ML20236K764

Renewed License SNM-778 for B&W,Authorizing Use of Listed Matls at Licensee Facilities at Nnfd Research Lab

ML20236K764
Person / Time
Site:	07000824
Issue date:	07/30/1987
From:	Rouse L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20236K757	List: ML20236K753 ML20236K764 ML20236K777
References
NUDOCS 8708070242
Download: ML20236K764 (4)

Text

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CDRC Form 374 1 3

~' O F PAGE' pAGcS GS 80 U.S. Q*UCLE AR R EGULATORY COMMISSION MATERIALS LICENSE Parsuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 438).and Title 10, k f

Co<!e of Federal Regulations. Chapter 1, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representati heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byprodu:t, !p!

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source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated brSw; to I deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This lR:

!icense shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is f l' subject to all apphcable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

f Ip Licensee b

I' 3. License number SNM-778, as renewed Babcock & Wilcox f l Naval Nuclear Fuel Division  ;

NNFD Research Laboratory i 2'

P.O. Box 11165 4. Expn.ation date 1

Lynchburg, VA 24506-1165 , ~

July 31, 1992 l

5. Dock et or '

- Reference No. .70-824 I ,

6. Byproduct, source, and/or .

7. Chemical and/or physical 8. Maximum amount that licensee N special nuclear material , ,

form ,

$may possess er any orse time

. .u'nder this license  ;

A. Uranium enriched to A. Encapsulated or A. 3.5 kg con- .

> 20% in the U-235 -irradiated tained U-235 .I Isotope l:

9 B. Uranium enriched to B. ~Unencapsu,ated l B. 0.53 kg con- i

> 20% in the U-235 .

. and.unirradiated 4tained U-235  !

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Tsotope l l,. '. s C. Uranium enriched >~ C. Encapsulated or' 'C[ 1.2 kg con-l l 5% to < 20% in the irradiated - tained U-235 l

U-235 isotope '

D. Uranium enriched >- D. Unencapsulated D. 0.5 kg con-5% to <20% in the and unirradiated tained U-235 ;i U-235 isotope i

! 1 E. Uranium enriched > E. Encapsulated or E. 55 kg con-  ! l

.711% to < 5% in tee irradiated tained U-235 '

j U-235 isotope l l

F. Uranium enriched > F. Unencapsulated F. 11 kg con- M

.711% to < 5% in tee and unirradiated tained U-235 J' U-235 isotope k 1

G. U-233 G. Any G. I gram l i i

i H. Plutonium H. Unencapsulated H. 50 g  !

l and unirradiated I. Source material I. Any I. 6,000 kg g Y'

l B708070242 870730 I

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NRC Form 374A U.S. NUCLEAR REGULATORY COMMIS$10N 2 3 j PAcc og p, cts ll License number l j

' SNM 778, as renewed

' MATERIALS LICENSE et m Reference rn t -

,' SUPPLEMENTARY SHEET _ggq l

1 I l I l I

l I J. Fission products J. Irradiated fuel J. Quantity I I & transuranium contained in .

)

I elements 4 irradiated  !

j l fuel assemblies I

I K. Fission products K. Irradiated fuel K. 5,000,000 Ci i I and transuranium I elements .

i I

L. Any byproduct L. Irrac iated L. 50,000 Ci l jt uc(tural E G .,

y material t j i materials & {

l C components 'd i i

%y M, "h  ;

I I M. Byproduct S

Any 6l. 3,000 C1 each I

material with total not to i l l Atomic nos. 3 Cry eQ , f7 $ exceed .

l g thru 83 t/s g. N ,g% ,000,000 Ci  :

N. Transuranium $ D An b . O millicuries l

elements (( '

.gf gjll N. (each total not  ! 3

- 'r yh U " ri*S

0. Cf-252 V Sea] ur ; s, l/jfp 0. d4 mg

0) .-

&W  %

Pb30Ci N

P. Am-?41 Q  %[* dSea ra ources q / n Q. u p$d,/soueces. D gQg Qj.9 100 Ci y

Q. H-3 y/;, Scal n O,, Q.

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Oxide th R. 3 Ci 4 wt v., ,

! S. H-3 S.#'51'Ilate'd-sci! Y S. 3 Ci Sj 5

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j f 9. Authorized Use: For use in accordance with the statements, representations, i and conditions of Chapters 1 thru 8 of the license application dated f 1 i November 26, 1985, and supplements dated May 27, 1986, and January 20, to April 27, and May 26, 1987. g l

l 10. Authorized Place of Use: The licensee's existing facilities at the NNFD k y Research Laboratory. $

11. Sealed sources shall be tested in accordance with the enclosed " License Condition for Leak Testing Sealed Sources Which Contain Alpha and/or Beta-gamma Emitters."

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$ 12. Release of equipment from the plant site to unrestricted areas or to onsite clean g

! areas shall be in accordance with the enclosed " Guidelines for Decontamination of i Facilities and Equipment Prior to Release for Unrestricted Use or Termination g) p e of License for Byproduct, Source, or Special Nuclear Material" dated May 1987. pg e o I @ M i -

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>------------------ ------m-2-m _ ,--y NFIC Form 374A U.S. NUCLEAR REGULATORY COMMISSION p,,c 3 o ,. 3 ,,ces l Ucense number l SNM-778, as renewed y

• MATERIALS LICENSE pocket or nererence nureber i i SUPPLEMENTARY SHEET 70-824 E N

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13. Within 90 days of the date of the license renewal, the licensee shall submit, for l' j NRC's review a: a approval, a groundwater monitoring program for the detection of y  !

potential leakage of the below grade tanks in the Liquid Waste System (Building B). p The program shall include the location of the wells, monitoring frequency, analysis N .

action levels, an<? the reporting requirements. I i

14. At the end of plant life, the licensee shall decontaminate the facility and site l ]

in accordance with the general Decommissioning Plan submitted with the renewal g 1 application dated May 26, 1987, so.that these facilities and grounds can be i released for unrestricted use. Til e inancfdycommitmentassociatedwiththe i ]j Plan, assuring funds for deconsiiissio{f,ing,'is n tiiretiyf i incorporated as a condition i of the license.

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FOR THE NUCLEAR REGULATORY COMMISSION p fr' ciel e,p,,e g l Date: EL3 1997 By: ' ? N c fx..> .,

Division of Fuel Cycle, Medical, Academic, and Commercial Use Safety f Washington, DC 20555 Iad - m e h\f umegy,m3,$/r/ m osys.e - ,xe - - m e - e m m awrm 1

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, JUL 3 01987 l l

LICENSE CONDITION FOR LEAK TESTING SEALED SOURCES WHICH CONTAIN ALPHA AND/0R BETA-GAMMA EMITTERS A. Each sealed source containing licensed material with a half-life greater than 30 days shall be tested for leakage at intervals not to exceed 6 months. In the absence of a certificate from a transferor indicating that a test has been made within 6 months prior to the transfer, the sealed source shall not be put into use until tested.

Notwithstanding the periodic leak test required by this condition, any licensed sealed source is exempt from such leak tests when the source contains 100 microcuries or less of beta and/or gamma emitting material or 10 microcuries or less of alpha emitting material.

The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used. The sources excepted  !

from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within 6 months prior to the date of use or transfer.

B. The test shall be capable of detecting the presence of 0.005 microcurie of alpha and/or beta gamma removable contamination on the test sample. The test sample shall be taken from the source or from appropriate accessible surfa-as of the container or device in which the sealed source is mounted or st ;I on which one might expect contamination to accumulate. Records of 1 u test results shall be kept in units of microcuries and maintained for vection by the Commission. ,

C. If the test reveals the presence of 6.005 microcurie or more of removable contamination, the licensee shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired by a person appropriately licensed to make such repairs or to be disposed of in acccrdance with the Commission's regu'lations.  !

Within 5 days after determining that any source has leaked, the licensee i shall file a report with the Director, Division of Fuel Cycle, Medical, ,

Academic, and Commercial Use Safety U. S. Nuclear Regulatory Commission, Washington, DC 20555, describing the source, test results, extent of con-tamination, apparent or suspected cause of source failure, and corrective action taken. A copy of the report shall be sent to the Administrator of the appropriate NRC Regional Office listed in Appendix 0 of Title 10, Code of Federal Regulations, Part 20. l i

GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE l OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL f

i U.S. Nuclear Regulatory Commission Division of Fuel Cycle, Medical, Academic, and Connercial Use Safety s

Washington, DC 20555 May 1987

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>ecify the The instructions in this guide, in conjunction with Table 1, s 3e used in radionuclides and radiation exposure rate limits which should decontamination and survey of surfaces or premises and equipment prior to The limits in Table 1 do not abandonment or release.for unrestricted use.

apply to premises, equipment, or scrap containing induced radioactivity for  ;

which the radiological considerations pertinent to their use may be different.

The release of such facilities or items from regulatory control is considered on a case-by-case basis.

1. The licensee shall make a reasonable effort to eliminate residual contamination.

2. Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the covering. A reasonable effort must be made to minimize the contamination prior to use of any covering.

3. The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and l other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.

4. Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces This may contaminated with materials in excess of the limits specified.

include, but would not be limited to, special circumstances such as razing of buildings, transfer to premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status. Such requests must: .

a. Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.

b. Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.

3

5. Prior to release of premises for unrestricted use, the licensee shall

-make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1. A copy of the survey report shall be filed with the Division of Fuel Cycle, Medical, Academic, and Comercial Use Safety, U. S. Nuclear Regulatory Commission, Washington, DC 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report should be filed at least 30 days prior to the planned date of abandonment.

The survey report shall:

a. Identify the premises.

b. Show that reasonable effort has been made to eliminate residual contamination,

c. Describe the scope of the survey and general procedures followed.

d. State the finJings of the survey in units 'specified in the instruction.

Following review of the report, the NRC will consider visiting the facilities to confinn the survey.

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