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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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

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General Atomics

3. Ucense number SNH-696, l

Amendment No. 10 t

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P. O. Box 85608

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San Diego, California 92138

4. Eiptrf tita#e December 31, 1989 ll y

5. Docket or

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'I 70-734 Reference No.

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. Byproduct, source, and/or

7. Chemical and/or physical L4 Maximum amount that licensee I

6 hay possess at ar.y one time I

special nuclear material form I

,ggder this license 1

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'.e A.'q985 kilograms of I

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A.

Uranium enriched in A.

As described iry 1; hat U-235 isotope.

portion of the 4tcensee's

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in-Item 9 of-t ds license 3

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U-233 8.

Any B;3 5 kilograms of I

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.D C.

Plutonium C.

Encapsulated and/or

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3 kilograms total Pu l

L Sealed Sources l

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Plutonium D.

8 red but unseparatees.

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1 kilogram total Pu I

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Plutonium E.rPlated,. calibration E.

5 grams total Pu D

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F.

Plutonium F.

Solutions, precipitates F.

5 grams total Pu 3

j and solids W

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

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8808220221 880817 I

PDR ADOCK 07000734 I

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N: C Form 3N A.

U.S. NUCLE An f.EGULATORY COMMIS$10N 2

,, m iI Linn.e number 3N3 696

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MATERIALS LICENSE Amendment No. 10 L

i SUPPLEMENTARY SHEET 7O 734 L

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Authorized use:

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

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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;

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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

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March 9, (2), March 22, and April 26, 1988.

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'r 1l 10. Authorized Place of Use:

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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:

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

a.

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

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Copies of all other safety-related records (e.g.,. plant al ations and 1

additions, abnomal occurrences associated wi, tit radioactiv

releases,

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l audits and inspections, instrument calibrations, ALARA fin gs, training t

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and retraining, personnel exposuresi routine radiation and vironmental F

l surveys) shall be retained for at least 2 years or longer required by i

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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

lf contained U-235 independent of whether_ double batching is credible.

P 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

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non-compliar.ce with the license or a regulation, r

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i li 14. The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA i l 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 i) i eff' 'nt release data to determine (a) if there are any upward trends developing in 5

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

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

the ALARA concept, and (c) if equipment *or effluent and exposure control is being r

1I properly used, maintained, and inspected.

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NCC wmanA u.s. NUCLE AR REGULATOQY COMMISSi@N m

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l' MATERIALS LICENSE SNM-696, Amendment No. 10 1

SUPPLEMENTARY SHEET

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70-734 I

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The CRSC evaluation, recommendations, and corrective actions shall be

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documented and the report shall be sent to the appropriate operations l

managers and the Vice President, Finance and Administration, I

i 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

l be signed by Health Physics management or a senior staff member before related

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work can commence.

A senior staff member shall be a Health Physics Technician I

l having a minimm 5 years' experience in radiation safety.

An evaluation of

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the safety effs.

.aness of the permit shall be made upon compittion of the work.

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L s needs, shall be given to 116.Radiationsafetytraining,appropriateto'theeaployy'g

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all new employees.

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

l Physics Manager or by a similarly qualified individual.

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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 m,

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can become sirborne.

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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 sempling.

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

1 commencement of operations in any area thlatstias been shutdown for more than L I f

6 months to verify the representativepass! cf ' air sampling.

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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 r l, 1

dual HEPA filtering of the ef. fluent air.

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

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1; dated November 1983, the licensee shall conduct 5eak tssting of sealed plutonium

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sources and alpha sources in tccordance with Annex A "License Condition for Leak j ],

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Testing Sealed Plutonium Sourcis," dated November 1979, and Annex B "Licendt g

3 Condition for Plutonium Alpha Purces," respectively.

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

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

Commission, Washington, DC

'.0555, a report whenever there is any new residential

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l' development within one mile around the site that constitutes a sigitificant change i

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

the environment.

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nmq N C oem 374 A U.S. NUCLE AR REGUL ATORY COMMISsloN l

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l MATERIALS LICENSE SNM-696, Amendment No. 10

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SUPPLEMENTARY SHEET I

70-734 i

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

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

1 procedures for his Radiological Contingency Plan as necessary to implement the j) g supplemented on August 22, 1984.

The licensee shall also maintain implementing j

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Plan.

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

This i

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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

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planning and notification procedures.

The licensee shall make no change in his f

Radiological Contingency Plan that would decreast the response effectiveness of p

the Plan without prior Commission approval as evidenced by a license amendment.

il The licensee may make changes to his Radio)ogical Contingency Plan without prior 1l Commission approval if the changes do not decraase the response effectiveness of I;

the Plan.

The licensee shall maintain records of changas that are made to the l

Plan without prior approval for ? period of 2 years free the date of the change I

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h and shall furnish the Chief, Fue1 Cycle Safety Branch, DWKion of Industrial li I

Washington, DC 20555, and the appropriate NRC Regional Offict(pission, and Medical Nuclear Safety, NMSS, U. S. Nuclear RegulatorytCor p

specified in lj gl (j

Appendix 0 of 10 CFR Part 20, a report containing a descriptio(of each change n

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within 6 months after the change is made.

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y jl24.Attheendofplantlife,thelicenseeshalldecontaminatethe%teandfacilities, k f

authorized as a place of use for special nuclear mat 9tial, in accordance with the general decommissioning plan submitted by swr lette" dated JulF25,1986, and its'

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1i 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 dated November 1983, the release of the fae.ilities and equipment for unrestricted j

g-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

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

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

)26.Thelicenseeisherebyexemptedfromtheprovisionsof10CFR70.24duringthe l

1 hodification of the SV-A criticality alarm system insof ar as this section applies p

R to materials held in the SV-A building under this license subject to the following y

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The criticality alarm system shall be in service in all areas where the P

a.

F-l quantity of special nuclear material (SNM) does not meet the exemption criteria 8

in Section 4.2.1.4 of the specification volume with the exception of the SNM q

i storage vaults in the SV-A building.

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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 system is not in service.

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N C Form 374A U.S. NUCLdAR REouLATO9Y CoMMisStoN PAGE op

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Licenu number l

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MATERIALS LICENSE SNM-696. Amendment ta. 10 I

S'JPPLEMENTARY SHEET l

1 70-734

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l'27.NetwitnstandingthestatementinSection4.2.1.4,PartIIofthelicense,the trip levels will be readjusted af ter each monthly test of the criticality alarm j

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system if the alarm point fails to activate within approximately 5 seconds, more I

than once out of four trials.

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. Notwithstanding the statements in Section 4.2.1.4, Part II of the license, no I

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material handling shall De allowed in any area in which the required criticality ql alarm system is inoperative.

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

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 1

3 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

ij subject to the following w difications:

g Thesurveyfrecuenciesandcontaminationcontrolmeasurehpecifiedinthe f

a.

license shall be used whenever work is performed on or witLequipment which y

handles radioactive material.

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Any work performed on equipment which handled rddioactive Esterials shall be I

b.

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 Ij is maintained.

d.

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

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

increased to the levels specified for Type II laboratories.

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

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inspection, at least annually, of ali areas specified.

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FOR THE NUCLEAR REGULATORY COMMISSION M &gned By:

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Leland C. Rouse t

l Date:

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Division of Industrial and Medical Nuclear Safety

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Washington, DC 20555 g

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