ML20151V296

Amend 10 to License SNM-696,deleting Five Sampling Stations from Existing Environ Monitoring Program

ML20151V296
Person / Time
Site:	07000734
Issue date:	08/17/1988
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20151V206	List: ML20151V203 ML20151V296 ML20151V304
References
NUDOCS 8808220221
Download: ML20151V296 (5)

Text

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'f*W M- N _SNAA_+A A A_^ m. A m_m a m a a ny a ' N2C Form 374 g

'#0E 0" $ PAGES m aa) U.s. NUCLE AR REGULATORY Commission g MATERIALS LICENSE ,. l Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93 ~438), and Title 10. I Code of Federal Regulations, Chapter 1, Parts 30,31,3.',33,34,35,40 and 70, and in reliance on statements and repres heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, j source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to I deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(st This I license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is I subject to all applicable rules, regulations and orders of the Nuclest Regulatory Co : mission now or hereafter in effect and to any conditions specified below. j Ucensee l I

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General Atomics 3. Ucense number SNH-696, Amendment No. 10 l t

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P. O. Box 85608 '..

, f , .I San Diego, California 92138 4. Eiptrf tita#e December 31, 1989 ll y

5. Docket or */ 70-734 'I Reference No. m y 6 . Byproduct, source, and/or 7. Chemical and/or physical L4 Maximum amount that licensee I

_! special nuclear material form hay possess at ar.y one time I

,ggder this license I 1

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' .e 7 y I A. Uranium enriched in A. As described iry 1; hat A .'q985 kilograms of I

.; U-235 isotope. portion of the 4tcensee's @ 235 l l application referred to y . ,

in-Item 9 of-t ds license 3 i i  :,i, w I B. U-233 8. Any B;3 5 kilograms of I :

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' U-233

_ , .D C. Plutonium C. Encapsulated and/or 'C. 3 kilograms total Pu l L ,

Sealed Sources - ' l q d 5 0. Plutonium D. 8 red but unseparatees . D. 1 kilogram total Pu I l > .

I 1 E. Plutonium E.rPlated,. calibration E. 5 grams total Pu D l

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, 1 7] F. Plutonium F. Solutions, precipitates F. 5 grams total Pu 3 j and solids W )

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1No more than 1,000 grams of U-235 will be in the form of UF6 '

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8808220221 880817 PDR I

ADOCK 07000734 I '

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i f^^^^^^^^ _ $ ?5NWEU?S ZQQ l N: C Form 3N A. U.S. NUCLE An f.EGULATORY COMMIS$10N ,, m 2 , $

iI Linn.e number 3N3 696 ~[

! MATERIALS LICENSE Amendment No. 10 L i SUPPLEMENTARY SHEET 7O 734 L I

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l 9. Authorized use:

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I L i For use in accordance with ststements, representations, and conditions contained [

l in Part II "License Specification:" dated July 24, 1981, and supplements dated L I March 16, and December 24, 1982; February 4, November 14, and November 15, 1983; (

j April 10, April 12, June 28, September 4, and September 7, 1984; December 5, 1985; L i

May 23, September 25, and December 10, 1986; December 21, 1987; March 4, I l l March 9, (2), March 22, and April 26, 1988. [

i I 'r l l 't 1l 10. Authorized Place of Use: r 1

The licensee's San Diego, California site at 10956.0ehn Jay Hopkins Ori've and l 11220 Flintkote Avenue as specified in the aforesaid- cation and supplements.

11. Reurds of all safety-related reports and analyses shall tgetained as follows:

1: a. Copie,s of criticality and radiation safety analyses shahtje retained for at "

8{ least 2 years or for 6 months after a project ist,tarminat 4 whichever is

% longer. *'

.b O f i i b. Copies of all other safety-related records (e.g.,. plant al additions, abnomal occurrences associated wi, tit radioactiv ations and '

1 releases, l

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audits and inspections, instrument calibrations, ALARA fin gs, training t 4! and retraining, personnel exposuresi routine radiation and vironmental F l surveys) shall be retained for at least 2 years or longer required by i

] regulations. , ;

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12. Notwithstanding the statements in Section 5.4.2 in the Licente Specification  :

1 Volume (Part II), if double batching is not credible, the carimum safe batch size  :

4; shall be no more than 75 percent of the minimum critical a ss independent of the f 3 degree of water moderation and reflection. However, wnan the Th/U atomic ratio J 3

is > 3.6 aad the H/V < 20, the maximum safe batch size may be increased to 790 g L contained U-235 independent of whether_ double batching is credible. P lf .

1! 13. The Director QACO, upon recommendation of the appropt; ate manager within

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f QACD, shall have authority to require immediate termination of activities  ;

3 and/or corrective action in any situation which, in their judgment, could  ;,

f lead to the unnecessary exposure of personnel to ionizing radiation, i 1

release of radioactive material, loss or damage of property, or  : I j non-compliar.ce with the license or a regulation, r 1  : i i l14. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA il 9 Committee, shall meet at least annually to review (1) repcrts of audits and  ;

j, inspections performed since the last ALARA review and (2) employee exposures and eff' 'nt release data to determine (a) if there are any upward trends developing in i) 5 i

i per- ael e.xposures for identifiable categories of workers, types of operations, or [

l' efflaent releases, (b) if exposures and releases might be lowered in accordance with Li 1

1 the ALARA concept, and (c) if equipment *or effluent and exposure control is being r I properly used, maintained, and inspected. L l L I! t I! r I! L l t

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MAAn AAAAAA X L A A AA AM A AAm mykg'g13 e i NCC wmanA u.s. NUCLE AR REGULATOQY COMMISSi@N m 3 w 5 um _ l I ucenie numtier l SNM-696, Amendment No. 10 MATERIALS LICENSE " "'"""

• l' 1 SUPPLEMENTARY SHEET 'l l 70-734  ;

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'l 1 ,l I The CRSC evaluation, recommendations, and corrective actions shall be 'l

! documented and the report shall be sent to the appropriate operations l managers and the Vice President, Finance and Administration, h{

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i 15. Radinlogical Work Percits (RWPS) shall be issued for all unplanred or i i non .outine work with licensed material not covered by a WA. The RWP shall l be signed by Health Physics management or a senior staff member before related  ?

l work can commence. A senior staff member shall be a Health Physics Technician I g

l having a minimm 5 years' experience in radiation safety. An evaluation of ]

l the safety effs. .aness of the permit shall be made upon compittion of the work.

!y I Q t < : .. L s needs, shall be given to 116.Radiationsafetytraining,appropriateto'theeaployy'g all new employees. ;jl l * :-

17. Radiation safety training and indoctrination shall be ed by the Health conduc}Jealth Physics jl.

l Physics Manager or by a similarly qualified individual. The' 'g i Manager may delegate training in that portion of the course tW an individual who t 1 is uniquely qualified to present it. ,

.4 h18.ContinuousairsamplingshallbeconductedinanyareawhereifcInsedmaterial ,I iI l

can become sirborne. . - m, s ,L. .

f 19. The location of air samplers shall be.' checked annually and wheneVer any process .

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1 or equipment changes are made to verify .the;representativeneis of work area : *r r 1

1 sempling. In addition, the location of hir's.amplers shall be checked at tha t ;

$ commencement of operations in any area thlatstias been shutdown for more than LI f 6 months to verify the representativepass! cf ' air sampling.  ; j '

1 i i, 20. The laboratories in which plutonium in a dispersible form may be used shall have g i exhaust ventilation systems separate from other building exhausts and shall provide 1 dual HEPA filtering of the ef. fluent air. r l, l

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j 21. Notwithstanding the statements masie ie Section 4.1.5 of *..he revised application y

dated November 1983, the licensee shall conduct 5eak tssting of sealed plutonium sources and alpha sources in tccordance with Annex A "License Condition for Leak

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A Testing Sealed Plutonium Sourcis," dated November 1979, and Annex B "Licendt g 3 Condition for Plutonium Alpha Purces," respectively. t ,

1 L l 22. The licensee shall prepare and r.ubmit to the Chief, Fu21 Cycle Safety Branch, I I i

i Division of Industrial and MeMcal Nuclear Safety, NHSS, C. S. Nuclear Regulatory E 1

l' Commission, Washington, DC '.0555, a report whenever there is any new residential development within one mile around the site that constitutes a sigitificant change

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i 1 in parameters that may be affected by the release of radioactive matericis into 1-3,;

the environment. I 1, t I t '

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N C oem 374 A U.S. NUCLE AR REGUL ATORY COMMISsloN l ,,ot 4 o, $ , t g LKenne number g  ;

SNM-696, Amendment No. 10 'l f l MATERIALS LICENSE "' "'"""""*'

I SUPPLEMENTARY SHEET l I I 70-734 , ., l i i 1 l

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1 23. The licensee shall implement, maintain and execute the response measures of his ) '

Radiological Contingency Plan submitted to the Commission on May 25, 1984, and 1 1

l l supplemented on August 22, 1984. The licensee shall also maintain implementing j g

q procedures for his Radiological Contingency Plan as necessary to implement the j) j

Plan. The Plan shall be fully implemented by February 12, 1985. This , l i

i Radiological Contingency Plan and associated implementing procedures supersede a 4 the emergency planning requirements of 10 CFR 70.22(i) as they refer to onsite ) l planning and notification procedures. The licensee shall make no change in his h Radiological Contingency Plan that would decreast the response effectiveness of l f the Plan without prior Commission approval as evidenced by a license amendment. ,

p il The licensee may make changes to his Radio)ogical Contingency Plan without prior l Commission approval if the changes do not decraase the response effectiveness of ,

1l I; the Plan. The licensee shall maintain records of changas that are made to the li Plan without prior approval for ? period of 2 years free the date of the change I 4 and shall furnish the Chief, Fue1 Cycle Safety Branch, DWKion of Industrial li I

h and Medical Nuclear Safety, NMSS, U. S. Nuclear RegulatorytCor p

gl Washington, DC 20555, and the appropriate NRC Regional Offict(pission, specified in lj  ;

(j Appendix 0 of 10 CFR Part 20, a report containing a descriptio(of each change n within 6 months after the change is made.

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-) y 1 jl24.Attheendofplantlife,thelicenseeshalldecontaminatethe%teandfacilities, kf 3

authorized as a place of use for special nuclear mat 9tial, in accordance with the

1 general decommissioning plan submitted by swr lette" dated JulF25,1986, and its' [,

i supplement dated October 15, 1986, so:that these fa.ilities and y ounds can be 1 released for unrestricted use. The corporate commitment that funds will be made i 1; available for decommissioning the f acility, provided by letter dated September 10, p j 1986, is hereby incorporated as a condition of the licensa. >

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25. Notwithstanding the statements made in Section 4.3.5 of the-revised application g- dated November 1983, the release of the fae.ilities and equipment for unrestricted j 1 use from the plant site or to unrestricted areas onsite shall be in accordance p 3 with the enclosed Annex C, "Guidelines for Decontamination of Facilities and p p

1 Equinment Prior to Release for Unrestricted Use or Termination of Licenses for

} By product, Saurce or Special Nuclear Material", dated July 198?. P

)26.Thelicenseeisherebyexemptedfromtheprovisionsof10CFR70.24duringthe lp 1

hodification of the SV-A criticality alarm system insof ar as this section applies R to materials held in the SV-A building under this license subject to the following y 1 >

I a. The criticality alarm system shall be in service in all areas where the P F-l quantity of special nuclear material (SNM) does not meet the exemption criteria 8 q

in Section 4.2.1.4 of the specification volume with the exception of the SNM i storage vaults in the SV-A building. g 1 k I b. There shall be no movement of any special nuclear material (SNM) into, out of, k I or within the SV-A building SNM storage vaults while the criticality alarm I f 1 system is not in service.

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e l MME'EMMMMEEEA l N C Form 374A U.S. NUCLdAR REouLATO9Y CoMMisStoN PAGE $ op $ ,4ogs l 1 Licenu number l SNM-696. Amendment ta. 10 ]

! MATERIALS LICENSE " *"**""** #

I S'JPPLEMENTARY SHEET l 1

70-734 ,r I l g 3 1 ,t I

l'27.NetwitnstandingthestatementinSection4.2.1.4,PartIIofthelicense,the g trip levels will be readjusted af ter each monthly test of the criticality alarm j i system if the alarm point fails to activate within approximately 5 seconds, more  ;

I than once out of four trials. 'r I I I 28 . Notwithstanding the statements in Section 4.2.1.4, Part II of the license, no I I

f material handling shall De allowed in any area in which the required criticality ql alarm system is inoperative. j gi y l 29. The licensee may reduce the radiation safety, nuclear criticality safety, and Il y

environment?1 surveillance requirements within the.HTGR fuel fabrication and i storage areas in the S/-A Building, TRIGA fuel merrufacturing building, and in 3 1

the GA Hot Cell possessing fissile and/or other radioactive terial, curing a il period of reduced activities es specified in the applica'tfan dated April 23, 1985, t j

i subject to the following w difications: g  !

a. Thesurveyfrecuenciesandcontaminationcontrolmeasurehpecifiedinthe f license shall be used whenever work is performed on or witLequipment which y handles radioactive material. L i

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b. Any work performed on equipment which handled rddioactive Esterials shall be authorized by and performed 'ander a radiation work permit. $

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c. All openings of ventilation ducts and enclosures which are not completely I sealed shall be maintained with a mininune airflow of 25 LFM.D The licensee 't shall determire, on at least a semiannual basis, that this minimum airflow I is maintained.

j j d. If air sample results indicate an increast in airborne contamination to i'

, 10 percent or more of the appropriate MPC, survey frequencies shall be t

,, increased to the levels specified for Type II laboratories. t i '

e. The Manager, Nuclear Safety, or his designee shall perform a criticality C g inspection, at least annually, of ali areas specified.

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1 I. FOR THE NUCLEAR REGULATORY COMMISSION M &gned By:

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D Leland C. Rouse t l Date: / Bv:

Division of Industrial and I  !

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/ Medical Nuclear Safety [!

Washington, DC 20555 g I i

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