ML20203B932

Amend 1 to License SNM-960 for General Electric Co

ML20203B932
Person / Time
Site:	07000754
Issue date:	02/12/1998
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203B930	List: ML20203B924 ML20203B932 ML20203B937
References
NUDOCS 9802250005
Download: ML20203B932 (7)

Text

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! NAC ToRM 374 u.S. NUCLE AQ RE@uLAToRY CoMMISSloN

1. ' E } O' 6 "I ;g!g g f , llI (10 89) , ,

l MATERIALS LICENSE g I

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

(f Cde of Federal Regulations, Chapter I, Parts 30. 31,32,33,34,35, 39,40 and 70, and in reliance on statements and representations heretofore lp ll made by the licenser, a license is hereby issued authorizing the licenwe to receive, acquire, posse;s, and transfer byproduct source, and special IN I nuclear material designated below; to uw such material for the purpose (s) and at the place (s) desigi sted below; to deliver or transfer such material to persons authoriicd to receive it in accordance w ith the regulations of the rpplicable 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 !

l Regulatory Commission now or hereafter in effect and to any conditions specified belaw.  !

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I Licensee I SNM-960 g General Electric Company y

1. 3. Ucense number Amendment i gri i P.O. Box 460 February 28,1999 Pleasanton, Califomia h ( Qration date hl 2.

l l; 5. Docket or , _ 70 754 16 y

gi Reference No jli l 6. Byprmiuct, source, and/or 7. Chemical and/or physical 8. Maximum amount that heensee j li specia' nuclear material form may possess at ny one time {

cnder this license j s

,l 1 !i A. U 235 enrichui to less A. The material may be in A. 50 kilograms  !

lll' than or equal to the form of irradiated it li 10 percent for special niiclear material j i authorized activities with its attendar't

! byproduct and reactor-  !

lil, produced transuranics l 1

I B. U-235 enriched to more B. The material may be in B. 4 kilograms than 10 percent the form of irradiated i]L

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for authorized activities special nuclear material with its attendant F

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ll byproduct and reactor- l ll produc.ed transuranics !3 K

0 h C. U-235 C. In any urwradiated form C. Less than 1 effective kilogram j

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I I D. Plutonium D. Containted or sealed D. 100 grams of !I

1. M form in addition to the Plutonium l

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irradiated quantities

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1 E. U-233 E. In any form E. 100 grams of U 233 E I R I t I I I i l 9. Authorized Place of Use: The licensee's facilities in the Vallecitos Nuclear Ceriter located in y l Pleasanton, Califomic., as described in Appendix A of their December 1,1992, application. I I I I I (g I 9002250005 980212

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10. This licensee shall be deemed to contain three sections: Safety Cond:tions, Safeguards q Conditions, and Transporation Conditions. All these sections art part of the license and the q i licensee is subject to compliance with all listed conditions in each section. N 4

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FOR THE NUCLEAR REGULATORY COMMISSION g N

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}t4'al By Mbl F. Weber f b)A R Date:bW"1 $' '

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i and Safeguards q Washington, DC 20555 W j l i i E l ),  !

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q MATERIAL,S LICENSE twici o, neve,ence sumner y SUPPLEMENTARY SHEET 70-754 SAFETY CONDIT!0MS g

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4 SAFETY CONDITIONS

1. N S-1. Authorized Use: For actaires m ocordance with statements, representations and conditions speci'iad in g Appendix A of the licenseet .4pplication dsted December 1,1992 (letter dated December 9,1992),

with supplements dated December 3,1993 (letter dated December 8,1993), and June 4,1997.

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S-2. On or before January 28,1999, the licensee s ll s rrdfor NRC review a safety anaysis for facility l

y operations, as descri%d in the app g i CG U g

S-3 Sealed Plutonium sources shqll 6je tibject to the leak testing an ogas specified in the attached

" License Condition for Leak Tpping Sealed Plutonium Sources," datedfhril 1993.

U S-4. Release of equipenent or m erials for unrestricted use shall be in accord with the attached N

y " Guidelines for Decentinpation'of Fg.ilities and Equipment Prior to ReleasMr Unrestricted _

uct, Source, or Special one'ar Maddal," April 1993.

y Use or Termination ofgses f6(

U S-5. The licensee shall dbmmission the faal s !n'aMonsan the general @ commission plan as submitted bktter dated FcLtda(y,1'7,1982. 'ghe rdal;' commitment assure that such decommissiongg,is accomplished,, resentedirtthelipen s letter of 14,1979,

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g S-6. The licensee shall provjde to the NRC copfes tg pgrpal report summarizinghe effiuent monitoring and U

' environmental surveillarica progratyls at the Valleates F6ciear Center.?This report shall be sent to the .

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g Chief, Licensing BranshgDivision of Fuel Cycl Safeti and Safeguirds, NMS$70.8. Nuclear Regulatory E Commission, WashingtoneDC 20555, and the blRC Regid6al Office-RegiorW at the address specified in y

Appendix D of 10 CFR Phrt 20.

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y /// m W S-7. Exemptions to the requirements'of 10 CFR 70.24, " Criticality Accident l Requirements," ars hertby grantec' U

l g N pursuant to 10 CFR 70.24(d). The exernptions are granted in accordance with Section 5.9. " Monitor y U l Alarm System," of Appendix A of the application as follows:sK- g g

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g 1. The following areas are exempted from monitor alarm requirements:

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a. Areas where SNM is stored in locations within the United States provided that the SNM is l E I g

fully packaged as for transport in containers meeting all of the general license requirements U of 10 CFR 71 or in containers owned by the General Electric Company and certified for g I transport under the provisions of 10 CFR 71 in accordance with the conoitions of a g a certificate of compliance authorizing delivery of such containers to a carrier for Fissile Class g

g I transport, l b. Building 102 storage pool, l,

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MATERI ALS LICENSE  ! ll I

tgegrgevence sumner SUPPLEMENTARY SHEET H g SAFETY CONDITIONS (g ts

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c. For each nrea in whic.h is stored one (1) sh:pment of packages cc.Tainiry special nuclear g

material licensed pursuant to 10 CFR 71 for transport outside the confines of the Vallecitos lE Nuclear Center insofar as the requirements of Section 70.24 pertain to the material lE s

gl contained in such shipments,

d. For each Groa where there is not more then one " safe batch" (as defined in Section 3.11 of lN h Appendix A of the application) of finisheo reactor fuel rods or assemblies, under conditions g lU E

g which protect against rearrangement of fuelbearing portions into more reactive g

configurations, f gB HFG 4 -

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e. For each area which meets the requirement of a "subcalical s rea" as defined in Section E g

y 3.14 of Appendix A of the application. <f p n Exception to the maximum preset a' arm point of 20 millirems per hour specified in 10 CFR 70.24 is 2

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E y granted for areas described in Section 5.9.3 of / ppendix A of the application provided that the y maximum preset alarm point does not exceed 500 millirems per hour. /.

S-8 Pursuant to 10 CFR 2b.106(b), the licensee is hersby authorized to release radiohetive mateials in E accordance with Section 8.9,"Airt>ome Emuent Control," of Appendix A of the appli:ation.

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S-9 Thq licensee shall estatinsh, maintain, and follow written procedures for carrying out licensed activities. }E g -

g The procedures shall be approved and updated every two years.~

Attachments:

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1. LC for Leak Testing Sealed Plutonium Sources did 4/03

2. Guidelines for Decontamination of Facilities and Equipmen: . 4/93 f

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SG-1.0 PHYSICAL PROTECTION REQUIREMENTS 3 R

W SG-1.1 The licensee shall not possess or use at the Vallecitos Nuclerr Center special nuclear me erial in f' u

g quantities CFR Part 70 has specified in 10 been submitted, andCFR ap -ved73.1(b)(1) 6y'tfieTuclearsntil a detailed Regulatory plan as described Commission.

E N , r. vy, E SG-2.0 FACILITY OPERATION Q '

E 3G 2.1 Notwithstanding those sections within 10 CFR Parts 70 and 74 whiIh establish requirements for E

licensees e 2thorized to possess unirradiated special nuclear material (8NM) in quantities exceeding g E one o'fective kilogram, the licensee may follow the applicable requirem6nts of 10 CFR Parts 70 and g I 74 as though onh authod. zed to possess less than one effective kilogram uf SNM, provided that the E y licensee does rot possess at any one time unitradiated SNM in quantity equal to or greater than one g '

effective kilogram, y g

E 5 A Fundamental Nuclear Material Control Plan which addresses the material control and accounting SG-2.2 3 requirements of 10 CFrt Pections 70.51,70.57, and 70.58; or Section 74.31; or Sections 74.51, $

74.53,74.55, 75.57, and 74.59, as appropriate, shall be submitted to and approved by the Nuclear f g

g Regulatory Commission prior to incmasing the actual holdings of unitradiated SNM under License SNM-960 beyond one affective kilogram.

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( MATERIAL S LICENSE t>uci m neve,ence sumter g W SUPPLEMENTARY SHEET 70-754 lg TRANSPORTATION CONDITIONS j

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] 5 E 5  ! E k T-1.0 TRNISPORTATION SECURITY g 8 ju 4 T-1,1 The licensee shall not import, export, transport in a single shipment, or take delivery of a single 'g I

N shipment free on board at the point where it is gelivered {o an agant or carrier, quantities of special g 8 nuckr matarial af speedied in,10 CF6PMI 73.11bM2) until a detailed plan as desetibed in 10 CFR g 4 g 70.22(g)

Commission. of 10 CFR ,N VPart 70 has beeri submitted, and approved by[the Nuclear

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l LICENSE CONDITION FOR 1.EAK TESTI M f I

i sen tD traANIUM BOtmers l AFRIL 1993 4

A. Each uranium source shall bs tested for leakage at intervals not to exceed 6 months. In the absence of a certificate from a transforor

1. indicating that a test has been made within 6 months prior to the transfer, the sealed source shall not be put into use until tested.

B. The test shall be capable of detecting the presense of 0.00$

• microcurie of alpha contamination on the test sample. The test sample shall be taken from the source er from appropriate accessible surfaces of the device in which the sealed source is permanently or semipermanently mounted or stored. Escords of lostk test results shall be kept in units of microcuries and maintained for inspectica by tha comunieeion.

C. If the test reveals the presence of 0.005 microcurie or more of removable alpha contamination, the licensee shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and 3

repaired by a person appropriately licensed to make such repairs er to be disposed of in accordance with the commission's regulations.

Within 5 days after determining that any source ha,s leaked, the licensee shall file a report with the Division of Fuel Cycle Safety and safeguards, U.S. Nuclear Regulatory Cocaission, Washington, DC

' 20555, describing the soures, test results, extent of contamination, apparent or suspected cause of source failure, and the corrective action taken, h copy of the report shall be sent to the Administrator j

of the nearest NRC Regional Of fice listed in Appendia D of Title 10, code of Federr.1 Regulations, Part 20.

1 D. The periodic leak test required by thiv condition does not apply to sealed sourves that are stored and not hsing used. The sources excepted fitos this test shall be testd for leakage prior to any use or tr.snsfer to another person unisse th+y have been leak tested within l~

6 months prior to the date of use or transfar.

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GUIDELINES FOR DECONTAMINATION OF FACILITIES AND BQUIPMENT PRIOR To Rr. LEASE FOR UNRESTRI T USE OR TERMINATION OF LI ONSES FOR BYFRCDUt., SOURS, OR SPECIAL NUCLEAR MATERIAL i .

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U.S. Nuclear Regulatory Comunission Division of Fuel Cycle Safety and Safeguards Washington, DC 20555 April 1993 e

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't The instructione in this guide, in conjunction with Table 1, specify the radionuclides r.ad radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises c.nd equipment prior to abandonment or release for unrestricted use. The limits in Table 1 de mot

• apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different.

The release of such facilit.tes or items from regulatory contcol is considered on a case-by-case basis.

1. The licensee shall make a reasonable effort to eliminata reakuval oc~tamination.

• 2. Ati, wetivity on equipment or surfaces shall not be covered by paint, platu.g, or other covering material unless contamination levels, as etermined by a survey and documented, are below the limits specifiod ,

in Table 1 prior to the application of the covering. A reasonable effort must be made to minimise the contamination prior to use of any 4

covering.

3. The radioactivity on no interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these lea:ations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surf aces of premises, equipment, er scrap which are likely to be contaminated but are of such sise, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in escess of the limits.

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4. Upon request, the coemission may authoride a licensee to relinquish possession or control of premises, erguipment, or scrap having surf at.:es contaminated with materials in excess of the limits specified. This may incluce, but would not be listited to, special circumstances such as rasing of buildings, transfer of premises to another organisation continuing work with radioactive materials, or conversion of facilities to a long-term stcrage or standby status. Such requests musta

a. Provide detailed, specific information describing the premises, -

equipment or scrap, radioactive contaminants, and the nature, eatent, and degree of r6sidual surface contamination, b, provide a detailed health and safety analysis which redocts that the residual amounts of materials on surface areas, together with otht.' considerations such as prospective use of the-premises, equipment, or scrap, are unlikely to result it an unreasonable risk to the health and safety of the public.

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5. Prior to release of premises for unrestricted use, the licensee chall make a comprehsnaive radiation survey which establishes that A copy of contamination is within the limits specified in Table 1.

the survey report shall be filed with the Division of Fuel Cycle safety and safeguards, U. 3. Nuclear Regulatory casumission, Washington, DC 20555, and also the Administrator of the NRC Regional office having jurisdiction. The report should be filed at least 30 '

• days prior to the planned date of abandonment. The survey report shall .

a. Identify the premises.

b. Show that reasonable effort has been made to eliminate residual contamination.

c. Describe the scope of the survey and general procedures followed.

d. state the findings of the survey in units specified in the instruction.

Following review of the repor^. the NRC will consider visiting the facilities to confirm the sarvey.

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TAKE 1 ACCEPTABLE SURFACE CONTAMINATkON LEVELS _

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AVERAGE **' M AXIMUM* *' REMOVAKE**'

NUCUDES*

i U-nat, U-235, U-238, and 5,000 dom e/100 cm' 15,000 dpm e/100 cm' 1,000 dem e/100 cm'  ;

associated decay products Transuranics, Re-226, Ra-228, '

100 dom /100 cm' 300 dpm/100 cm' 20 dpm/f 00 cm' Th-230. Th-228, Ps-231, Ac-227, f-125,1-129 I

i Th-not, Th-232, !;<-90, 1000 dom /100cm' 3000 dor"J100 cm' 200 dpm/100 cm'

' Re 223, Ra-224, U-232, 6-126, 1131,1-133 Betap emitters Inuclides '

i with decay modes other then 8 1000 dpm h/100 cm' 5000 dpm h/100 cm' 15,000 dpm h/100 cm siphe emission or epontaneous fissioni except Sr-90 and

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i others noted above.

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• Where surface contamination by both alphe- and beta-ger une-emitting nucIldes exists, the limits estaldlehod for alphe- and bagemme-l  ;

emitting =.cadma should apply :. " ;: ; .di.

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• As used in this totdo, dpm idsintegrations per minutel means the rate of emission by radioactive meterial as determined by correcting the '

l counts per nenues observed by en ; ,, 2 detector for background, efficiency, and geomet.ic faceors associeeed wish the

( instrumentation.

'Moseurements of everage contaminent should not be averaged over enore than 1 square meter. For objects of less surface aree, the average should be desived for each such otgect. i l

% maximum w .Lr . level appeles to en area of not more then 100 cm'.

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'The amount of removable red' ' active meterial por 100 cm' of surface eres sho*sid be determined by wiping that ares with dry filter or '

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sof: at? sorbent paper, applymt qlerate pressure, and assessing the amount of radioactive msetorial on the wipe with an appropriate ,

. hen removable contamination on otgects of less surface area is determined, the portment levels should instrument of known efficienc) l be reduced proportionany and tne entire surface should be wiped.  !

t The svarsee and maximum radiation levels associated with surface contamination resulting from beta-gamme emitters should not exceed l 0.2 mred/hr at ' cm and 1.0 mrad /hr at I cm, respectively, measured through not more then 7 rr:igierams per square cenemotor of total l absorter. ,

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