ML20203C075

Amend 11 to License SNM-1107 for Westinghouse Electric Corp

ML20203C075
Person / Time
Site:	Westinghouse
Issue date:	02/17/1998
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203C071	List: ML20203C065 ML20203C075 ML20203C083
References
NUDOCS 9802250061
Download: ML20203C075 (8)

Text

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U.S. NUCLE AR QEGULATORY COMMISSPN E

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MATERIALS LICENSE 4

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b g! Pursuant to the Atomic Energy Act of 1954, as amended, the Energy ReorFanization Act of 1974 (Public Law 93-438), and Tale to, jp' g! Cede 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 dl made by the licensee, a license is hereby issued authorizing the licenwe io receise, acquire, pmse s, and transfer byproduct, source, and special

,1 ll nuclear material designated below; to use such material for the purpme(s) and at the place (s) designat I

k to perwns authorized to receise it in accordance with the regulatiors of the applicable Part(s). This license shall be deemed to contain the conditions f specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and o g Regulatory Commission now or hereafter in effect and to any conditions specified below.

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Ucensee q

I 3, Ucense number 4l I' q

Westinghouse Electric Corporation SNM-1107 y

Amendment 11 f

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P,0, Box 355 7

l Pittsburgh, Pennsylvania 15230-0355 November 30,2005

4. Expiration date N

t ll S. Docket or 1151

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O Reference No

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(; 6. Byproduct, source, and/or

7. Chemical and/or physical

8. Maxtmum amount that licensee

Ir ll special nuclear material form may possess at any one time

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under this license I

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i A. U-235 A.

Ar;y A.

0.35 kg F

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Any, except B.

75,000 kgs

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to not more 1

ll than 5.0 w/o

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C, U-233 C.

Any C.

5 grams iiI

[N D. Pu-238, D.

Sealed sources D.

1.5 grams Pu 239 l

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A.nnorized place of use: The licensee's existing facilities at Columbia. South Carolina.

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

j fl These sections are part of the license and the licensee is subject to compliance with alllisted conditions jly ij in each section.

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FOR THE NUCLEAR REGULATORY COMMISSION I

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Date: (EL u"'I } 9~, l1 W I

By Michael F. Weber M

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Division of Fuel Cycle Safety 1

I, and Safeguards l

Washington, DC 20555 -

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PAGES g

Licent Numter g

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.iNM-1107 Amendment 11 g

MATERI ALS LICENSE

' Docket or Reference Number g

SUPPLEMENTARY SHEET 70-1151 g

SAFETY CONDITIONS h

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SAFE 7 CONDITIONS h

S-1.

Authorized use: For use in accordance with statements, representatiora, and conditions in the j

license application dated April 30,1995, and supplements dated May 11 and 18, August 4 and g

25, and September 25,1995; November 8,1996; July 14 and 25, August 11, November 17, and y

y December 17,1997; and January 9 and 12,1908.

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h lify ety Analysis (CSAs) will defins the sM)t the plan S-2.

The Criticality Safety Evaluat ghou be completed as described in criticality safety bases y

y Sections 6.4.1 and 6 e license application for e p of the process. A submittal to g

y the NRC will be ma estinghouse which willinclude in ion which the staff will review I

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against the comrgtpents listed in Section 6.2.3 of the license a ion. These submittals will I

not be specific colhmitments, but are intended as a demonst he adequacy of the bases of safety itemilag in Sectior(6.2.3. The contents listed in Section j of the license application l are commitmQta. The denpnetration will show the 19g'idysed by thecolumbia Fuel Fabrication g

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Facility (CF Tn developing criticality safety bases pt n unde,stooq that this demonstration inclu&@on'sistjoffauthmary of tdCSE or CSA as annota l

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g may che over time. The fault trees ffer those systerprjor which a CSE will be I

below for e system (

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done). T uscy of the o'ommitmadia inbetiok6'.2.'3 of the license application will be I

ofA letter repElWillibe' generated anhent from the staff to

' "the fos (pd {lt will hopided'acconj evaluated a

g al'by the following schedule:

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Solvent EMraction Us' rrimary of CSE1 TBD"W e

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y @h URRS Scriip Processing: ' Low-Level Waste Processing Shl '9siimmary of CS N

Mop Water System Equipment - summary of CSA - 9 ')6V U

incinerator System'- summary of CSE - 9/rg W

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Ash Recovery System ieummary off Sp9i96(

g Liquid Honing System - summary o% SEW 9/96 g

y Ultrasonic Cleaning System - summary of CSE - 9/96 g

g Shredder System - summary of CSE - 9/96 I

g URRS Waste Treatment - summary of CSA - 11/95 I

g IDR Conversion - summary of CSE - Prior to Restart U

y ADU Conversion - summary of CEE - 4/96 g

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• - ADU Pelleting - summary of CSE - 6/96 g

Powder Blending - summary of CSE - 1/96 8

y Miscellaneous:

Ventilation Systems (Geometry Controlled) -

summary of CSE-3/9P*

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Ventilation Systems (Modeition Controlled)-

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summary of CSE-3/98" g

Scrubber Systems - summary of CSE - 3/98**

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g Hoods & Contamment - summary of CSA - 9/96 g

g Laboratories - summary of CSA-9/96 g

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PaGES g l

Lkenne Numhrt SNM-1107 Amendment 11 Ig l

5 MATERI ALS LICENSE Met or Refennce Number g

q SUPPLEMENTARY SHEET 70-1151 Ig IN R

SAFETY COND1110NS ig q

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I Storage Pad NCS is based on DOE reports K-1920 and K-1663 g

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Rods - summary of CSA - 3/96 g

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Storage - summary of CSE U97 g

I Final Assembly - summary of CSE - 6/97 g

UF Cylinder Washing - summary of CSE - 12/95 I

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• The CFFF has performed a CSA upgrade and does not han a specific date for schedule of this CSE at l

this time.

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" These systems are to be coupled with the bi t sk Management Program (RMP) to be done for tha EPA decute the msponse measures irhep)ite Emcrgency Pl I

S-3.

The licensee shall maintain ed March 31, and September 30,199f; Aarch 25, August 15, and b

April 30,1990, and revisioq I.

September 30,1994; Jariqary 9, February 17, August 17, and October 2Lh995; or as further revised by g

N the licensee consistop 10 C 70.32(i).

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S-4.

Notwithstanding the iremer $ k0 CFR 20.205(b) to rnonit terr l' surfaces of packaged a

1 radioactive material'Yoceipts for radi

, ive contamipation(tp)icensee is axempted from such 3

I tequirement relativtW flatbed trailer 25 ents of fusi assamtsies received fmm the Generul Electric 5

N Company for inten'niiterage purpo,ses

, prfvided the'cdpstraints, conditicInsland controls committed t

N to in the licensee'shetter, dated NoveMe '30,'1993,9tderitdiciation # NRC-93-036), are satisfied; and t

fuelassern%e 'ored 'at-the liEQsee's site at any given I

further provided that tpe total nu'mberl)f st i

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PAGES Lkense Number g

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SNM-1107 Amendment 11 g

I MATERIALS LICENSE twei er acecrence Numoer l

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SUPPLEMENTARY SHEET 70-1151 i

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I SAFEG' JAP.DS CONDITIONS j

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SAFEGUARDS CONDITIONS I

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I SECTION 1.0 - MATERIAL CONTROL AND ACCOUNTING I

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I SG-1.1 The licensee shall follow pages i through xvii and Chapters 1.0 through 9.0 of it:

• r uncemental I

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I Nuclear Material Control Plan for the Columbia Fuel Fabncation FaciiW," with siJ pages identified I

I as Revision 27 (dated May 23,1997). Any further revisions to this Plan shall be made only in E

I accordance with, a.id pursuant to, either 10 Cf ! 70.32(c) or 70.34.

E SG-1.2 Operations involving special r es i

t referenced in the Plan identified in I

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Condition SG-1.1 shall pthe irfitiated uitil an a

,spjeguards plan has been approved N

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by the Nucioar RegulMory" Commission.

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l In lieu of the reqdi monts contained in 10 CFR 74.13(a)(1) and h to me the Forms N

II SG-1.3 i

I DOE /DC-742r 742C, the licensee may use computer Jorms provided all 5

j information rei by the late *t printed instructions for completing,tte particular form is N

included.

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l in lieu of the requirements contained in CFR 70.54 and? 4.15 to use tfie N

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4 the licensee'thay use computer generated forins pdised'all informstion' required ty the latest N

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printed instructions for'complebr$ inejarticularifornds included g

Deleted Per AmendmerW 3, Au& nrm &b3W Ul ined in licensee's Fundam n

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SG-1.5 gust 1996 Cc<runstmerit now conta N

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NotwithstandirQ the requiri...dti'b thi[

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licensee may usel1) a single standard for measurement control (iiuluding daily control limit n

J monitoring and bias corrections) for any Enear-response tube or;rgd scales, in any initially -

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demonstrated to be linear over its.ange of Use within the discrimination of the scale by N

I calculating a bias at fourlevels across the range of use and' demonstrating that the four results 4

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- are not stadstically different, and (2) that the continued linearity of response of the scales is d

I venfied by rnonthly calibration against at,least four traceable standards covering the range of a

l use.

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E SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5.2.3 of the licensee's 4

Fundamente! Nuclear Material Control Plar), the licensee is exempted from physical ir.ventory I

requi.ements relative to the material identified in Condition S-4; provided the conditions and 1

commitments contained in the licensee's November 30,1093, letter (idenutication # NRC-93-036)

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are satisfied.'

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SG-1.8 Nct OF--Jrg the requirement of Section 6.2.1(a).5 of tne licensee's Fundamental Nuclear E

I Material Contiel Plan to unpackage and perform an item count upon receipi of special nuclear E

I matenal, the licensee is exempted from such requirement roladve to the matedal identified in E

I Condition S-4; provided the conditions and commitments contained in the licensee's E

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I November 30,1993, letter (identificatson # NRC-93 036) are satisfied.

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SNM-1107 Amendment 11 It N

MATERI Al,S 1,1 CENSE wei or neference Numdei g

SUPPLEMENTARY SHEET 70-1151 SAFEGUARDS CONDITIONS g

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SG-1.9 Notwithstanding the recuirement of Section ll.A.7, block U, of NUREGIBR-0006. which is incorporated via 10 CFR 74.15, to complete receivers measurements of scrap receipts (following B

8 recovery processing) within 60 days of receint, the licensee shall not be subject to any time limit L

relative to racovering and measuring received UF, heels when the block U action code (of 1

j DOE /NRC Form 741)is used to book such receipts.

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SG-1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, ' allowed number" E

N within the phrase ' allowed number of defects

• is hereby specified as oeing:

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(i) up to two defects when each item within a batch of items has an assigned value equal to or E

R reg, less than 50 grams U-235; (ii) no more than one defeck en each item within a bat @E.ofpigned value in excess of 50 gra U

ems has an assigned value of R

N lass than 500 grams.U-235, but one or more items has an b jE E

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Nl (iii) zero detect when any item within a batch of items contains 500 N more grams U-235.

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Notwithstandin'g'the first pa'regraph of Section 7.1 of thii badidentifi$g'by Condition S I

SG-1.11 E

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licensee shaft conduct shipper-receiver comparisons on'all SNM materiais received (regardless

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of whether booked on the basis of receivers or shippets values), except for those materials N

identified in Section 7.1 of NUREG-1065 (Re4 2) as being exempted from shipper-receiver lE N

contparison's.

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j Nj SECT!ON 2.0 - PHYSICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE jE 4

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N SG-2.1 The licensee shall fcilow the " Site Physical Security Plan - Westinghouse Electric Corporation, y

N Columbia, S.C.," dated March 1980; Revision 10.0 dated October 1,1987; the " Revision Record" E

ilj contained in the approved Physical Security Plan (current to October 1,1994); and as may be N

revised in accordance with the provisions of 10 CFR 70.32(e) K E

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SECTION 3.0 - INTERNATIONAL SAFEGUARDS M

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N SG-3.1 The licensee shall follow Codes 1 through.6 of Transitional Facility Attachment No. 5A dated li N

August 31,1988, to the US/lAEA Gafeguaros Apreement. Such Transitional Facility Attachment jE N

shall be interpreted in accordance with Conditions SG-3.1.1 through SG-3.1.7.

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'E SG-3.1.1 With respect to Transitiocu r:acility Attachment Code 2:

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,e il The reference design information is that dated by the licensee on October 14,1985. "Information jE j

il on the Faciiity" also includes other facility information submitted via Concise Notes in accordance jll N

with 10 CFR 75.11(c).

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SG-3.1.2 With respen to Transitional Facility Attachment Code 2.2:

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A Substantive changes to the information provided in the Columbia Plant Design Information j

N Questionnaire (DIQ) means those changes requiring amendment of the Transitional Facility jE N

Attachment. Such changes shall be provided by letter to the NRC Office of Nuclear Material jE Safety and Safeguards at least 70-days in advance of implementation.

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FORM 374A Le. NUCLEAM C.EcVLATcRY coMWssioN PAGE 6

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PAGES g L6 cense Number g

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SNM-1107 Amendment 11 g

g MATERIALS LICENSE oocaci ar neverence Number g

l SUPPLEMENTARY 3HEET 70-1151 g

SAFEGUARDS CONDITIONS N

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Non-substantive changes to the information in the DlQ means those changes not requiring g

g amendment of the Transitional Facility Attachment. Such changes shall be provided by Concise y

g Note (From DOE /NRC-740M) within 30 days of receiving notification from the NRC that the g

g facility has been identified under Article 39(b) of the US/lAEA Safeguards Agreement.

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The types of modifications with respect to which information is required under 10 CFR 75.11, (to y

y be submitted in advance), are those items stated in Code 2.2, specifically-y N

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g (a) "Any change in the purpose of o

means:

g Any deviation from tgdeschbed activities in I special nuclear material and any g

change to the madq)um' enrichment and/oi quantitiss ofjU-235 currently authorized by g

g License No. SNMji107, and/or as described in Paragrapl16'of the Design Information y

g QuestionnairA!(OlO) dated October 14,1985, or as modified fr) accordance with 10 CFR g

y 75.11(c).,lndluded also is any deviation from the described'special nuciaar material (SNM) y production activities' described in paragraph 6 of the DlO dated 6ctober 14,1985, or as y!

modifiedgeccordsoce with 10 CFR 75.11(c) fpy g

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(b) "Any changes in the layout,of the facHitf Mich affects safeguardbmplementation of the

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provisWis of the Protocot" rneans:

Any change in the; existing facility and/or site layo;ut'or new additier(affecting any activity p

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involving BNM as described in Paragrapt}s'10 and 11 (per the referenced attachments of lg g

the DlQ dated October'14,1985/N as rnodified in accordance wRh'10 CFR 75.11(c).

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g included _also is any modification to, or deviation from, ths data provided in Paragraphs 13 Ig g

and 14 (per the referenced attachments)'of the DR.1 dated October 14,1985, or as modified i fl g

in accmdance with 10 CFR 75.11(c). '

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(c) "Any changithAt makes the selected Kep Measuiement Points (KMPs) (as described in g

Code 3.1.2) inadeq9 ate for the Agency's accounting purpose" means:

g Any change to the KMP5 as described in Code %1.2 of the Westinghouse-Columbia y

Transitional Facility Attachment to the US/lAEA Safeguards Agreemer.t, or as modified in g

g accordance with 10 CFR 75.11(c), that results in any KMP alteration affecting r purpose y

y of KMPs as stipulated by 10 CFR 75.4(m) ig N

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(d) "Any change in the physical inventory procedures that would advercely affect tne inventon/

y taking for the Agency's accounting purposes" means:

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Any change to the description data contained in Paragraph 34 (per the referenced I,

g attachments) of the DlQ dated October 14,1985, or as modified !n accordance with 10 CFR g

g 75.11(c), that would not permit the Agency to conclude an SNM material balance for the g

y Westinghouse-Columbia facility.

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g Eense Number g

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y SNM-1107 Arnendment 11 r

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g SAFEGUARDS CONDITIONS I

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l (e) " Introduction of a significantly less accurate analytical method for accounting purposes" g

i means:

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Any recalculation of the " Relative Errors-Random and Sp.tematic" as listed in Attachment g

i 36.2 referenced in Mragraph 36 of the DlQ dated October 14,1986, or as modified in g

j accordance with 16 'cR 75.11(c), that resuits in the estimates of the random and g

systematic errors being affected by a factor of two or more.

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j (f) " Decrease in the frequency of calibrating measuring equipment if it significantly decreases g

q the accuracy of the materials a un m" means:

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Any change that re hs tre estimates of the ptic error being affected by a factor of 1

two or more.

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%idual measurement error "Any change ittihe statistical procedures used to combine i(d!!!erences and material 1

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esi; mates to obtain limits of error for shipper / receiver (S/R) g i

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Any depiato/

1 outlinedjn A'.tachments 37i.ification of),the equatip ar,d/or calculat, ions n from (or, mod g

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the DIO dated October 19,1985, or as modified irraccordance wijth 10 CFR g

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Management and Safeguards System upon receipt of the receiver's~ measurement resuits.

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The licensee shall use ttA material composition codes documented in the DlQ dated Octooer 14, g

j 1985, and as modified by Concise Notes ( Further, notwithstanding any other requirements for g

advance notificahon and/or reporting, the licensee may add or delete composition codes for p

nucioar material routinely prr cessed and on inventory at CFFF immediateiv upon telephone g

nobfication to the Office of Nuclear Material Safety und Sefeguards. Follow-up documentation, in T

the form of a Concise Note accompanied by appropriate changes to Table 1 of Attachment 34.8 to the DlQ shall be submitted within three regular workdays of the telephone notification.

SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1:

Measured discards should be reoorted as an SN (Shipment to non-safeguards facility) whf n shipped off-site to en authonzed burial ground. (The IAEA system will not process measu*ed discards as loss / disposal (LDs) when they are shipped off-site)

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W SAFEGUARDS CONDITIONS y

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g SG-3.1.6 With respect to Transitional Facility Attachment Code 5.1.1:

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For inventory changes, time of recording, "upon" means: No later than the next regular workday p

(Monday through Friday).

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For those occasions where natural or depleted uranium is inadvertently enriched above 0.711 g

y percent through commingling with msidual ennched uranium in process equipment, the resultant y

I product shall be considered as being produced through a blending operation and the material y

category change shall be recorded upon obtalning measurement confirmation that a materia l g

g category change has occurred.

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g SG-3.1.7 With respect to Transiti Attachment

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g programme" %'knticipated physical inventory schedule. Q g

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