ML20137F419

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Amend 39 to License SNM-0696 for General Atomics,Revising Safety License Condition S-1 as Listed
ML20137F419
Person / Time
Site: 07000734
Issue date: 03/27/1997
From: Weber M
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20137F413 List:
References
NUDOCS 9704010099
Download: ML20137F419 (9)


Text

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NRC YORM 374 1

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U.S. NUCLE AR REGULATORY COMMISSION MATERIALS LICENSE i

g Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, j

3 l

Code of Federal Regulations Chapter 1, Parts 30,31,32,33,34,35,39,40 and 70, and in reliance on statements and representations heretofore p!

l made by the licensee, a license is hereby issued author. zing the licensee to receive, acquire, possess, and transfer byproduct, source, and special 5!

I nuclear material designated below; to use such rnaterial for the purpose (s) and at the place (s) designated below; to de!lver or transfer such material i

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 m Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclear i

Regulatory Commission now or hereafter in effect and to any conditions speciGed below.

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Licensee l

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3. Ucense number l

General Atomics SNM-696, i

Amendment 39 l

2.

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P.O. Box 85608

4. Expiration date December 31, 1989
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San Diego, California 92186-9784' lE i

5. Docket or 70-734 iE I,

Reference No jp i

6. Byproduct, source, and/or
7. Chemical and/or physical
8. Maximum amount that licensee jE I

special nuclear material form may possess at any one time jf under this license I

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A.

Uranium A.

Enriched up to 19.99%

A.

200 kilograms U-235 E

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,1 U-235 i

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i B.

Uranium B.

Enriched 20 to 100% U-235 B.

Less than 5000 gm*

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C.

U-233 C.

Any C.

Less than 2000 gm lti l

i U-233*

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Plutonium D.

Encapsulated and/or D.

Less than 2000 gm

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sealed sources total Pu*

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E.

Plutonium E.

Bred but unseparated E.

Less than 1000 gm

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total ?u*

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F.

Plutonium F.

Plated calibration F.

Less than 5 grams g

source total Pu*

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Plutonium G.

Solutions, precipitates G.

Less than 5 grams

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solids and total Pu*

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l The sum total quantity of strategic special nuclear material possessed at any one g

time must be less than 5,000 grams computed by the formula:

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i Grass =

grams U-235 in uranium enriched to 20% or more plus 2.5 (grams U-233 +

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i grams plutonium) ll i

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l 9.

Authorized place of use:

The licensee's San Diego, California site as specified in ll the aforesaid application and supplements.

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SNM-696 Amendment 39 l-g MATERIALS LICENSE Docket or Reference Number g

SUPPLEMENTARY SHEET 70-734 m

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10.

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

Safeguards Conditions. These sections are part of the license, and the licensee I

is subject to compliance with all listed conditions in each section.

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Division of Fuel Cycle Safety i

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Washington, DC 10555 g

N (Provided w/ Amendment 31)

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Enclosures:

1. License Condition for Leak Testing i

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Sealed Plutonium Sources, dtd 4/93 N

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2. License Condition for Plutonium Alpha ii N

Sources, dtd 4/93 N

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3. Guidelines for Decontamination of I

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NRC FORM 374A U.S. NUCLEAR REcVLATORY COMMISSION PAGE 3

or 9

PAGES g

i NO License Number g

SNM-696 Amendment 39 g'

MATERIALS LICENSE Docket or Reference Number g

SUPPLEMENTARY SHEET 7:;-734 ll l

3 SAFETY CONDITIONS 1

i!

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SAFETY CONDITIONS E

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S-1.

Authorized use: For use in accordance with statements, representations, and i'

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conditions contained in Part II

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

supplenants dated March 16 and December 24, 1982; February 4, November 14, and Il 1

g November 15, 1983; April 10, April 12, June 28, September 4, and September 7, 1984; i'

i l

December 5, 1985; May 23, September 25, and December 10, 1986; December 21, 1987; i

l March 4, March 9 (2), March 22, Aprji 267: August 22, September 8, and November 2, i

g 1988; May 25 and November 17,g1989; Dune 27,7 1990;jApril 30 and September 27, 1991; i

p March 5, March 18, June 24, land September 10,1992';/ January 20, 1995; and in the i ',

"SVA Decommissioning Plan" dated April 1, 1990 (submitted by letter dated March 30, Ei 1990); August 22, 1990 / submitted by letter dated August 23 1990); June 15, 1992; Il July 12andAugust23M994; Group 6Laboratoriesunrestrfckeduserequestdated ii y

August 12, 1994; March 1, 1995; Group 7 Laboratories unrestricted use request dated i i i

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December 5, 1995; Group 88 Laboratories unrestricted use request dated August 23, E'

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1996; and October 15, 1996. *

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S-2.

Records of all safety-related reports and~analys.es'shall be rita.'ined as follows:

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l Copies of criticality and-radiation-safety analyses shall be' retained for at i

a.

least 2 ye.wf or for 6 months af ter a project (is t.erminated7whichever is I,

longer.

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Copiesofall(othersafety-relatedrecords_(e.g.,' planta]terationsand i

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additions, abnormal occurrences associated with radioactivity releases, audits i

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and inspections Linstrument. calibrations, ALARA findings;-training and l

retraining, personnel exposures, routine rtdiation and environmental surveys) i shall be retained.for at least 2! years or longer if; required by regulations.

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S-3.

Notwithstanding the statements in Section 5.4.2 in ths License Specification Volume j

N (Part II), if double batching,is not credible, the maximum safe batch size shall be 5

no more than 75 percent of the minimum critical mass independent of the degree of gi g

N water moderation and reflection.

However, when the Th/U atomic ratio is 1 3.6 and I

g the H/U s 20, the maximum safe batch size may be increased to 790 g contained U-235 g

I independent of whether double batching is credible.

N g

i N S-4.

The Director QACD, upon recommendation of the appropriate manager within QACD, g

N shall have authority to require immediate termination of activities and/or g

N corrective action in any situation which, in their judgment, could lead to the 5

unnecessary exposure of personnel to ionizing radiation, release of radioactivs I.

material, loss or damage of property, or non-compliance with the license or a N

regulation.

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FORM 374A u.S. NUCLEAR REcVLATORY COMMISSION PAGE 4

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PAGES

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l Licent.e Number g'

,p SNM-696 Amendment 39 g

l MATERIALS LICENSE Docket or Reference Number l

l SUPPLEMENTARY SHEET 70-734 I

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SAFETY CONDITIONS E S-5.

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

Committee, shall meet at least annually to review (1) reports of audits and i

I inspections performed since the last ALARA review and (2) employee exposures and i

I effluent release data to determine (a) if there are any upward trends developing in i

I personnel exposures for identifiable categories of workers, types of operations, or i

I effluent releases, (b) if expot.ures and releases might be lowered in accordance tl 1

with the ALARA concept, and (c) if equipment for effluent and exposure control is Il I

being properly used, maintained, and inspected.

I 3

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The CRSC evaluation, recommendations, and corrective actions shall be documented i

~1 and the report shall be sent to the appropriate operations managers and the Vice i

.I President, Finance and Administ d ion" RF 0/

i Radiological Work Permitsr(RWP$) Yshall be issued fo/', ll unplanned or non-ro 1

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S-6.

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work with licensed materfal' not covered by a WA.

Th~e-RWPs hall be signed by Health g'

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Physics management oria senior staff member before relateihvork can commence. A p

l senior staff member shall be a Health Physics Technician hiying a minimum of 5 g

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years' experience in radiation safety. An evaluation of the safety effectiveness g

g of the permit shall'he made~upon completion of the work.

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1 S-7.

Radiation safety training, appropriate to the employee.'s needs,sshall be given to l

1 all new employees.

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q S-8.

Radiation safety training and indoctrination shall be conducted:by the Health

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Physics Manager;or by a similarly, qualified individual. The Health Physics Manager v

y maydelegatetraininginjthatportionlofjthecoursetoanindiyidualwhois y

uniquely og4H fied to present it.

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4 S-9.

Continuous air sampling shall be' conducted in:any area where licensed material can y

become airborne.

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l S-10. The location of air samplers shall be checked annually and whenever any process or I

I equipment changes are made to verify the representativeness of work area air y

I sampling.

In addition, the location of air samplers shall be checked at the I;

yj commencement of operations in any area that has been shutdown for more than 6 months to verify the representativeness of air sampling.

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S-11. The laboratories in which plutonium in a dispersible form may be used shall have Il exhaust ventilation systems separate from other building exhausts and shall provide I;

l dual HEPA filtering of the effluent air.

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

I in the attached " License Condition for Leak Testing Scaled Plutonium Sources,"

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dated April 1993.

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W il Plutonium alpha sources shall be subject to the actions specified in the attached Il El

" License Condition for Plutonium Alpha Sources," dated April 1993.

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MATERIALS LICENSE Docgegorgference Number l

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SUPPLEMENTARY SHEET l

lj SAFETY CONDITIONS N

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4 S-13. The licensee shall prepare and submit to the Chief, Licensing Branch, Division of Ii I

Fuel Cycle Safety and Safeguards, leiSS, U.S. Nuclear Regulatory Commission, il N

Washington, DC 20555, a report whenever there is any new residential development ii I

within 1 mile around the site that constitutes a significant change in parameters i

I that may be affected by the release of radioactive materials into the environment.

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S-14 Deleted by Amendment 14 dated August 3, 1990 (originally numbered S-23 in 1990 -

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1992 and renumbered to S-14 in Amendment 23 dated October 7, 1993). The information i

I in License Condition S-23 was incorporated into License Condition S-9 by adding the i

i date of May 25, 1989* License o tgn g9[

r became S-1.

S-15. At the end of plant.ife,-tbe licensee shall decontaIninate the site and facilities, g

generaldecommissionin~gfus'eforspecialnuclearmater}al authorized as a place of in accordance with the i

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plan submitted by your letter date July 25, 1986, and its l

sothatthesefacilitici(s,andgroundscanbe q

l supplement dated October 15, 1986, g

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released for unrestr,1cted use. The corporate commitment thatTfunds will be made p

i availablefordecoimeissioningthefacility,providedbylette}redatedSeptember10, yl

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1985, is hereby incorporated as a condition of theilicense.

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q S-16. Release of equipment, facilities, or packages to!the unrestricted area or to i 1 s

l uncontrolled area's onsite shall be in accordance;with the attach ~ed " Guidelines for g

1 Decontamination;of Facilities and Equipment Prio' lto' Release foe Unrestricted Use g.

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or Termination of Licenses for Byproduct, Source, or Special Nuclear Material,"

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dated April 1993P af.

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S-17. Deleted by Amenda'lt 37,~ September 1996'.! (ThetSVA facility has'been decommissioned e

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q and released for general use.

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S-18. Notwithstanding the# statement in'Section 4.2.1.4,lPart II$f the license, the trip l

y levels will be readjustcd after each monthly test'of the' criticality alarm system 3

if the alarm point fails to activate within approximately 5 seconds, more than once out of four trials.

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S-19. Notwithstanding the statements in Section 4.2.1.4, Part II of the license, no l'

material handling shall be allowed in any area in which the required criticality 4

alarm system is inoperative.

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I S-20. Deleted by Amendment 37, September 1996. The SVA facility has been decommissioned

,I and released for general use.

S-21. Deleted by Amendment 31 dated September 1995. Fuel elements were shipped back to II l

the licensee on October 3, 1988.

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I The SVA facility has been decommissioned 8}lS-22.DeletedbyAmendment37, September 1996.

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and released for general use.

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~ g LKense Number g

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SNM-696 Amendment 39 i

g MATERIALS LICENSE r.xwici or nefecce Number g

g SUPPLEMENTARY SHEET 70-734 g

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y SAFETY CONDITIONS N

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I S-23. The licensee shall maintain and execute the response measures described in the i

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Emergency Plan dated August 1995 (letter dated August 30,1995), and as revised by E

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letter dated June 6,1996, with pages dated May 19%; or as further revised by the E

1-licensee consistent with the provisions of 10 CFR 70.32(i).

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U.S. NUCLEAR RE2ULATORY COMMISSION PAGE 7

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pacts l

License Number g

.l SNM-696 Amendment 39 g

MATERIALS LICENSE oocteior nererence Number g

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SUPPLEMENTARY SHEET 70-734 l

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I SAFEGUARDS CONDITIONS i

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SAFEGUARDS CONDITIONS i

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l SECTION I.0 -- FACILITY ORGANIZATION l

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I Currently there are no license conditions in this section. The necessary information has i

I been incorporated into an approved plan.

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I SECTION 2.0 -- FACILITY OPERATION g

DeletedbyAmendment37,g[emb%e 19b applicable under a possession l

SG-2.1 only license.

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DeletedbyAmendmenDvt 37, September 19%. Not applicable under a possession p

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SG-2.2 only license.

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SG-2.3 DeletedbyAnddment37,; September 1996. Not applicabl under a possession A

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SG-3.1 Deleted by Amendment 37,'Septembe" ] jf \\

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3 SG-3.2 DeletedbyAmeMment37,Septembe'Y996. NotApplicab1MSnderapossession l

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SG-3.3 Deleted by Amendment ~37, September 1996. Not applicable under a possession 4

I only license.

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I SECTION 4.0 -- MEASUREMENT CONTROL 1

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

only license.

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i SS-4.2 Deleted by Amendment 37, September 1996. Not applicable under a possession I

1 only license.

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

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

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License Number g

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SNM-696 Amendment 39 g

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B SUPPLEMENTARY SHEET 70-734 i

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SAFEGUARDS CONDITIONS i I I,

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

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orly license.

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SG-4.6 Deleted by Amendment 37, September 19%.

Not applicable under a possession i

I only license.

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SG-4.7 Deleted by Amendment 37, September 1996.

Not applicable under a possession ii I

only license.

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t applicable under a possession i

1 SG-4.8 Deleted by Amendment 37, SeplA y Ig6

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I only license.

g SECTION 5.0 -- INVENTORY V

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I SG-5.1 Deleted by Amendment 37, September 1996.

Notapplicalf[Eunderapossession s

I only license.,

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l SG-5.2 Deleted by Amendment 37,$ September 1996.

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l' SG-5.3 Deleted by Amendment 37, September 1996. Not: applicable un., der a possession g

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SECTION 6.0 -- RECORDS'AND REPORTS 1

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SECTION 7.0 -- INTERNAL CONTROL 4

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SG-7.1 Deleted by Amendment 37, September 1996.

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I SECTION 8.0 -- MANAGEMENT s

I SG-8.1 Deleted by Amendment 37, September 1996.

Not applicable under a possession g

only license.

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SECTION 9.0 -- PHYSICAL PROTECTION REQUIREMENTS FOR FORMULA 00ANTITIES OF STRATEGIC k

SPECIAL NUCLEAR MATERIAL EI M

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I SG-9.1 The licensee shall follow the measures described in the physical protection I

plan entitled, " Fixed Site and Transportation Plan for the Protection of E,

Spect-1 Nuclear Material of Moderate and Low Strategic Significance," dated May E

198'), submitted by letter dated May 8, 1989; and as it may be further revised E.

l in accordance with the provisions of 10 CFR 70.32(e).

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SUPPLEMENTARY SHEET 70-734 M

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SECTION -10.0 -- TEMPORARY OR ONE TIME CONDITIONS

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SG-10.1 Deleted by Amendment 31, dated July 1995.

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

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