ML20154D365

Amend 50 to License SNM-696 for General Atomics

ML20154D365
Person / Time
Site:	07000734
Issue date:	09/30/1998
From:	Emeigh C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20154D363	List: ML20154D359 ML20154D365 ML20154D370
References
NUDOCS 9810070203
Download: ML20154D365 (8)

Text

____

NIC FORM 374 PAGE I

OF R

PAGES U.S. NUCLEAR REGULATORY COMMISSION 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 1, Parts 3,0,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a hcense is hereby issued ausorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designa below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

Licensee

1. General Atomics

3. License Number SNM-696, Amendment 50

2. P.O. Box 85608

4. Expiration Date December 31,1989 San Diego, California 92186-9784

5. Docket No.70-734

_n (7 t n Reference No.

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wg N[iCliemical and/or Physical ' </ ^. 8. Maximum amount that Licensee

6. Byproduct Source, and/or Special Nuclear Material Form May Possess at Any One Time Y

Under This License A,yEnriched up to 19'99No I.4 200 kilograms U-235 A.

Uranium

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j U-235 >

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C B.

Uranium H

,g.1.Eariched'20,to,100%. B.I'ess than 5000 gm*

B W

U:q $'i g.P cf

$l~*

p M2 6

p Q ChAny,lgf%4

,C7 Less than 2000 gm C.

U-233 WD 9 4jf O{J r

L U-233*

g 4W.

9 D.

Plutonium O. Encapsulated and/O D.

Less than 2000 gm 3ssagurgesM total Pu*

E.

Plutonium E.

Bred but unseparated E.

Less than 1000 gm total Pu*

F.

Plutonium F,

Plated calibration F.

Less than 5 grams source total Pu*

G.

Plutonium G.

Solutions, precipitates G.

Less than 5 grams solids and total Pu*

The sum total quantity of strategic special nuclear material possessed at any one time must be less than 5,000 grams computed by the formula:

Grams =

grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 + grams plutonium) 9810070203 900930 PDR ADOCK 07000734 c

PDR l

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- NRd FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 of 8 PAGES i

License Number l

SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 50 9.

Authorized place of use: The licensee's San Diego, California site as specified in the aforesaid application and supplements.

10.

This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.

These sections are part of the license, and the licensee is subject to compliance with all listed conditions in each section.

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By: Ch ries W. Emelah. Actina Chief

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Division of Fuel C'ycle Safety and Safeguards, NMSS Washington, DC 20555 (Provided w/ Amendment 31)

Enclosures:

1. License Condition for Leak Testing Sealed Plutonium Sources, dtd 4/93

2. License Condition for Plutonium Alpha j

Sources, dtd 4/93 i

3. Guidelines for Decontamination of I

Facilities..., dtd 4/93 l

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NRt FORM 374A U.S. NUCLEAR RECULATORY COMMISSION PAGE 3 of 3 PAGES License Number SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SIIEET 70-734 Amendment No. 50 SAFETY CONDITIONS S-1.

Authorized use: For use in accordance with statements, representations, and conditions contained in Part ll " License Specifications" dated July 24,1981, and supplements dated March 16 and December 24,1982; February 4, November 14, and November 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; March 4, March 9 (2), March 22, April 26, August 22, September 8, and November 2,1988; May 25 and November 17,1989; June 27,1990; April 30 and September 27,1991; March 5, March 18, June 24, and September 10,1992; January 20,1995; the "SVA Decommissioning Plan" dated April 1,1990 (submitted by letter dated March 30,1990); August 22,1990 (submitted by letter dated August 24,1990); June 15 1992j,t$at% August 12 1994; M July 12 and August 23,1994; Group 6 Laboratories unrestricted opebqlles Laboratories unrestricted use{1996; October 15,1996, April 30,1997

/

use request dated August @$)

unrestricted use request dated July 17,1997; Building 30 Laboratories unrestricted use release dated July 25,1997; and January 29,1998; Site Decommissiemnjflan dated October 11 and December 5,1996: Aprib18,1997;' January 15,,19ppbHot C ecommissioning Plan dated April 22,1998, Group jp Labs date August 14; Building 27 of release dated August 25, and Building 30 - Phase 11' dated Sept. ber A,199_81 h *

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Records of all safety-r atedh;

• ods' M/rfyIsIs s;halj be refained as follows:

S-2.

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Copies of critica!ity'hfld radiaSon sa et/anap. p' hall-6e retained for at Ica e years or for 6 a.

ses s months after a projec(i termiriated,pJcheVe',r is Ign'ger.

b.

Copies of all other safety elated records

, pknt alterations and additiores, abnormal occurrences associated withEdloactivit e ases, audits and inspections, instrument calibrations, ALARA findings, training and retraining, personnel exposures, routine radiation and environmental surveys) shall be retained for at least 2 years or longer if required by regulations.

S-3.

Notwithstanding the statements in Section 5.4.2 in the License Specification Volume (Part 11), if double batching is not credible, the maximum safe batch size shall be no more than 75 percent of the minimum critical mass independent of the degree of water moderation and reflection. However, when the Th/U atomic ratio is 2 3.6 and the H/U s 20, the maximum safe batch size may be increased to 790 g contained U-235 independent of whether double batching is credible.

S-4.

The Director QACD, upon recommendation of the appropriate manager within QACD, shall have authority to require immediate termination of activities and/or corrective action in any situation which, in their judgment, could lead to the unnecessary exposure of personnel to ionizing radiation, release of radioactive material, loss or damage of property, or non-compliance with the license or a regulation.

NkC FORM 374 A U.S. NUCLEAR REGULATORY CO x MATERIALS LICENSE SUPPLEMENTARY SHEET

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S-14 Deleted by Amendment 14 dated August 3.1E

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f 'if renumbered to S-14 in Amendment 23 dated C

>r S-23 was incorporated into License Condition -

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Condition S-9 later became S-1.

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S-15. At the end of plant life, the licensee shall decc use for special nuclear material, in accordana Je your letter dated July 25,1986, and its suppia gqj grounds can be released for unrestricted use.

• <N available for decommissioning the facility, proh m4y incorporated as a condition of the license.

Release of equipment, facilitig,%p pji p

S-16.

rpackages n y

shall be in accordance with4he attached "Gu;

% d.Yh Prior to Release for Unrest'rteted Use or Term:

Nuclear Material," dated 4pril 1993.

' ~ $g Deleted by Amendmen?p7, September 1991

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released for general use.

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S-18. Notwithstanding the stakemerifin Sectiod blh.

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after each monthly test 3f the Njticality M$nd Y

approximately 5 secondspore tNaiche'e.out :

S-19. Notwithstanding the statem dts in Section 4 2.

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allowed in any area in which th'e required cw 2

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'y S-20. Deleted by Amendment 37, September 1996 qs sit 1 s

released fcc general use.

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S 21. Deleted by Amendment 31 dated September i Jl j

on October 3,1988.

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+y S-22. Deleted by Amendment 37, September 199i

- U released for general use.

U S-23. The licensee shall maintain and execute the n dated October 10,1997, supplemented by letb 1

licensee consistent with the provisions of 10 CF u

S-24 The licensee shall develop individual survey ;:

NRC a 30-day notification, prior to GA initiatm inspections / surveys if required.

S-25 The licensee must submit for review and app j-data and planned decommissioning procedun,

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I NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 of 8 PAGES License Number SNM-696 MATERIALS LICENSE D eket r Reference Number r

SUPPLEMENTARY SHEET 70- m l

Amendment No. 50 i

S-5.

The Criticality and Radiation Safety Committee (CRSC), functioning as an ALARA Committee, shall l

meet at least annually to review (1) reports of audits and inspections performed since the last ALARA review and (2) employee exposures and effluent release data to determine (a) if there are any upward

- trends developing in personnel exposures for identifiable categories of workers, types of operations, or effluent releases, (b)if exposures and releases might be lowered in accordance with the ALARA concept, and (c) if equipment for effluent and exposure control is being properly used, maintained, and inspected.

The CRSC evaluation, recommendations, and corrective actions shall be documented and the report shall be sent to the appropriate operations managers and the Vice President, Finance and Administration.

cga REGf material not covered by a @$PS) shall be issueNor all unplanned S-6.

Radiological Work Permits (R

. The RWP shall be signed b,y Health Physics management or a senior 7

staff member before related. work can commence. A sento staff member shall be a Health Physics Technician having a miniolumlof 4 years' experience in rad (f3 tion safety. An evaluati effectiveness of the pe/rhit shall-

'made upon[mTietion offhe work.

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Radiation safety trainih, approhrisojhojmfl fee's neeh,shall be given to all new emp S-7.

Radiation safety trainik ancMo. \\

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.2 U.ian tie ebnductgby the Health Physics Manager or by a doc't'ri S-8.

l similarly qualified individdal. T@(e y,qu' fiddtogresentJt?dds$p6ger rnay delegate trainin course to an individual % is unk S-9.

Continuous air sampling sh cond Ia r

ere licensed material can become airborne.

S-10. The location of air samplers shall e (Medqedhnbally and whenever any process or equipment changes are made to verify the representativeness of work area air sampling. In addition, the location of air samplers shall be checked at the commencement of operations in any area that has been shutdown for more than 6 months to verify the representativeness of air sampling.

S-11. The laboratories in which plutonium in a dispersible form may be used shall have exhaust ventilation systems separate from other building exhausts and shall provide dual HEPA filtering of the effluent air.

S-12. Sealed Plutonium sources shall be subject to the leak testing and actions specified in the attached

" License Condition for Leak Testing Sealed Plutonium Sources," dated April 1993.

Plutonium alpha sources shall be subject to the actions specified in the attached " License Condition for Plutonium Alpha Sources," dated April 1993.

S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards, NMSS, U.S. Nuclear Regulatory Commission, Washington, DC 20555, a report l

whenever there is any new residential development within 1 mile around the site that constitutes a significant change in parameters that may be affected by the release of radioactive materials into the environment.

NkC FORM 374A U.S. NUCLEAR REGULA10RY COMMISSION PAGE $

of 8 PAGES License Number SNM-696 MATERIALS LICENSE D eket r Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 50 S-14 Deleted by Amendment 14 dated August 3,1990 (originally numbered S-23 in 1990 - 1992 and renumbered to S-14 in Amendment 23 dated October 7,1993). The information in License Condition S-23 was incorporated into License Condition S-9 by adding the date of May 25,1989; License Condition S-9 later became S-1.

S-15. At the end of piant life, the licensee shall decontaminate the site and facilities, authorized as a place of use for special nuclear material, in accordance with the general decommissioning plan submitted by your letter dated July 25,1986, and its supplement dated October 15,1986, so that these facilities and grounds can be released for unrestricted use. The corporate commitment that funds will be made available for decommissioning the facility, provided by letter dated September 10,1986, is hereby incorporated as a condition of the license,R E W PAR Release of equipment, facilities or~ packages to thI60 restricted area or to uncontrolled areas onsite N

S-16.

g shall be in accordance with4he attached " Guidelines fdr Decontamination of Facilities and Equipment Prior to Release for Unrest'ricted Use or Termination of Lfg(ses for Byp Nuclear Material," dateci: April 1993.

Deleted by Amendmedt'37, Septe'rn(ber 1996. Th[

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SVA facilh has been decommissioned and S-17.

released for general uhe.

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Notwithstanding the st (emeMn Shhlfo'r 4 atter each monthly test'of,the criticalitkp[f art il of tiihlicense, the trip levels will be readjusted l

S-18.

ystem if the al~'rm point fails to activate within a

r trialp approximately 5 secondsp/

ora than once~oot o "c.e N

Notwithstanding the statemIrjt9 in Section'4.2.1.4, Pythof the license, no material handling shall b S-19.

allowed in any area in which the required criticality &, alarm system is inoperative.

n g-f..g S-20. Deleted by Amendment 37 September 1996. The SVA facility has been decommissioned and released for general use.

S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to the licensee on October 3,1988.

S-22. Deleted by Amendment 37, September 1996. The SVA facility has beer: decommissioned and released for general use.

S-23. The licensee shall maintain and execute the response measures described in the Emergency Plan dated October 10,1997, supplemented by letter dated November 6,1997, or as further revised by the licensee consistent with the provisions of 10 CFR 70.32(i).

S-24 The licensee shall develop individual survey plans for each facility or group of laboratories and provide NRC a 30-day notification, prior to GA initiating a final survey, to allow the NRC to schedule in-process inspections / surveys if required.

S-25 The licensee must submit for review and approval to NRC residual contamination and characterization j

data and planned decommissioning procedures for areas where

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 6 of 8 PAGES l

License Number i

SNM-696 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-734 Amendment No. 50

1. Decommissioning procedures will be required that have not been used by the licensee in i

previous decommissioning activities or have not been identified in the Site Decommissioning 1

Plan dated October 11,1996, as amended December 5,1996; April 18,1997; and January 15, 1998;

2. Workers would be entering areas where surface contamination and radiation levels are i

significantly higher than routinely encountered during previous decommissioning operations;

3. Procedures could result in significantly greater airbome concentrations of radioactive materials than have been present in previous decommissioning operations; or Procedures could result in sigillfic3ns)fgpajer releases of radioactive material to the 4.

environment than thoss as~sociated with previous decommissioning operations.

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NR'C FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 7 of 8 PAGES License Number SNM-696 MATERIALS LICENSE DoctuH w Rererence Number SUPPLEMENTARY SHEET 70-734 Amendment No. 50 SAFEGUARDS CONDITIONS SECTION 1.0 -- FACILITY ORGANIZATION Currently there is no license condition in this section. The necessary information has been incorporated into cn cpproved Fundamental Nuclear Material Control Plan, dated February 1998.

SECTION 2.0 - FACILITY OPERATION SG-2.1 Deleted by Amendment 37, Septembpr 1_996. Not applicable under a possession only license.

cA.HEG/

P Deleted by Amendmen 3,7)S6ptember 199Mko pplimble under a possession only license.

SG-2.2 Deleted by Amendmtdit 37, September 1996. Not appji cEble under a possession only SG-2.3 Co Qp j

,4 Deleted by Amenpent 37,p'pt, ember 19962 t applip> ble under a possession only license.

SG-2.4 m

s SECTION 3.0 - MEASUREh[dNTS 4p O

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-A g3 Deleted by Amer [Olenih.m S5p$r'rE[lh06."Nh..s SG-3.1 applibeble under a possession only license.

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Deleted by Amendrnje t 37.l Septemberf1 Not app $

V SG-3.2 eble under a possession only license.

SG-3.3 Deleted by AmendmeniG7, Septe A 1996. N plicable under a possession only license.

SECTION 4.0 -- MEASUREMENT CON O kk' W -ff I

SG-4.1 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.4 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.5 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.6 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.7 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-4.8 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

I NRC FORM 374A U.S. NUCLEAR REGUL.ATORY COMMISSION PAGE a of a PAGES l

License Number SNM-696 MATERIALS LICENSE Docket or Reference Number L

SUPPLEMENTARY SHEET 70-734 L

Amendment No. 50 l

SECTION 5.0 - INVENTORY SG-5.1 Deleted by Amendment 37, SepMmber 1996. Not applicable under a possession only license.

SG-5.2 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SG-5.3 Deleted by Amendment 37, September 1996. Not applicable under a possession only license.

SECHON 6.0 - RECORDS AND REPORTS SG-6.1 Deleted by Amendment 37, Septemb 1996. Not applicable under a possession only license.

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GW SECTION 7.0 -- INTERNAL CONTROLV y

e SG-7.1 Deleted by Amendme'ot 37, September 1996. Not a cable under a possession only license.

ea SEC. TION 8.0 - MANAGEMEf4T NN 7

Deleted by Ameobent 37[) ) rnber119.9%M (, hot appli T

O SG-8.1 ble under a possession only license.

iiES SIN E Tk ORJORMULA QUANTITIES OF STRATEGIC SECTION 9.0 - PHYSICAL OT i

SPECIAL NUCCFAR IMTERid

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The licensee shall foh(Pipn for the'Pfotectionthe measurps[dAsdlBe physical protection plan entitled, " Fixed SG-9.1 Site and Transportatior ecial Nuclear Material of Moderate and Low Strategic Significance," d6tedfay 1989, sujjgnitt by letter dated May 8,1989; and as it may be further revised in accordance witNth!kpnk/isTons of 10 CFR 70.32(e).

SECTION -10.0 -- TEMP _QRARY OR ONE TIME CONDITIONS SG-10.1 Deleted by Amendment 31, dated July 1995.

SG-10.2 Deleted by Amendment 31, dated July 1995.

SG-10.3 Deleted by Amendment 31, dated July 1995.

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