ML20127N229

Amend 23 to License SNM-696,incorporating Revised Radiological Contingency Plan Re Issue Which Should Be Addressed in Insp Rept 70-0734/92-07 Covering Vendor Training & Retraining Programs

ML20127N229
Person / Time
Site:	07000734
Issue date:	11/25/1992
From:	Jim Hickey NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20127N224	List: ML20127N221 ML20127N229 ML20127N238 ML20127N243
References
NUDOCS 9212010100
Download: ML20127N229 (5)

Text

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4 MATERIALS LICENSE Y

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4 l Pursuant to the Atomw Energy Act of 1954, as amended. ihe Encrp) Reorganvaimn Act of 1974 (PuNw l.aw 9.b4 h and hde IR 4

g C<ue of l'cderat Regulanons. Clupics 1. l'ans M 31..n.'. R R M. M 40 and 70. arki en returwr on siawments arkiivperwntaimm hevetof air 4

i made b3 e.e is enwe a hunse a herch.s muca auo.orving ihe hansee in reune. cqunc. emess, and irander b> pndat, sourw. and slui - I g

[j nuclear materu! drugnated tvlow, to use sus h matcrial for ihe purpn.ct O aiki et de pl.h r(si Jcuynated below, to dchset og transics sa h malvtw'.

b to ivrmns avbr ued to <ccene it m anor.tain e with the regutaiwirn of Oie applicat le paris e Thn hwnse shall le danwd to condam the soramwm p apecified m Sntion iW3 of the Aionne l;nergy Ast of 194.n erncrmicJ. and n subject to all apptecable rules. regulaison arwi o#Jcts of the Nuitcar j

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I General Atomics

3. Lcense number Stim-696, f

4 Amendment flo. 23 I

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P.O. Box 85608 4 Espiration te December 31, 1989 V

4 San Olego, California 92186-9784

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b. Masunum amount th.tt beenwe 5

specul nuclear matenal form may poucu at any one tune

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Uranium enriched in A.

As described in that A.

985 kilograms } of f>-

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U-235 isotope portion of the licensce's U 235 f,

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in item 9 of this license h

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1;-233 B.

Any B.

5 kilograms of g

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Plutonium C.

Encapsulated and/or C.

3 kilograms total Pu I. -

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Plutonium D.

Bred but unseparated D.

I kilogram total Pu v

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Plutonium E.

Plated calibration E.

5 grams total Pu f.

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Plutonium F.

Solutions, prehipitates F.

5 grams total Pu

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and solids i

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Authorized use:

For use in accordance with statements, representations, and f

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conditions contained in Part !!

" License Specifications" dated July 24, 1981, and t

supplements dated March 16, and December 24, 1982; February.4, tiovember 14, and h(g tiovember 15, 1983; April 10, April 12, June 28, September 4, and September 7, 1984; December 5, 1985; May 23, September 25, and December 10, 1986; December 21-1987; h.

March 4, March 9. (2), March 22, April 26, August 22, September 8, and_flovember 2, p

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1988; May 25, and tiovember 17, 1989; June 27, 1990; April 30 and September 27, 1991; 9

' f and March 5, March 18, June 24, and September 10, 1992; and in the "SVA f

j Decommissioning-Plan _" dated April 1, 1990 (submitted by letter _ dated March 30', 1990), h j

August 22. 1990 (submitted by letter dated August 24, 1990), and June 15, 1992.

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K iffo more-than 1,000 grams of U-235 will be in the form of UF '

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MATERIALS LICENSE

-SM 696~ Amendment lio. 23 _ _

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10. Authorized place of use: The licensee's San Diego, California site as specified in j -

the aforesaid application and supplements.

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.11. Records of all safety-related reports and analyses shall be retained as follows:

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Copies of criticality and radiation safety analyses shall be retained for at' t

least 2 years or for 6 months v "r a project is terminated, whichever is longer. ' -

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Copics of all other safety-related records (e.g., plant alterations and j

additions, abnormal' occurrences associated with radioactivity releases, audits A

i and inspections,-instrument calibrations, ALARA' findings, training and j

retraining, personnel exposures, routine radiation;and environmental surveys)

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12. flotwithstanding the statements in Section 5.4.2 to the License Specification Volume

,4 (Part 11), if doubl6 batching 71s not credible, the, maximum safe batch size shall be M) j]

no mere than 75 percent of the minimum critical mass independent of the degree of f -

water moderation and reflection. liowever, when the Th/U atomic ratio is 2 3.6 and 4

the li/U s 20, the maximum safe batch size may beilncreased to 790 g contained independent of whether double b' tching is credible.

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13. The Director QACD; upon recommendation:of, thehropriate manager within QACD, shall !y>I g

h have authority to require immediate termination of activities and/or corrective M>

y-action in any situation which, in their judgment, could lead to the unnecessary g

j exposure of personnel to ionizing radiation; ' release'of radioactive material, loss or y

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' damage of property, or non-compliance with the license or a. regulation.

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. The Criticality and Radiation Safety Committee (CRSC), = functioning as an ALARA Committee, shall meet at least annually to review (1). reports of audits' and-

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inspections performed since the last ALARA review and (2 employee exposures and:

<j ef fluent release data to determine-(a) if there are any u)pward trends developing..in 5-tg i

personnel exposures for identifiable categories of workers, types of operations, or 9

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effluent releases, (b) if exposures and releases might be lowered in accordance with _/

,f the ALARA concept, and-(c) if equipment for effluent and exposure control is being-A i

properly used, maintained, and inspected.

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4 the report shall be sent to the appropriate operations managers and the Vice lj!

f President, Finance and Administration.

M 15. Radiological kork Pernits (RWPS) shall be issued for all unplanned or n_on-routine i

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work with licensed rr rial not covered by a WA.

The RWP shall be signed by Health

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It; gi Physics management or senior staff member before related work can commence. A W

a senior staff member shall be a Health Physics Technician having a minimum of 5 years' W experience in radiation safety. An evaluation of the safety effectiveness.of' the F

y permit shall be-made upon completion of the work.

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SUPPt.EMENT ARY SHEET 70-734 f

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16.Radiationsafetytraining,appropriatetotheemployee'sneeds,shallbegiventoalllp

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new employees.

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17. Radiation safety training and indoctrination shall be conducted by the Health Physics i>'

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,4 Manager or by a similarly qualified individual.

The Health Physics Manager may j

delegate training in that portion of the course to an individual who is uniquely 3

qualified to present it.

1 18.Continuousairsamplingshallbeconductedj"n(anyareawherelicensedmaterialcan 1

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19. The location of air sample s' shall be checked annually'and whenever any process or

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4 equipment changes are made to verify the representativenes's)of work area air 4

sampling.

In addition ~the location of air samplers shall'be checked at the p

j commencement of operations in any area that has been shutdown 1.for more than 6 months

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14 to verify the representativeness of air sampling. A -

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20. The laboratories in which plutonium in a,dispersiblelform may'be used shall have exhaust ventilation systems separate from other building exhaust

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k enclosed Annex C, " Guidelines for: Decontamination of facilities and Equipment prior j

4 to Release for Unrestricted Use or Termination of Licenses for By-product, Source or

,p Special Nuclear Material", dated July 1982.

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26. The licensee is hereby exempted from the provisions of 10 CFR 70.24 during the

>l modification of the SV-A criticality alarm system insofar as this section applies to (

f materials held in the SV-A building under this license subject to the following:

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The criticality alarm system shall be gin. serv 1ce-in all areas where the quantity; 3

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of special nuclear material.-(SNM) does not me,et,the exemption criteria in Section }t>

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4.2.1.4 of-the specificatich volume with the exception of the SNM storage vaults j

in the SV-A building.S

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There shall be no lmo'vement of any special nuclear material (SNM) into, out of, or %

4 within the SV-A building SNM storage vaults while the crit,1cality alarm. system is j>

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not in service.

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27. -Notwithstanding the statement inDction'4.2.1.4,f Part II of the license, the trip levels will be readjusted after.cach monthly test of the criticality. alarm system if 4

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the alarm point falls to activate;within approximately 5 seconds, more than-once out jp of four trials.

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28. Notwithstanding the statements in Sectioni4.2.1;4, part !! of the license, no material hindling shall be allowed infany!. p fdrea>in which-the required criticality I;>

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alarm system is inoperative.

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29. The licensee may reduce,the radiation safety, nuclear criticality safety, and

j environmental surveillance requirements within the liTGR fuel fabrication and storage

,I areas in the SV-A Building,'TRICA fuel manufacturing building, and in' the GA llot Cell ;.

possessing fissile and/or other radioactive material, during a period of reduced-4(

fI activities as specified in the application. dated April 23, 1985, subject to the

)4 following modifications:

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The survey frequencies and contamination control measures specified.in the jh h

license shall be used whenever work is performed on or with equipment which h;

y handles radioactive material, V

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Any work performed on equipment which handled radioactive materials shall be Id authorized by and performed under a radiation work permit.

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h All openings of_ ventilation ducts and enclosures which are not completely scaled (t

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shall be maintained with a minimum airflow of 25 LFM.

The licensee shall t

[j-determine, on at least a semiannual basis, that this minimum airflow is J-p

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SNM-696 Amendment No. 23 MATEl(IALS LICENSE 4

SUPPLEMENTARY SHEET 4

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If air sample results indicate an increase in airborne contamination to 10 i>p

'4 percent or more of the appropriate MPC, survey frequencies shall be increased to

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the levels specified for Type !! laboratories, p

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!j The Manager, Nuclear Safety, or his designee shall perform a criticality e.

4 inspection, at least annually, of all areas specified.

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30. The licensee is hereby authorized to pospess 16 TRICA fuel elements at the University,)

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4 of Missouri for purpose of packag.ingl(he;elEhents for delivery to a carrier as i

specified in the amendment application date'd' $eptember 8,1988.

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Ij 31.Theindiv;dualidentified[in'theJune 17, 1992, letter, pho holds the position

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of BNI Project Manager,'is hereby exempted from the degree-j contained in Section 2'2.3 of the SVA Decomissioning Plan:yequirements

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FOR THE NUCLEAR REGUt.ATORY COMMISSION j

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W4PM1 Signed BT pi NOV 2 51992

/4 Date:

By:

Joh.n W. N. Hickey

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= I4, Division of Industrial and j

1. p[ e\\dy hj Washington, DC 20555 ij Medical Nuclear Safety l

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Enclosures:

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