ML20216C560

Amend 1 to License SNM-960 for Ge,Revising License Condition S-1

ML20216C560
Person / Time
Site:	07000754
Issue date:	02/12/1998
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20216C567	List: ML20216C560 ML20216C612 ML20217Q036
References
NUDOCS 9803160079
Download: ML20216C560 (7)

Text

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MATERIALS LICENSE j Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10 g Ccde of Federal Regulations, Chapter I, Parts 30, 31,32,33, 34. 35,39,40 and 70, and in reliance on statements and representations heretofore ;p made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and nuclear material designated below; to use such material for the purpoqs) and at the place (s) designated below; to deliver or transfer such material ;N to persons authorized to receive it in accordance with the regulations of the appicable Part(s). This license shall be deemed to contain the con 3

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 i; I l

Regulatory Commission now or hereafter in effect and to any conditions specified below. g I , I Ucensee l

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jp I 6. Byproduct, source,and/or ,',. 7. Chemical and/or physical 8. Maximum amount that licensee ji I special nuclear material form - may possess at any one time lI )

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ilp I A. U-235 enriched to less ~A. The matenal may be in A. 50 lulograms than or equal to the form ofirradiated ;4 I

l 10 percent for special nuclear matenal with its attendant j

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i byproduct and reactor-I produced transuranics lg t ,'

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I B. U-235 ennched to more B. The material may be in - B. 4 lulograms :8, l than 10 percent the form ofirradiated j l l for authonzed special nuclear material jg 1

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8 I produced transuranics C. U-235 C. In any unirradated C. Less than 1 I l form effective lulogram !gg i

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j form in addition to the irradiated quantities Plutonium i)l y

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!i I E. U-233 E. In any form E. 100 grams of U-233 i

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! 9. Authorized Place of Use: The licensee's facihbes in the Vallocatos Nuclear Center located in Pleasanton, Cahforms, as described in Appendix A of their December 1,1992, apphcation I  !

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' SUPPLEMENTARY SHEET 70-754 g I N I_ N I N I N I N I N I 10. This licensee shall be deemed to contain three sections: Safety Condebons, Safeguards g I Conditions, and Transporation Conditions. All these sechons are part of the license and the g i licensee is subject to compliance with all listed conditions in each section g I q I N I N I N l l gRREG 9L l

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SAFETY CONDITIONS I-I L

S-1. Authonzed Use: For activities in accordance with statements, representshons and condsbons specified in I

Apperdx A of the heensee's appucahon dated December 1,1992 (letter dated December 9,1992), I with supplements dated December 3,1993 (letter dated December 8,1993), and June 4,1997. I I-S 2. On or before January 28,1994, the licensee g,for NRC review a safety analysis for facihty t

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S-3. Sealed Plutonium sources

" License Cordtion for Leak to the leak teshng

@ Sealed Plutonium Sources," phril1993.

s specsfied in the attached l-I S-4. Release of equipment or r edals for unrestricted use shall be in with the attached I

"Guidehnes for D=-:+?IpTof lities and Equipment Prior tg Unrestricted Use or Terminabon ofp uct, Source, or 54+{ld:: Madnal," April 1993. l l-S 5. The licensee shall mission th s iri ' Ae general Mmission I

plan as sutxmtted t%er dated F /7,192$ assure that I

such is pq 14,1979,

[e's letter of and is hereby;6ceg'd as D l

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effluent monitoring and I S-6. The licenses shall to copiesM f t i< ior d fuiport summa'rizi I

erwironmental progmainat itWYa $ < bi l Cente6'This shall be sent to the I

Chief, Licensing Bra cWest CM s, .S. Nuclear Regulatory Commission, Washingt @DC 20655,RCReg ff6 and. the ion N{ W Reg at the address specified in I Appendix D of 10 CFR P t) . ([j,y.G g  % f I

S-7. Exemptions to the requireme 'bf 10 CFR 70.24,'"Cnbcahty Accident uirements," are hereby granted I

pursuant to 10 CFR 70.24(d). Tl9ie ex s are granted in accost}nce with Sechon 5.9, " Monitor Alarm System," of Appendix A of the n foi :g ,l I

1. The following armes 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 I-fully packaged as for transport in containers meebng all of the general license requirements I of 10 CFR 71 or in containers owned by the General Electnc Company and certified for l'

transport under the provisions of 10 CFR 71 in accordance with the cordbons of a I-certificate of compliance authonzing dehvery of such containers to a camer for Fissile Class I I transport, ,

b. Busiding 102 stora0e pool, f L

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c. For each area in which is stored one (1) shipment of packages containing speaal nuclear l material licensed pursuant to 10 CFR 71 for transport outside the confines of the Vallecitos I i N Nuclear Center insofar as the requwements of Section 70.24 pertain to the material contained in such shipments, i

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d. For each area where there is not more than one " safe batch" (as defined in Section 3.11 of l Appendoc A of the apphcahon) of finished reactor fuel rods or assembbes, under condebons N

i N whsch protect against reamangement Nbeanng porbons into more re I

cc"'*="*"*- 9@ GO For each area whictfmeetIthe requirement of a "su area" as defined in Section l

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, 2. Excephon to the maximum preset alarm point of 20 millirems per hour specified in 10 CFR 70.24 is N

granted for areas desonbod in Sechon 5.9.3 of Appendix A of the apphdeben provided that the i

i maximum preset alarin point does not exceed 500 millirems par, hour.

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S-8 Pursuant to 10 CFR 20.'106(b), the licensee is hereby authuizedM release radiE:tive materials in N l accordance with Secuod 8.9, "Arbome Effluent Control," of Appendix A of the apphcahon. N i * ::..- V l S-9 The licensee shall eb, maintain, and follow written proc duris for carryird'out licensed activities. I The procedures shall be approved and updated every two years.~ 4 I

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1. LC for Leak Testing Sealed Plutonium Sources did 4/93 I 2. Guulehnes for Decontamination of Facilities and Equipment.. 4/93 I i N 1 a 1 N i E 4 W E

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NM FORM 374A U.S. NUCLEAR REEULATORY COMMISSION License Number PAGE 5 or 6 PAGES g

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, SG-1.0 PHYSICAL PROTECTION REQUIRN8:NTS U

SG-1.1 The heensee shau not possess or use at the Vallocatos Nuclear Center specal nuclear material in l quantebes speer6ed in 10 CFR 73.1(b)(1) until ,

plan as desenbod in 10 CFR 70.22(h) of 10 N

CFR Part 70 has been submitted, f Regulatory Comrmssion I

SG-2.0 FACILITY OPERATION (, i N

I SG-2.1 Notwithstanding those pestions within 10 CFR Parts 70 and 74 whi establish requirements for N

licensees authorized t'o possess unirradiated specsal nuclear materlaf (8%) in quantebes exceedmg l one effective kilogram, the licensee may follow the applicable requwem6 pts of 10 CFR Parts 70 and I

I I 74 as though only,authonzed to possess less than one effectrve kilogram alSNM, provi&xt that the

, E licensee does not possess at any one time unirradiated SNM16 quantity equal to or greater than one g ~

effective kilogram.' O I s '

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SG-2.2 A Fundamental Nuclear Material Control Plan which addrinsees the materialeontrol and accounting I N requirements of 10 CFR Sechons 70.51,70.57,'and 70.58l or Sechon 74.31Fer Sectons 74.51, I 74.53,74.55,75.57, and 74.59, as appropriate, shall be' submitted to and approved by the Nuclear l Regulatory Commission prior to increasing the actual holdmgs of unitradiated SNM under License N

SNM-960 beyond one effective kilogram. -k l

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l E g TRANSPORTATION CONDITIONS g I E I E I E I E I TRANSPORTATION CONDITIONS E I E I E I N I T-1.0 TRANSPORTATION SECURITY W I E I T-1.1 The l6censee shaR not import, export, transport in a single shipment, or take delivery of a single g I sluprnent free on board at the point . is ($i p an agent or camer, quantities of special g

I nuclear material as speedied in 10CF 7:F.it plan as described in 10 CFR g I 70.22(g) of 10 CFR Part 70 besM submitted, and . . ' Nuclear Regulatory g I

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LfcENSE 00NDITION FOR "w TESTING SEALED URANIUM 30mtCES APRIL 1993 .

A. Each uranium source shall be tested for leakage at intervals not to exceed 6 months. In the absence of a certificate from a transferor 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 presence of 0.005

• sierocurie of alpha contamination on the test sample. The test sample shall be taken from the souroe'er from appropriate accessible surfaces of the device in which the sealed source is pc;manently or semipermanently mounted or stored. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Cossaission.

C. If thfr test reveals the presence of 0.005 microcurie or more of 1 removable alpha contamination, the licensee shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired by a person appropriately licensed to make such repairs or to be disposed of in accordance with the Commission's regulations.

Within 5 days after determining that any source has leaked, the licensee shall file a report with the Division of Fuel cycle safety and safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555, describing the source, test results, extent of contamination, apparent or suspected cause of source failure, and the corrective action taken. A copy of the report shall be sent to the Administrator of the nearest NRC Regional Office listed in Appendix D of Title 10, code of Federal Regulations, Part 20.

D. The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within 6 months prior to the date of use or transfer.

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OUIDELINES FOR DECONTAMINATION OF FACILITIES AND BQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMIIULTION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MkTERIAL i . .,

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

The instructions in this guide, in conjunction with Table 1, specify the radionuclides and radiation exposure rate limits which should De used in decontamination and survey of surfaces or promises and equipment prior to abandonment or release for unrestricted use. The limits in Table 1 do not '

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 facilities or items from regulatory control is considered on a case-by-case basis.

1. The licensee shall make a reasonable effort to eliminate residual contamination.

2. Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified 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 covering.

3. The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making seasurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such sise, construction, or location as to make the surfaer inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.

4. Upon request, the commission may authoride a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified. This may include, but would not be limited 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 storage or standby status. such requests musta

a. Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.

b. Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together wit'.a other considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.

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~3-l S. Prior to release of premises for unrestricted use, the licensee shall make a comprehensive 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. S. Nuclear Regulatory Commission, Washington, DC 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report should be filed at least 30 l

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

a. Identify the premises.

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

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

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l d. State the findings of the ev' rey in units specified in the instruction.

Following review of the report, the NRC will consider visiting the facilities to confirm the survey.

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