPERATIONS (DDO)
HEALTH PHYSICS ADMINISTRATIVE PROCEDURE (HP-AP) i Control of Revisions to Radiation Protection Program Documents L \00 nil 01ED CON BATTELLE 505 King Avenue Columbus, Ohio 43201 Procedure Status:
(X] Non-Critical Procedure
[ ] Critical Procedure - Procedure Qualification Packet (PQP) Required
l
.. o o 1
. . . Putting Technology To Work REVISION RECORD INDICATING LATEST DOCUMENT REVISION Title Control of Revisions to Radiation Protection Program Documents No. HP-AP-36.0 I I
Page_iof_li INDEX OF PAGE REVISIONS Page No. i ii Rev.No. 0 0 l 1
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Page No. 1 2 3 4 5 6 7 8 9 10 Rev. No. 0 0 0 0 0 i i
I Page No. 11 12 13 14 15 16 17 18 19 20 l Rev. No. 0
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Page No. 21 22 23 24 25 26 27 28 29 30 j Rev. No.
Page No. 31 32 33 34 35 36 37 38 39 40 Rev. No.
L' REVISION RECORD - ' REVISION RECORD l
Rev. No. Date Rev. No. Date !
CURRENT REVISION:
Rev. No. O Issue Date '/01-/ 99 Issued By 4/$
DDOM, Rev. 3 (09/93) Lar A
1
.., (n.
, )
n HP-AP-36.0 Revision 0 j Page ii ofii PROCEDURE APPROVAL PAGE Prepared By:
{
[M C C.'E. Jense@
/70eade~ler/
Date This procedure, HP-AP-36.0, Control of Revisions to Radiation Protection Program Documents, has been reviewed and approved by the following:
a WJrln A3ll1l48 d .Layendecked 'Date Safety, Health and Environmental Support Manager NJ E 12/ n %g_
M. E. Jackson 9 Date Regulatory Compliance, Environmental, Safety, and Health Oversight Manager
/.:2 // 7 3:-
L. Ermold 8 /
Date BCLDP Operations Manager d!H. Eriksen M c-/n / %
' 6 ate '
({ Quality Manager Q:\ PROJECTS'6 AFETY~lWPRIL'STROCEDURTCLDP\HPAP36 1.RVO
O- C)
HP-AP-36.0 Revision 0 Page1 of5 CONTROL OF REVISIONS TO RADIATION PROTECTION PROGRAM (RPP) DOCUMENTS 1.0 ' Scope This document applies to the review of revisions to RPP documents used for Decontamination and Decommissioning (D&D) Operations. See Section 3.3 for a definition of"RPP Documents."
2.0 Purpose The purpose of this procedure is to provide a review of revisions to RPP Documents to assure that there has not been a reduction of the radiological protection afforded D&D activities as a result of the revision. This review als,o assures that the revision does not violate or invalidate previously agreed to regulations, agreements, or commitments.
This procedure is written in response to a request from the Nuclear Regulatory Commission Region III (N.RC) to conduct reviews on the D&D Program RPP Documents similar to those required in Reference 3.2.1.
3.0 Bffirrargs. Developmental Resources. and Definitiom i
1 3.1 References i 3.1.1 QD-AP-6.1, Documents Control 3.2 Developmental Resources 3.2.1 10CFR50.59, Changes, tests, and experiments 3.3 Definitions 3.3.1 Radiation Protection Procram (RPP) Document - Those procedures, i plans, and technical basis documents which define the RPP for D&D activities. This includes, but is not limited to, all HP-AP-XX, HP-OP-XX, EM-SP-XX (radiological topics only), EP-IP-XX (radiological topics only), RS-AP-XX, RS-OP-XX, TD-AP-04.0, and TD-AP-05.0.
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HP-AP-36.0 Revision 0 Page 2 of 5 4.0 : . General The intent of this procedure is to help ensure maintenance of the radiological safety
margin of the BCLDP Radiation Protection Program through its implementing plans and procedures. The BCLDP document revision review will adopt the evaluation process in
. the general form of one used in the commercial nuclear power industry (10CFR50.59).
The principal test used is an evaluation whether the proposed change results in a decrease in the radiological safety envelope relative to the radiological risks of the project.
- 5.0 Responsibilities 5.1' Procedure authers are responsible to designate reviewers to implement this i
procedure, and provide the DDO-341 form as part of the review and conunent
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process for RPP Documents. j 5.2 . - Reviewers designated to perform the review required by this procedure are to perform the review in accordance with this procedure, document their review on Form DDO-341, obtain the concurrence of the Radiological Safety Officer
. (RSO), and return the completed DDO 341 to the requesting author.
5.3 _ The RSO either concurs with the review results done by the designated reviewer I l
c or directs actions to allow concurrence with the results documented on DDO- 1
-341.
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6.0 Procedure
' 6.1 - . Proccdure Revision 6.1 ' 1 Procedure authors prepare Review and Comment packages for i
procedure revisions in accordance with Reference 3.1.1. 8 6.1.2 For RPP Documents, a review in accordance with this procedure is required.
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o o HP-AP-36.0 Revision 0 Page 3 of 5 6.1.3 Procedure authors designate the reviewer for this procedure by writing "HP-AP-36.0 Review" on the DDO-192 form under " Organization" I . and naming the reviewer. For this reviewer only, provide a blank Form
' DDO-341 in the package sent out.
6.2 - Procedure Retirement 6.2.1 Responsible managers and/or authors who retire RPP Documents are responsible for distributing the DDO-341 to the designated reviewer j and attaching the completed DDO-341 to the DDO-188 or procedure !
retirement memo in accordance with Reference 3.1.1.
6.3 ' Field Changes / Waivers 6.3.1 Authors are responsible for distributing the DDO-341 to the designated reviewer and attaching the completed DDO-341 to the DDO-398 in accordance with Reference 3.1.1.
6.4 Conduct of Review 6.4.1 The designated reviewer analyzes the revised portions of the subject procedure and answers the review questions on the DDO-341 by checking "yes" or "no" to the questions. The reviewer signs and dates the DDO-341, and presents it to the RSO for concurrence.
,, 6.4.2 ~ The RSO either concurs in the results of the review as done by the designated reviewer by signing and dating the DDO-341, or if disagreement exists as to review results, initiates steps to:
a Change the document revision to allow for a new review result, a Change the review result to allow for concurrence.
Once concurrence is reached, the RSO will signify this by signing and dating the DDO-341.
NOTE: If any of the questions on the DDO-341 are answered "yes,"
the RSO is responsible for providing direction / comments and arranging
, t Os HP-AP-36.0 Revision 0 Page 4 of 5 for any reviews, approvals, or submittals of the revised document as needed (e.g., RSC, NRC). In certain cases, procedure revisions will be denied by the RSO to prevent degradation of the radiation' protection program.
6.4.3 Once the DDO-341 is competed, the designated reviewer returns the completed form to the requesting author.
6.5 Comment Package Disposition 6.5.1 The procedure author includes the completed DDO-341 in the review and comment package (with the DDO-340s, DDO-192, and any other required documentation) and forwards it to Document Control in accordance with Reference 3.1.1.
7.0 Records 7.1 Project records resulting from implementation of this procedure are presented below. Document authors and their manager shall assure timely transmittal of all i records to Project liecords.
7.1.1 Completed DDO-341 forms NOTE: DDO-341 should not be sent to Project Records / Document
- i. Control as stand alone documents. They should be included as part of review and comment pacKat<es, procedure / plan retirement packages, or Field Change / Waiver packages.
8.0 Forms l 8.1 DDO-188, Procedure / Plan Assessment Form (see Reference 3.1.1) !
i 8.2 DDO-192, Review Assignment Form (see Reference 3.1.1) ]
8.3 DDO-340, Review and Comment Form (see Reference 3.1.1) l 8.4 DDO-341, Review of Revisions to Radiation Protection Program Documents !
8.5 DDO-398, Approval Form Procedure Change (see Reference 3.1.1) )
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- Y. Putting Technology To ntuk HP-AP-36.0 Revnsnon 0 Page 5 of 5 CONTROL OF REVISIONS TO RADIATION PROTECTION PROGRAM (RPP) DOCUMENTS To: (Author) _ , _ _ . Date:
Fr:m: (Reviewer) Requested Completion Date:
Document No., Revision No.: Document
Title:
NO YES
- 1. Does the proposed revision constitute a reduction in the radiation safety of the radiation protection program versus the previous revision?
- 2. Does the proposed revision require a change to the Decommissioning Plan, NRC license, regulatory submittals, Environmental Assessment, or the BCLDP Radiation Protection Plan?
- 3. Does the proposed revision increase the likelihood or consequence of radiological occurrences / events?
- 4. Does the proposed revision allow for a less conservative radiological release limit or a radiation dose limit than those O i described in the previous procedure revision, Decommissioning Plan, NRC license, regulatory submittals, Environmental Assessment, or the BCLDP Radiation Protection Plan?
Resolution / Comments NOTE: A "YES" answer to any of the above questions also requires RSO approval of the revision and may require the concurrence of the Battelle Radiation Safety Committee or the NRC.
Description of resolution / comments /further actions Reviewer Date Radiological Safety Officer Date i
DDO-341 12/98(sca) l 4
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. . . Putting Technology To %k QD-AP-6.1 Revision 10 DECONTAMINATION AND DECOMMISSIONING OPERATIONS (DDO)
QUALITY DEPARTMENT ADMINISTRATIVE PROCEDURE (QD-AP)
DOCUMENT CONTROL BATTELLE 505 King Avenue Columbus, Ohio 43201 UNC0HROED C0'Y i i!
l Procedure Status:
[X] Non-Critical Procedure
[ ] Critical Procedure - Procedure Qualification Packet (PQP) Required j
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. . . Putting 7bchnology To %k REVISION REC _ RD INDICATING LATEST DOCUMENT REVISION Titel Document Control No. OD-AP-6.1 Page _.L of _il INDEX OF PAGE REVISIONS Page No. I il lii Rev. No. 10 10 Page No. I 2 3 4 5 6 7 8 9 10 Rev. No. 10 10 10 10 10 10 10 10 10 10 Page No. 11 12 13 14 15 16 17 18 19 20 Rev. No. 10 10 10 10 10 10 10 10 10 10 Page No. 21 22 23 24 25 26 27 28 29 30 Rev. No. 10 10 10 10 10 10 10 10 10 10 Page No. 31 32 33 34 35 36 37 38 39 40 Rev. No. 10
'JREVISION RECORD - $REVIS10 RECOR'D Rev. No. Date Rev. No. Date 0 8/16/89 6 10/30/92 1 10/17/89 7 1/6/94 2 5/23/90 8 8/24/94 LCUR. RENT REVISION '
3 7/6/90 9 1/26/96 Rev. No. 10 4 7/31/91 9.1 3/29/97 Issue Date IOJ/14 5 5/12/92 Issued By $
DDoelo Revinian 3
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, QD-AP-6.1 Revision 10 Pageiiofii PROCEDURE APPROYAL PAGE Prepared By:
Aa-L &and u -n -99 Ruth Baruth, Document Control Manager Date This procedure, OD-AP-6.1 entitled Document Control, has been reviewed and approved by the following.
Approved By:
]M1k h 3/ bb ipll1/4A
/.SJ. Lafend'cker,8afety, e Heakl{and Environmental ' Date Support Manager 12!h 9%
M. E. Jackson, Regulator} Compliance, Environmental, Date
,, Safety, and Health Oversight Manager M /3l/1 9P L. F. 5rmold, DecontamiNon & Decommissioning Operations ' Dbte Manager Pm?OW d 'H. Eriksen, Quality Manager
%'/N99 Date
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o o QD-AP-6.1 Revision 10
. Page 1 of 31 DOCUMENT CONTROL 1.0 Scope
'Ihis document applies to the review, approval, distribution, and control of all Battelle Columbus Laboratories Decommissioning Project (BCLDP) documents that prescribe activities affecting the quality of the Decontamination and Decommissioning Operations (DDO) program. 'Ihis includes documents that establish policies, prescribe or plan operations, and specify work requirements or methods.
2.0 Euranse The purpose of this procedure is to establish consistent requirements and methods for the review, ;
approval, distribution, and control of documents that prescribe activities affecting the quality of the DDO program.' This procedure, in conjunction with Reference 3.1.1, implements the requirements of the DDO Quality Manual, Section 6.0 (Reference 3.1.2).
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. 3.0 References and Definitions !
3.1 - Referene 3.1.1 QD-AP-5.1, Preparation of Procedures 3.1.2 ' DDO Quality Manual 3.1.3 DD-92-04, Readiness Reviews 3.1.4 DOE 5700.6C, Quality Assurance 1 3.1.5 TD-AP-3.0, Qualification for Critical Procedures 4, 3.1.6 QD-AP-15.1, Nonconformance Reporting for Activities, items and Materials j 3.1.7 ' HP-AP-36.0, Review of Revisions to Radiation Protection Program Documents l 3.2 Definitions Per Reference 3.1.4, documents to be controlled include drawings, data files, computer codes, I
. procedures, work instructions, data sheets, and other items. Within BCLDP, all quality documents of this type are handled in a " controlled" manner. However, signature sheets are only required for Controlled Documents as defined below.
3.2.] cnnernited Document - A document describing, defining, specifying, reporting, or certifying the quality of an activity, item, or service. The preparation, issue, distribution, and use of Controlled Documents are subject to specified requirements, i
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QD-AP-6.1 Revision 10 l Page 2 of 31 reviews, and approvals. A signed receipt for a specifically numbered copy is required ,
from the recipient to verify possession. !
3.2.2 Critical Pror adure - Procedures whose incorrect performance would pose an immediate or direct threat or danger to D&D workers or members of the general I public. Reference 3.1.3 lists the criteria which, when met, constitute a critical action.
3.2.3 Deviation - A planned or unplanned departure from specified requirements. A deviation may be a characteristic outside specifications or failure to follow accepted, j documented procedures. Frequently, planned deviations are permitted when written authorization, e.g., a waiver or emergency change is obtained prior to the planned i 1
departure from specified requirements. Unplanned deviations are handled as '
deficiencies and nonconformances.
3.2.4 Document - Any written or pictorial information describing or defining activities, requirements, procedures, and plans or reporting of results. )
3.2.5 Field Change - Changes made to a document without entering the revision process.
Signatures of the responsible manager, RC&ESHO Manager or designee, Quality representative, and Safety, Health and Environmental Support Manager or designee (as appropriate for safety requirements) are required. Field changes expire when the. j next revision of the document occurs.
3.2.6 Official - For this procedure, the term applies to an assigned copy of a Controlled Document, e.g., an individual procedure from a controlled manual.
3.2.7 Procedure Oualification Packet (POP)- A package for critical procedure qualification which includes instructions, prerequisite information, a performance checklist, and a set of questions. The manager or qualifier uses this packet to test a candidate's knowledge of the critical procedure and his ability to perform the procedure to the standards and criteria presented in the PQP.
3.2.8 Retristered Document - A document requiring reviews and approvals prior to issue, and a documented distribution and issuance. No signature receipt is required for a j Registered Document and documents are not individually numbered. Revisions shall be issued to the registered recipients of the documents when the previous revision is rescinded.
3.2.9 Resnonsible Manager - The line manager with one-over-one approval authority who supervises the staff member assigned as the author of procedures and their revisions.
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.As used in this procedure, the responsible manager is the individual responsible for a !
set of defined organizational functions and, as the functional supervisor of subject matter experts, should normally be accountable for preparing and maintaining i
implementing procedures associated with that set of functions.
3.2.10 Unccmtrolled - For this procedure, the term applies to an unassigned, unregistered copy of a Controlled Document.
3.2.11 Walver - Documented authorization to deviate from specified requirements prior to commencement of the subject activity. This may cover an entire procedure or any portion thereof, and apply to a single activity or multiple operations. Waivers cannot add requirements or operations. Mandatory signatures shall include thz responsible manager, RC&ESHO Manager, Safety, Health and Environmera; Support Manager (as appropriate for safety requirements), and the Quality representative prior to the
. starting of the activity. Length of effect for waivers must be stated. ;
3.2.12 Radiation Protection Procram (RPP) Doctiment - Those procedures, plans, and technical basis documents which define the RPP for D&D activities. This includes, !
but is not limited to, all HP-AP-XX, HP-OP-XX, EM-SP-XX (radiological topics only), EP-IP-XX (radiological topics only), RS-AP-XX, RS-OP-XX, TD-AP-04.0, and TD-AP-05.0.
i 4.0 General i
4.1 Documents issued for review shall be on white paper and marked " Draft" on each page. After I i
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all review comments have been addressed, the procedure shall be issued on white paper for final approval with the " Draft" designation removed.
4.2 The document generation and review process should be planned e allow for a reasonable amount of time for reviewers to review documents. In general, ten working days should be the allowable time period required for document reviews. When necessary to achieve urgent project milestones, five working days is the minimum review time to be allowed. This minimum time should not be abused, however, to make up for lost time (by the author or others).
4.3 Documents will be assumed to have approval from reviewers who have not responded by the ;
stated due date. Late comments will be reviewed for importance and may be held for the next !
document revision. Comments to be considered for dispositioning, but not needing subsequent l
9 9 QD-AP-6.1 Revision 10 Page 4 of 31 resolution, may be denoted by the reviewer signing and dating both the Reviewer and Comment Resolution Complete spaces provided on Form DDO-340.
4.4 Governing procedures must be present at work sites where corresponding activities are being performed. For the purpose of this procedure, this means governing procedures must be present within the work site building or in an immediately adjacent building. For example, work crews in Buildings 2 or 3 could work to procedure documents present in Building 3.
However, it would gg be acceptable for a work crew in Building 7 to indicate their governing procedures are in Building 3. In all cases, workers must be able to demonstrate to their supervisor they are fully knowledgeable of the procedure requirements governing their activities.
4.5 - Procedures shall be designated as critical or non-critical on the cover of the procedure. The responsible manager concurs with this designation by signing and dating the approval page of the procedure.
4.6 As a condition for issue, procedures and plans submitted to Document Control must be accompanied by the review and comment package and software copies of the text and any new/ revised forms.
4.7 Document Control shall maintain a central repository for the most current version of document texts and forms. Software copies of a document to be revised should be obtained from this file by the authorized individuals (authors, secretaries, and managers). However, Document Control retains the right to question the reason for software copy requests and may require additional confirmation of need and/or approvals. Persons using software copies other than
- i. those from Document Control do so at their own risk since they may not contain the most L current version of the document text or form (s).
5.0 Repansibilities 5.1 Responsible managers are responsible for the preparation of procedures and plans for their functional activities. The authors and their managers designate the critical procedures used in I their functional areas and review completed PQPs for accuracy before forwarding them to the Training Manager. The authors and their managers are also responsible for assuring that all review comments have been documented, dispositioned, and resolved. When agreement cannot be reached, successive levels of management must be involved until resolution is achieved.
O O QD-AP-6.1 Revision 10 Page 5 of 31 5.2 Procedure authors designate the procedure as non-critical or critical, with documented concurrence from the responsible manager, Procedure authors, either individually or with assistance by the training staff, prepare PQPs for each critical procedure and may conduct the training and qualify staffin accordance with Reference 3.1.5.
5.3 The Quality Manager is responsible for the preparation of Quality Department Administrative-Procedures (QD-AP) and the Quality Manual.
5.4 The Project Records Manager is responsible for administering the Document Control System and shall fulfill the responsibilities of Document Control Manager.
5.5 Reviewers are responsible for performing thorough reviews of documents, documenting .
comments on Review and Comment Form DDO-340, providing written corrections or changes as needed, and resolving comments (if requested) with the document author or designee.
5.6 The approval signature of the Safety, Health and Environmental Support Manager certifies that a procedure or its subsequent changes have been reviewed to ensure that safety and health controls have not been lessened or degraded by implementation of the procedure or change.
5.7 Individuals using procedures and forms are responsible for insuring the procedures and forms are current and correct.
5.8 Authors of RPP Documents (see Section 3.2.12 of this procedure) are responsible for designating reviewers and obtaining review results in accordance with Reference 3.1.7.
6.0 Precedure 6.1 Document Review and Approval s 6.1.1 Quality Manual 6.1.1.1 The Quality Manager shall prepare or revise the Quality Manual to satisfy contractual requirements for quality.
6.1.1.2 ' The Quality Manager shall distribute draft copies of the Quality Manual for review to the BCLDP Operations Manager and all DDO managers j reporting to the Operations Manager. Forms DDO-340 and DDO-192 l
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will be attached to each document distributed for review. Additional l reviewers may be designated by the Quality Manager.
6.1.1.3 Reviewers shall return completed Review and Comment forms to the Quality Manager who shall dL ssition the comments (see Sections 5.2 and l 6.1.2.4 of this procedure), complete the resolution by acquiring
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QD-AP-6.1 l '
Revision 10 Page 6 of 31 appropriate signatures on the review forms, and revise the draft Quality Manual to contain the resolved changes.
6.1.1.4 The BCLDP Operations Manager and Quality Manager shall sign approval on the heading of each section of the Quality Manual. Additionally, the Battelle Columbus Operations Vice President for Environment, Safety, Health, & Quality shall sign approval of the Quality Manual Policy Statement. After all signatures have been obtained, the Quality Manager shall forward the Quality Manual to the Document Control Manager for issue along with the review and comment package and software copies of the text and any new/ revised forms, if any.
6.1.1.5 The Document Control Manager shall issue the Quality Manual as a I Controlled Document according to a distribution list provided by the Quality Manager.
6.1.2 DDO Administrative, Quality, and Operating Procedures
- 6.1.2.1 The responsible manager shall prepare or assign a designee to prepare the procedure following the format and requirements of Reference 3.1.1.
6.1.2.2 The responsible manager / designee shall distribute the draft procedure with Forms DDO-340 and DDO-192 for review to the Regulatory Compliance
' & Environment, Health and Safety Oversight (RCE3HO) Manager; the Safety, Health and Environment Support Manager; a technical reviewer, preferably with experience in the subject activity; the Quality Manager;
+ and all DDO managers whose organizations may be impacted by activities addressed in the document. For RPP Documents (see Section 3.2.12 of this procedure), in addition to the above required reviewers, a review in accordance with Reference 3.1.7 is also required. The designation "HP-AP-36.0 reviewer" will be incled on the DDO-192 list of reviewers and a DDO-341 form, " Review of Revisions to RPP Document," will be j distributed to the assigned HP-AP-36.0 reviewer. Additional reviewers may also be selected. Responsible managers may assign the review to a i
/. delegated individual (s) by filling in the bottom of Form DDO-192. Where the review has been delegated to more than one individual, the responsible manager will integrate all comments to assure that no contradictory 1
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,- i QD-AP-6.1 Revision 10 Page 7 of 31 comments from the same organization are submitted to the document author.
6.1.2.3 All reviewers shall review the procedure using guidelines in Exhibit I as applied to their areas of expertise and responsibility. HP-AP-36.0 reviewers will follow the guidelines set forth in that procedure. The responsible manager shall make sure reviewers are aware of these guidelines, i 6.1.2.4 All reviewers shall record their comments or corrections on the Review and Comment Form DDO-340 (or DDO-341) and return it with Form DDO-192 to the responsible manager / designee for resolution. Reviewers shall identif ' on the Review;and Comment forms the pages, sections, paragraphs and lines being commented on, indicate whether the comment does or does not require formal resolution by following the signature directions at the bottom of the DDO-340 form, and when applicable provide an acceptable alternative for the commented text of the document. The Review and Comment and Review Assignment forms (DDO-340 and DDO-192) shall then be returned to the responsible manager / designee by the stated due date.
6.1.2.5 The responsible manager / designee of the procedure shall make changes deemed appropriate, disposition comments made on the Review and Comment forms, and complete the resolution by acquiring signatures of u the reviewer and responsible manager / designee on the Form DDO-340 if required (see Sections 5.2 and 6.1.2.4 of this procedure). The draft procedure shall be revised to contain the resolved changes to the text. l 6.1.2.6 The responsible manager / designee shall return the final document to the !
responsible manager; Safety, Health and Environmental Support Manager; Regulatory Compliance, Environmental, Safety, and Health Oversight (RCESHO) Manager; and Quality Manager for signature on the ]
Procedure /P an Approval Page. For Administrative, Quality, and any other policy stating procedure, the BCLDP Operations Manager shall also be an approver. These are the minimum approvers and other approval signatures may be added at the discretion of the responsible manager.
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, V 'v QD-AP-6.1 Revision 10 Page 8 of 31 6.1.2.7 The responsible manager / designee shall forward the procedure to the Document Control Manager along with the review and comment package l
and software copies of the text and any new/ revised forms. I 6.1.2.8 The Document Control Manager shall initial and date the Current Revision block located in lower right corner of the Document Revision Record Page (DDO-009) prior to distribution. This date is the issue date (the date on which the document becomes effective but is generally not the distribution date).
p 6.1.3 Technical and Administrative Plans (Work Plans, Quality Plans, Characterization Plans, D&D Plans, or any other plan specifying technical or administrative activities) 6.1.3.1 The individual responsible for the activity, or a designee, shall obtain a documeat number from the Document Control Manager and initiate preparation of the associated plan using whatever format is required or deemed appropriate.
6.1.3.2 The review process as delineated in Sections 6.1.2.2 through 6.1.2.5 of this procedure shall be followed. Plan approvals should be in accordance with Section 6.1.2.6, as deemed appropriate by the responsible manager.
The plan shall be forwarded and issued as outlined in Sections 6.1.2.7 and 6.1.2.8 of this procedure.
6.2 Document Registcstion, Control, and Issue 6.2.1 Controlled Documents-
+ 6,2.1.1 Documents issued as Controlled, such as the Quality Manual, Health Physics Procedure Manual, and other controlled manuals desimated by the responsible manages, shall be identified by a completed c ed Controlled Document Transmittal Record (Form DDO-191).
6.2.1.2 The document author and responsible manager shall prepare the distribution list for individuals to be recipients of Controlled Documents after consultation with the Document Control Manager. At a minimum, all organizations impacted by a document shall be represented on distribution lists.
O O QD-AP-6.1 Revision 10 Page 9 of 31 6.2.1.3 All controlled manuals shall be numbered consecutively and each assigned to an individual by the Document Control Manager. A copy of the numbered document, and a correspondingly numbered Form DDO-191, shall be delivered or sent to each individual on the distribution list. The )
Form DDO-191 shall also be used to distribute revisions and supplements to the individuals on the distribution list.
6.2.1.4 'Ihe document will be considered Controlled by return of the signed Form DDO-191 to the Document Control Manager.
J 6.2.1.5 The Document Control Manager shall maintain a record file of all I Controlled Document receipts and distribute any revisions as Controlled Documents to the recipients of the initial Controlled Document, with instructions to destroy or void the preceding revision.
'6.2.2 . Registered Documents
'6.2.2.1 Documents to be issued as Registered shall be forwarded to the Document Control Manager for distribution at the completion of the required review and approval process.
6.2.2.2 The document author and responsible manager, upon consultation with the Document Control Manager, shall formulate the distribution list for Registered Documents. At a minimum, all organizations impacted by a document shall be represented on distribution lists.
6.2.2.3 The staff member distributing the document shall initial and date the t.
distribution list (Form DDO-200) attached to the document " original",
I thus registering the completion of the distribution.
6.2.2.4 The document " original" file copy and registered distribution shall be filed and maintained as a record by the Document Control Manager.
6.2.2.5 Instructions for revisions to Registered Documents shall be sent to recipients of the initial Registered Document as specified in Section 6.3 of this procedure.
6.2.3 Delinquency Document
' When custodians or others are delinquent in returning signature sheets (Form DDO-191) or other documents, the Document Control Manager should use Form DDO-201, Document Delinquency Notice, to remind them of their delinquency.
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. O O QD-AP-6.1 Revision 10 Page 10 of 31 6.3 Controlled or Registered Document Revisions 6.3.1 Minor document revisions should conform to the format of the most recent revision of that document. Examples of minor revisions include changes to correct grammatical or typographical errors and limited changes which do not significantly alter the document content, scope or purpose.
6.3.2 Minor revisions shall require approval by the responsible manager and the Quality Manager. Depending on the nature of the change, other approvals may be required as deemed necessary by the responsible manager and/or the Quality Manager.
6.3.3 Minor revisions require a document revision number change. The number after the decimal point must be increased sequentially with each minor revision change e.g.,
Revision 2 to Revision 2.1. For minor revisions, substitution of only the individually revised pages is obligatory. There is no limit to the number of minor revisions allowed prior to a major revision.
6.3.4 M40r revisions including major document format changes or changes which significantly alter the content or purpose of the document shall be reviewed and approved by the same process used for the initial review / approval of the document. A major revision requires that the number to the left of the decimal point be increased sequentially to the next whole number (e.g., Revision 2.1 to Revision 3) and I
replacement of the entire document upon review and approval.
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6.3.5 All revisions or changes must be identified on the page with a vertical bar in the j margin adjacent to the line or lines in which the corrections were made or by other l
- s. methods which highlight the changes. The revision number must also be documented in the appropriate box (es) on the Revision Record Indicating Litest Document Revision (Form DDO-009) located as one of the front pages in each document.
6.3.6 Registration or control of a revised document shall follow the same process as the original document. Revision distribution shall be made to all individuals identified as recipients of the current Controlled Document (Form DDO-191) or Registered Document (Form DDO-200). Recipients shall replace the entire document (for major revisions) or the revised pages (for minor revisions) in order to keep their controlled or registered documents current. Record copies of revised procedures will be marked
" superseded."
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. O O QD-AP-6.1 Revision 10 Page 11 of 31 6.4 Usage, Field Change, and Walvers of Controlled and Registered Documents 6.4.1 Controlled Documents 6.4.1.1 Documents issued as Controlled, will be distributed to specific custodians at locations throughout the work areas. This will ensure that DDO staff have immediate access to the correct and current procedures, plans, manuals, etc, 6.4.1.2 Documents with the words " Controlled Copy" shall be the only copies at the work site. They may include the entire manual or " Official" copies of procedures from controlled manuals. Official copies shall indicate the control copy number, the custodian's (issuee) signature, and the date issued on the cover page. Custodians should maintain lists of those official copies issued. Upon receipt of a revision, the custodian will issue new official copies to the staff on the list and retrieve and dispose of the outdated copies. This will ensure that current revisions of all controlled documents are being used.
6.4.1.3 Controlled Documents cannot be reproduced without approval of the custodian or issuee. Documents that are reproduced for other than use involving work activities will be stamped or marked " Uncontrolled Copy" and may be used as outlined in Section 6.4.2.
6.4.1.4 A document marked " Field Change" will consist of all changes (including marked up pages of a procedure, plan, or drawing) not in the latest o revision of the pertinent controlled document. The field changes shall be attached to a Form DDO-398 which contains the approval signatures of the designated managers. Field changes for RPP Documents must be reviewed in accordance with Reference 3.1.7 and DDO-341 form completed and attached to the DDO-398 to form a complete package.
6.4.1.5 The original copy of the approved field change shall be submitted to Document Control with any supporting information and copies must be present at all work stations where the subject document is being implemented. Document Control will maintain a log of field changes in force. Changes or deviations can also be documented on a Nonconformance Report (NCR), Form DDO-177 (see Reference 3.1.6).
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6.4.1.6 A waiver to a Controlled Document authorizes a deviation from the specified requirements and is attached to a Form DDO-398 showing the signatures of the designated managers prior to the commencement of the !
activity. Waivers to RPP Documents must be reviewed in accordance with Reference 3.1.7 and a DDO-341 form completed and attached to the DDO-398 to form a complete package. Waivers are distributed as in Section 6.4.1.5. !
l 6.4.1.7 An official copy of a Controlled Document may be used when entering a ,
i contaminated area. This copy will be marked " Contaminated Area Work l Copy" and will be disposed of with the radioactive waste at the completion l i
of the task.-
6.4.1.8 If a Controlled Document requires replacement because of wear and tear, the custodian shall call the Document Contrc! Manager to request a i replacement. The custodian shall specify the specific document with assigned copy number. Upon receipt of the document, the custodian shall sign Form DDO-191, Controlled Document Transmittal Record, and return it to the Document Control Manager.
6.4.2 UncontrnHed Documents 6.4.2.1 Copies of Uncontrolled Documents shall be marked or stamped
" Uncontrolled Copy" and used for information only.
6.4.2.2 These copies shall NOT be used in the field to guide work activities.
i.
They may be used for training, personal information, or other "Information Only" activities.
6.4.2.3 Copies of Uncontrolled Documents may be made from " Controlled Copies" with the custodians knowledge, or may be obtained from Document Control. They shall be marked or stamped appropriately (see Section 6.4.2.1 of this procedure).
6.4.2.4 Revisions of Controlled Documents shall not be issued to holders of Official or Uncontrolled Document copies.
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. O O QD-AP-6.1 Revision 10 Page 13 of 31 6.4.3 Registered Documents !
.6.4.3.1 Documents issued as " Registered" shall include plans, and operating and administrative procedures with a separate distribution list from the Controlled Documents.
6.4.3.2 Document users and task managers have the ultimate responsibility of having the correct and current revision (per Procedure Index) at the work
, $2.
6.4i3.3 A document stamped " Field Change" will consist of all changes not available in the latest revision, including marked up pages of a procedure, plan, or drawing where the appropriate approval signatures have been obtained as in Section 6.4.1.4. ;
6.4.3.4 A waiver to a " Registered" document becomes effective when the l signatures of the designated managers have been obtained as in Section 6.4.1.6.
6.4.4 Advance Conien 1
6.4.4.1 Procedures may be issued as Advance Copies prior to completion of the i normal review cycle (see Reference 3.1.1).
6.4.4.2 As a minimum, Advance Copies require the approval of the responsible 1
manager, SH&ES Manager, and the Quality Manager. 1 6.4.4.3 Advance Copies will carry the next revision level followed by the letter l
" A" and be issued on white paper with the " ADVANCE COPY" notation displayed on each page. !
6.4.4.4 Advance Copies are valid for 60 days, and may be extended for an additional 30 days with the written approval of the Quality Manager. !
6.4.4.5 At the conclusion of the review and comment cycle, the Advance Copy ;
will be replaced by a normally issued copy.
- a. If NQ comments were incorporated into the final version, the final version will drop the "A" from the revision number and be issued with the same revisien number as the Advance Copy on white paper (Advance Copy revision "2A" would be issued as final version revision "2").
- b. If ABN comments are incorporated into the final version, the final ;
version will go to the next numerical revision number and be issued l
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.. O O QD-AP-6.1
- Revision 10 Page 14 of 31 on white paper. (Advance Copy revision "2A" would be issued as final version revision "3").
' 6.5 Procedure Retirement 6.5.1- A procedure may be retired as a result of a biennial assessment or at any other time whenjustified and documented by the responsible manager. The request may be documented on either the DDO-188 " Procedure / Plan Assessment Form," or in a memo. An example of a retirement request memo is shown in Exhibit 2.
6.5.2 The request must receive the concurrence of the RC&ESHO Manager, SH&ES Manager, and Quality Manager as documented on the request memo. Failure to obtain a concurrence shall be escalated to the next level of management for resolution.
6.5.3 Retirement of RPP Documents must be reviewed in accordance with Reference 3.1.7 and a DDO-341 form completed and attached to the DDO-188 or retirement memo to form a complete package.
6.5.4 The Document Control Manager will notify the Training Department and all holders of a procedure that the document has been retired and to destroy or void the procedure. Record copies will be marked canceled and moved to a retired procedures file. The retired procedure will also be removed from the procedures' index.
6.5.5 The same process shall be used to retire out-of-date plans after the subject activity has been completed.
6.6 Biennial Assessment of Technical Procedures and Plans 6.6.1 Technical procedures and plans shall have a documented assessment of their conformance to current requirements and work practices and utility for continued support of actvities.
6.6.2 They shall be reviewed eveg two years based on the current issue or last major revision date (see Paragraph 6.3.4) to assess them for continued use as is, revision, or retirement.
6.6.3 This assessment shall be conducted by the section manager (or designee) responsible for the procedure or plan.
5.6.4 The assessment shall be documented using Form DDO-188.
6.6.5 The procedure index database shall be used to track the dates for biennial assessments of procedures and plans.
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. O-QD-AP-6.1 i' Revision 10 Page 15 of 31 6.6.6 The Document Control Manager shall send a Form DDO-188 with a copy of the ;
procedure or plan attached to the responsible manager. The response date shall be specified but at least two weeks should be allowed. l
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6.6.7 'lhe responsible manager or designw shall evaluate the procedure's or plan's current conformance to DDO activities and requirements and its continued utility.
6.6.8 ' The responsible manager or designee shall complete Form DDO-188 with a statement -
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, of his/her intentions (use as is, revise, retire, etc), and sign, date, and return the form )
to the sender by the date indicated.
6.6.9 Requests to retire a procedure shall follow the process in Section 6.5.
6.6.10 Document revision by the responsible manager or his/her designee shall satisfy the requirements of Section 6.3 of this procedure. )
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6.6.11. The completed form shall be filed in the permanent procedure folder in the Document I Control System.
6.6.12 The Document Control Manager shall take appropriate action based on the findings from the assessment and note them on the bottom of Form DDO-188 and in the )
procedure assessment data base.
6.7 Document Index An index lhting all active documents and their revisinns shall be issued quarterly at a minim >n to designated staff and locations by the Document Control Manager. Procedures which have associated PQPs shall be marked with a symbol (#) on the DDO Procedures Index. Included in this index will be an identification of the section manager or designee responsible for each listed document. The index shall be updated by the periodic issuance of a supplement listing documents issued and retired during the defined period. A procedures index is also available
]
from the computer network and is updated on a routine basis.
6.8 Forms Management 6.8.1 Forms referenced in a procedure are an integral part of the procedure and as such, I shall be appended to draft and final procedures for reference purposes. All DDO forms shall be traceable to at least one active DDO procedure, manual, plan, etc.
6.8.2 An index listing for all active forms and their revisions is maintained and issued quarterly at a minimum by the Document Control Manager. The forms index is also available on the computer network and is updated on a routine basis. Forms users are i
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. -) G QD-AP-6.1 Revision 10 Page 16 of 31 responsible for consulting the latest issued forms index and assuring that they are using the most current revision.
6.8.3 Form numbers for new forms shall be obtained from the Document Control Manager ;
or his/her designate and, when finalized, a software disk copy shall be provided to the Document Cordrol Manager for file and distribution at the time of procedure issue. I l
6.8.4 Revision of forms shall be accomplished under the authority of the manager I responsible for the related procedure. Form revision outside of procedure revision
)
i should be approved by the responsible manager with the date. After the revisions are complete, a computer software disk copy shall be provided to the Document Control Manager for file and distribution upon request.
-6.8.5 Identification of items to be entered on a summary-type data form (e.g., DDO-103) may be listed without changing the form revision number. However, a disclaimer indicating the dedicated use of the form shall appear as shown in Exhibit 3.
6.8.6 When conducting the biennial assessment of technical procedures, the staff member performing the assessment shall assure that the forms referenced in, and appended to the procedure are the most current versions and that the forms are consistent with the contents of the procedure and vice versa.
6.8.7 A supply of current forms used on a routine basis shall be available at designated ;
locations within Program office work areas.
7.0- Records a
7.1 Project records resulting from the implementation of this procedure are presented below.
Document authors and their manager shall assure timely transmittal of all appropriate documents to Document Control.
7.1.1 Approved copies of Controlled Documents 7.1.2 Approved copies of Registered Documents 7.1.3 Signed Document Control receipts 7.1.4 Initialed Registered Document distribution list 7.1.5 Completed Review and Comment Forms 7.1.6 Completed Procedure Assessment Forms 7.1.7 Completed Review Assignment Forms 7.1.8 Field Changes and Waivers
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o QD-AP-6.1 Revision 10 Page 17 of 31 7.1.9 Document Delinquency Notices 7.1.10 Document Distribution Memos 7.1.11 Completed Review of Revisions to RPP Documents Form 8.0 Fuhihlis Forms and Attachments 8.1 Exhibits 8.1.1 Exhibit 1, Document Review Guidelines 8.1.2 Exhibit 2, Example of Memo to Request Procedure or Plan Retirement 8.1.3 Exhibit 3, Example of Disclaimer for a Dedicated Data Form 8.2 Forms 8.2.1 DDO-009, Revision Record Indicating Latest Document Revision 8.2.2 DDO-177, Nonconformance Report (see Reference 3.1.6) 8.2.3 DDO-188, Procedure Assessment Fonn 8.2.4 DDO-191, Controlled Document Transmittal Record 8.2.5 DDO-192, Review Assignment Form 8.2.6 DDO-200, Document Registration-Procedure Distribution 8.2.7 DDO-201, Document Delinquency Notice 8.2.8 DDO-340, Review and Comment Form 8.2.9 DDO-341, Review of Revisions to RPP Documents (see Reference 3.1.7) 8.2.10 DDO-398, Approval Form Procedure Change 8.3 Attachments None l
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. O O QD-AP-6.1 ;
Revision 10 Page 18 of 31 l l
EXHIBIT 1 l DOCUMENT REVIEW GUIDELINES 1
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- 1. Purpose and scope are clearly defined.
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- 2. Does not contradict other procedural or plan requirements.
- 3. Provides clear and logical process for satisfying purpose / requirement.
- 4. Responsibilities are clearly identified where appropriate.
- 5. Presents a realistic approach for performing the activity.
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- 6. If use of another document is required, it is identified.
- 7. Requirements and methods of performing each activity are defined to an appropriate degree.
- 8. Where practicable, features which will allow measurement of compliance are incorporated.
- 9. Specifies change control, if applicable.
- 10. Data and associated data forms specified as appropriate.
- 11. Special training requirements specified, if applicable.
- 12. Interfaces between organizations and documents are appropriately described, to
- 13. All applicable radiological, industrial health and safety, etc.,
requirements are addressed and the requirements identified if appropriate.
- 14. Compliance methods for all applicable DOE orders, NRC, etc.,
requirements are included and requirement reference identified.
- 15. All applicable OSHA standards, industry standards, etc., are addressed for compliance and the requirement reference identified.
- 16. All applicable local, state, and federal codes are addressed for compliance and the requirement reference identified.
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QD-AP-6.1 Revision 10 l
Page 19 of 31 l
EXHIBIT 2 l EXAMPLE OF MEMO TO REQUEST PROCEDURE OR PLAN RETIREMENT l
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@BaHelle
. . . Putting Technology To Work e,.i..t -e.,
Intenul Distribution Date To Document Control Manager From (Responsible Manager, Title) \
Subject ReQuCst to RClire (Provide Plan / Procedure Identifier)
I have reviewed (provide plan / procedure title) and request that it be retired for the following reasons (s):
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Concurrence:
1 RC&ESHO Manager Quality Manager SH&ES Manager
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\ V QD-AP-6.1 Revision 10 Page 20 of 31 EXIIIBIT 3 EXAMPLE OF DISCLAIMER FOR A DEDICATED DATA FORM OBallelle
. . . Putting Technology To Work
SUMMARY
AND/OR SPECIAL REPORT FORM Building No. W.I. No. . Date2 Entered by Date j
(
-Reviewed by: - Date ' .
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l DISCLAIMER: This modified form is limited to use b.y (name of erouo) l Personnel: i I
Health Physics:
RWP: HPS Surveys:
Work Accomnlished:
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DDG-103, Rev. I 7/92 (art >)
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QD-AP-6.1 Revision 10 Page 21 of 31 OBallellePutting Technology To hk REVISION RECORD INDICATING LATEST DOCUMENT REVISION Title No.
Page _i. of _ii_
INDEX OF PAGE REVISIONS Page No. i ii iii Rev. No.
Page No. 1 2 3 4 5 6 7 8 9 10 Rev. No.
Page No. 11 12 13 14 15 16 17 18 19 20 Rev. No.
Page No. 21 22 23 24 25 26 27 28 29 30 Rev. No.
I Page No. 31 32 33 34 35 36 37 38 39 40 I Rev. No.
' REVISION' RECORD ' REVISION' RECORD '
Rev. No. Date Rev. No. Date i
' CURRENT REVISION' Rev. No. j Issue Date Issued By DDO 009 Revision 3 (M/93) kar
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. l QD-AP-6.1 Revision 10 Page 22 of 31 ,
NONCONFORMANCE REPORT NCR No.
Nonconformance Item Date Originator -
Description of Nonconformance and Apparent Cause Recommended Corrective Action and Action to Prevent Recurrence Nonconformance Review Committee Disposition (if necessary) l Lessons I4arned i,
Nonconformance Review Committee Disposition Approval Date Date Correction Action Completed I
Date Date
. Responsible Manager I Date Date Quality Manager Date DDO-177, Revision 2 2/94(rm)
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. / U QD-AP-6.1 Revision 10 Page 23 of 31
@Ba11elle
. . Putting Technology To Work PROCEDURE / PLAN ASSESSMENT FORM oate
' To prom BCLDP Document Control subi.et ' Assessment of Procedures / Plans PROCEDURE / PLAN AUTHOR i i
The a'ttached procedure / plan is being sent to you for assessment of its content and continued utility. You ,
or your designee should assess the procedure / plan and check the appropriate lines below; please return this l form to BCLDP Document Control in Room 11-1-070 by l i
Please sign and date this form on the lines provided below.
l The following is my assessment of this procedure / plan:
I have assessed this procedure and no revisions are needed. Please renew.
Revisions are needed and I will have this done by (provide an estimate of the date). Also review PQP fc critical procedures.
This procedure / plan should be retired for the reasons presented below:
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To retire a document, obtain the following concurrence signatures:
Mark Jackson Date Steve Layendecker Date Gordon Eriksen Date RC&ESHO Manager ES&HS Manager Quality Manager
--' Date Responsible Manager (Signamre) i
' Document Control Manager Date Action DDO-183, Rev. 7 3/97(rb)
(m (~\
- U QD-AP-6.1 !
Revi:; ion 10 Fage 24 of 31
)
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QBalfelle
. Puu!ng Technology To work Page of CONTROLLED DOCUNEN"r TRANSMITTAL RECORD (Tansmittat Date)
(Transmittal No.)
To: From: BCLDP Document Control JN-1 ,
I litle: Copy No. I '
Remcve Insert Number- Item Rev. Date Rev. Date l
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q SpecialInstructions:
FI. EASE SIGN BELOW AND RETURN TO SENDER I hereby acknowledge receipt of the documents transmitted to me by this form. In the case of revisions,I acknowledge their incorporation into the appropr. ate ma::ual and have destroyed all supe.seded material er marked superseded copies as such.
Please Sip and Return by (Signature) (Date)
DDO-191 (8/91)
p QD-AP-6.1 Revision 10 Page 25 of 31
' ' ~ ~ '
8Ba#eue
. . . tutting Technology To %bek REMW Document ID Rev. Number Date Issued for Review Review Comments ASSIGNMENT FORM The subject document is being submined for your review and comment. Since this review is controUed, a response is required from au reviewers. brefore, please return this review sheet with comments on Form DDO-340.
To: Room No. From:
J Additional lastructmas*
- Please do 33 mark significant comments on text. I
- Only editorial comments may be marked on the document.
- Comments received after mandateg due data may not be incorporated. :
Signature of Artual .'
Organization Reviewer Reviewer /Date Quality R.C. and ESUI Oversight SH&ES Others:
i.
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Ceneral Review Comments This review has been delegated as indicated below. By my review signature below, I concur with their comments and they have my fuu review authority - ~
Reviewer: Name of Delegee: Date:
DOC 192. Rev. 2 8/9d(rm)
QD-AP-6.1
. Revision 10 Page 26 of 31 Project Number Internal Distnbution if Putting Technology To %k
. (see below)
Date To Distribution From Ruth Baruth subject Document Registration-Procedure / Plan Distribution Attached is a new procedure / plan.
Attached is a revised procedure / plan.
Please discard the previous revision.
Attached are replacement pages for procedure / plan.
Pages Please discard the replaced pages.
Procedure / plan has been retired. Please discard your copy. j Pages for an approved field change of procedure / plan-Keep these pages with your present copy of the procedure. A revision will be issued in the future.
NOTE:
If You Are To Be Quahfied On The Above Procedure, Initiate a DDO-085 Fonn And See Your Supervisor. If You Are Qualified On This Procedure, You Will Receive Notification from The s, Training Department That You Need to Complete a DDO-085 Fonn to Qualify On Any New Revisions. It Is Not Normally Necessary to Qualify on Administrative Procedures; Check With Your Supervisor. j DISTRIBImON DDO-200, Rev. 8 12/97 (RB)
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QD-AP-6.1 a- Revision 10 Page 27 of 31 OBanelle
. . . Pumng Technology To work DOCUMENT DELINQUENCY NOTICE Date:
To:
From: DDO Records Management The foDowing documents were sent to you and agnature sheets and/orimm have not been returned.
Type of Docinnent Document Number or Name Date ofIssue i
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- Manual, procedure with reading sheet, procedure assessment cc: QNDDO Program Manager / Records Management DDO-201 (7/91)
- V QD-AP-6.1 Revision 10 Page 28 of 31 OBaBeDe tumng Tkchnology To H6ck i REVIEW AND COMMENT FOILM Page No. of '
To: (Authori Date:
Frera: (Reviewer 1 "- ^ ' Comptedon Date:
Document No., Revision No.: _h-*
Title:
Secuens of Document to be Reviewed:
Page, Section.
Paragraph, and Review Comment Comment Disposition Line Number 4
1 I
I Date Reviewer
- Date Dispositioned By f Comment Resolution Complete Reviewer
- Date Author Date
' Reviewer shall sign both places initially if formal disposition and resolution of comments is not desired.
NOTE: See guidelinesfor Author's Review and Technical Review on back of thisform
p V '
QD-AP-6.1 Revision 10 Page 29 of 31 AUTHOR'S REVIEW GUIDELINES Assure that: .
- 1. The document is within the project scope.
. 2. The document is legible.-
- 3. The document satisfies contractual and project requirements.
4 The references are satisfactory.
- 5. Calculations and/or analyses and data are properly overchecked, documented, and traceable for verification. .
- 6. . The document is acceptable with no further review or that it is reviewed in greater detail by
- qualified independent technical reviewers. See Technical Reviewer Guidelines below.
TECHNICAL REVIEW GUIDELINES Address the following questions:
' 1. Is the document logically organized?
- 2. Is the text clearly and concisely wricen?
- 3. Is the problem to be solved and assumptions or rational for assumptions clearly stated?
.' 4 Does the document satisfy be project scope / requirements as stated in the planning documents?
- 5. Does the executive summary / abstract clearly and accurately state the conclusions to promote understanding by n non-technical reader? .-
, 6. Are references identified, traceable, available, and accurately quoted or interpreted?
- 7. Are units specified and correct? Are conclusions from data and/or calculations technically correct and logical?
- 8. If data are not as logically anticipated or reasonably expected, are stated conclusions technically rational?
- 9. Are data traceable and have the data been identified and verified?
. Add additional' items as appropriate when revie, wing a specific technical document.
QD-AP-6.1
, Revision 10 Page 30 of 31 OBa#elle Putting Technology To %bek REVIEW OF REVISIONS TO RADIATION PROTECTION PROGRAM (RPP) DOCUMENTS To: (Anthari Date:
From: (Revieweri Requested Completion Date:
Documesit No., Rension No.: Document
Title:
NO YES
- 1. Does the proposed revision constitute a lessening of the protection factor of the RPP versus the previous revision?
O O
- 2. Does the proposed revision constitute a lessening or elimination of a commitment to a regulatory requirement versus the previous revision?
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- 3. Does the Proposed revision constitute aless conservative release limit or dose limit?
l NOTE: A "YES" answer to any of the above questions requues I
resolution by the RSO with the NRC.
e :
Reviewer Date Radiological Safety Officer Date DDO-341 6/97(rm) l i
o' QD-AP-6.1
, Revision 10 Page 31 of 31 OBakse
. . . Puning Technokgy To %tuk APPROVAL FORM PROCEDURE CHANGE 1
Requester l (Prmt nanae & kle)
Procedure No. Rev. No.
Thu is an approvedprocedure change by one ofthefouawing methods:
O Field Change Effective tiH j 1
O waiver Efrective tiu 1
l Approvals:
/
Print / Sign Secnon Manager Date S. J. Layendecker, SUdESManager Dare M. E. Jackson, RC&ESEO Manager Date
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t G. B. Enben. Quality Manager Date l
I DDO.398 Rev. I 1068 (p) i i
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't OBaHelle Putting lechnology la obrk 505 King Avenue Columbus, Ohio 43201-2693 Telephone (614)4244424 racsimile (614) 424-5263 January 26,1999 Ms Cynthia Pederson Director, Division of Nuclear Materials Safety U.S. Nuclear Regulatory Commission - Region III 801 Warrenville Road Lisle, Illinois 60532-4351
Dear Ms Pederson:
Radiological Status of the Battelle Research Reactor Facility for CY98 and Request for Exemption from AnnualInspection Requirements This report summarizes factors pertinent to the radiological status of the Retired Battelle Research Reactor Facility for the calendar year (CY) 1998, as required by Battelle's NRC License SNM-7.
Facility Location The facility is located in Building JN-3, Battelle Memorial Institute, (BMI), West Jefferson North Site, about one mile south ofI-70 and one-quarter mile cast of State Raute 142.
Retired Facility Site Representative (RFSR)
The RFSR for calendar year 1998 continues to be Stephen J. Layendecker. The Battelle Columbus . Laboratories Decommissioning Project (BCLDP), Radiological Field Operations maintains purview of the facility and the Radiological Safety Committee (RSC), overviews the radiological status.
Facility Status Proposed uses of the facility must be approved by the RFSR and are subject to overview of the RSC. Dr. Patrick J. Sabourin was the chairperson of the RSC subcommittee during FY 98. The general arrangements within the building remain essentially the same as reported for the calendar year 1997.
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Ms Cynthia Pederson January 26,1999 Page 2 Security and Suneillance The facility remains within the confines of the fence and protected Nuclear Sciences Area.
-Twenty-four hour security and area access control is maintained by remote surveillance and periodic security patrols. Unescorted area access is limited to persons approved for access by Protective Services and site management; all others must be escorted by an approved staff member on the access list.
Environmental Survey On-site and off-site environmental monitoring is continued for the Nuclear Sciences Area according to DOE and NRC requirements. The annual Site Environmental Report (SER) incorporates data of the radiological and non-radiological Environmental Monitoring Program.
The data for the calendar year 1998 Report are currently being compiled and will be submitted to the U.S. Department of Energy and distributed to the U.S. Nuclear Regulatory Commission, the U.S. Department of Energy, and the Ohio Environmental Protection Agency. The raw data compiled for the report do not indicate any unusual conditions that may be attributable to this facility.
Retired Facility Surveys Surveys are performed as part of the Battelle Columbus Laboratories Decommissioning Project (BCLDP). The BCLDP work is authorized under an approved NRC HQ decommissioning plan.
The surveys are performed weekly as part of the BCLDP Surveillance and Maintenance Program in the occupied controlled areas of JN-3. Surveys are performed monthly of the office spaces at the East end of JN-3 and the environmental equipment storage area at the West end of JN-3.
Routine surveys are not conducted inside the access controlled Retired Reactor Core Area, Fuel Pool or the Shield Tank, as the areas are posted as Confined Spaces, and High Radiation or Radiation Areas. The safety hazards associated with Confined Spaces greatly outweigh the radiological hazards present; therefore, the integrity of these areas is monitored by performing weekly surveys at the boundary of the Confined Spaces. At this time, these areas are utilized to store radioactive waste, which is the source of the radiation. Surveys are conducted in these areas to support periodic personnel entry.
Smears from the weekly and monthly contamination surveys are evaluated for alpha and beta activity. Radiation levels are also documented and evaluated as a part of the weekly and monthly surveys. All contamination and radiation surveys conducted during 1998 were within the acceptable limits and no abnormal conditions were noted.
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t Ms Cynthia Pederson January 26,1999
' Page 3 Water Monitor )
i All water collected in the interior sump from the old hot drain system is pumped to an outside sump through a monitoring chamber. The water monitor listed in the FY 94 report was evaluated and found to be no longer needed.
i The wee'kly response checks and annual calibration with a Cs-137 solution were stopped at the end of the calendar year 1994. The past several years, environmental monitoring data has not ;
indicated detectable activity other than background; principally K-40 from agricultural fertilizer !
discharged through the monitor from the interior sump.
Facility Uses .
Current uses are:
liasement Area:(3100 Level)
(1) Old Pump Room, Northeast Basement - Contains a drain sump, water monitor (not in use), and sump pump.
(2) North Basement - Storage of respirator wash water tanks and packages of -
Plutonium-bearing waste.
(3) South Basement - Radioactive Materials Area containing contaminated (fixed contamination only) D&D equipment and materials.
(4) Southeast Basement - Storage for non-contaminated D&D equipment and materials and also contains a fumace room.
(5) West Basement - Storage for 55 gallon drums containing soil and storage for HEPA filter housings.
Ground Floor: (3200 level)
(1) West End - Annex for storage of archived environmental samples, non-radioactive equipment and storage crea for radioactive material in ground cylinder wells.
O o Ms Cynthia Pederson January 26,1999
'Page 4 (2) Former Shield Tank - Used as a Radioactive Materials Area for Suspect Low Level TRU Waste.
~(3)- North End - North rooms house a respirator issue, receipt and control shop.
(4)' East Rooms - Rooms are utilized by BCLDP Decontamination and
- Decommissioning personnel as office space.
- (5) Southeast End - Three rooms (3218,3219,3220)on the southeast side are utilized as emergency assembly areas and a locker room.
(6) South End - Utilized as an instrument counting station for Health Physics, and office space.
Second Floer: (3300 level)
(1) Northwest Laboratory Room - No cperations occur in the room.
(2) North Side Open Bay - Decontamination containment used for equipment
' disassembly and hazardous material identification prior to packaging for shipment.
(3) Open Bay East - Utilized as a small Low Level Waste Radioactive Materials Area j for storage of three crated used/ cleaned Plutonium glove boxes, B-25 boxes and 55 gallon drums containing D&D non-compactable waste awaiting disposal.
(4) South Cage Area - Radioactive Materials Area for storage of Low Level Non-Hazardous Soil Waste awaiting shipment. Also, utilized for Health Physics archive l storage.
(5) Southwest Old Control Room'- Utilized.as a Radioactive Materials Area for laundry storage.
(6) Former Fuel Pool Main Area- Utilized for interim storage for packaged Suspect TRU Waste.
Occurrences l There were no reportable occurrences during 1998 associated with operations conducted in the building.
Continuing Need for RFSR Report
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January 26,1999 Page5 With the pending approval of the amendment to SNM-7 to clarify requirements, it is Battelle's understanding that a continuing facility status report is no longer required by the NRC once this amendment is granted. U~pon approval, this will be the last RFSR status letter. If you have questions please contact G. Mike McCann at USNRC, Region III. I l
1 Conclusion l This report summarizes factors pertinent to the radiological status of the retired Battelle Research Reactor Facility for the calendar year 1998, as required by Battelle's NRC License SNM-7.
If you have any questions or require additional information regarding this facility, please contact me at (614) 424-3885.
'ncerely,, ,
(t[ phen J. Layendecker Safety, Health, and Environmental Support Manager / Radiation Safety Officer l
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