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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q! (to.se) U.S. NUCLE AR QEGULATORY COMMISSPN

• I gl p g! MATERIALS LICENSE 4 N! 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 I

llk tonuclear material designated below; to use such material for the purpme(s) and at the place (s) designat 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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I q Westinghouse Electric Corporation 3, Ucense number SNM-1107 y 4l

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I'P,0, Box 355 Amendment 11 f 7

Pittsburgh, Pennsylvania 15230-0355 November 30,2005 l - >

4. Expiration date N

t ll S. Docket or 1151 )

O Reference No {p,

(; 6. Byproduct, source, and/or 7. Chemical and/or physical 8. Maxtmum amount that licensee ;Ir special nuclear material form may possess at any one time 'l ll under this license fI  ! IL d !b li  !>:

l 0.35 kg F A. U-235 A. Ar;y A.

lll yj B. U-235 B. Any, except metal, enriched B. 75,000 kgs (y

i! to not more 1 ll than 5.0 w/o )

1: C, U-233 C. Any C. 5 grams iiI D. Pu-238, D. Sealed sources D. 1.5 grams

[N l Pu 239 $

!L ill 9. A .nnorized place of use: The licensee's existing facilities at Columbia. South Carolina. k li i ll 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 alllisted conditions j

fl in each section. jly ij lli.  %

i I FOR THE NUCLEAR REGULATORY COMMISSION -

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ls.4 I N I Date: (EL u"'I } 9~, l1 W By Michael F. Weber M I

Division of Fuel Cycle Safety 1 I, and Safeguards l l

Washington, DC 20555 - y i i 1 I e 1 I I I I I I 9802250061 98G217 I I

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• + Licent Numter g

.iNM-1107 Amendment 11 g MATERI ALS LICENSE ' Docket or Reference Number g SUPPLEMENTARY SHEET 70-1151 g SAFETY CONDITIONS h 8

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

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December 17,1997; and January 9 and 12,1908. y S-2. The Criticality Safety Evaluat criticality safety bases sM)t ghoutheh plan lify ety Analysis (CSAs) will defins the be completed as described in 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 g I against the comrgtpents listed in Section 6.2.3 of the license a ion. These submittals will g 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 are commitmQta. The denpnetration will show the 19g'idysed by thecolumbia Fuel Fabrication j of the license application l g g g Facility (CF Tn developing criticality safety bases pt n unde,stooq that this demonstration g may che below for e over time. The system (

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inclu&@on'sistjoffauthmary fault trees ffer those systerprjor which of tdCSE or be a CSE will l

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

evaluated a ofA letter repElWillibe' generated anhent from the staff to g

y Westingho The', ' "the fos (pd {lt will hopided'acconj al'by the following schedule:

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• URRS Diss61ver 'sur6 mary'of CSEt%/DS%>f N 8 l

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I e Solvent EMraction Us' u rrimary of CSE1 TBD"W 8

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

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

incinerator System'- summary of CSE - 9/rg W 4 g Ash Recovery System ieummary off Sp9i96(

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

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

Shredder System - summary of CSE - 9/96 I

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

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

• ADU Conversion - summary of CEE - 4/96 g U g

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

• Powder Blending - summary of CSE - 1/96 y 8

• Miscellaneous:

Ventilation Systems (Geometry Controlled) -

y summary of CSE- 3/9P* U g

Ventilation Systems (Modeition Controlled)- I y summary of CSE-3/98" g Scrubber Systems - summary of CSE - 3/98**

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

g Laboratories - summary of CSA- 9/96 g g-

• IFBA- summary of CSA- 3/96 '

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SNM-1107 Amendment 11 Ig

% MATERI ALS LICENSE Met or Refennce Number l

g 5 I q SUPPLEMENTARY SHEET 70-1151 g I

R N SAFETY COND1110NS ig q

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• Storage Pad NCS is based on DOE reports K-1920 and K-1663 g Ig N

• Rods - summary of CSA - 3/96 4

o Storage - summary of CSE U97 g I

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

• UF Cylinder Washing - summary of CSE - 12/95 t

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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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l. " These systems are to be coupled with the bi t sk Management Program (RMP) to be done for tha EPA I S-3. The licensee shall maintain decute the b April 30,1990, and revisioq ed March 31, and msponse September 30,199f; measures irhep)ite Aarch 25, August 15, and Emcrgency Pl 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). _p g 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 I further provided thatj tpe total nu'mberl)f st fuelassern%e 'ored 'at-the liEQsee's site at any given i

time does not excehd 250. f3v i .,N t h P j %s , d -'?I t N, o j1 7 h n.z{&,y r- 7 lp N( " **

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U.s. NUCLEAR CECULAToRY Commission PAGE 4 'OF 8 PAGES l g FORM 374A Lkense Number g

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g J SNM-1107 Amendment 11 g l

I MATERIALS LICENSE twei er acecrence Numoer l l l SUPPLEMENTARY SHEET 70-1151 i i i I j l SAFEG' JAP.DS CONDITIONS g

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l SAFEGUARDS CONDITIONS L I I i I SECTION 1.0 - MATERIAL CONTROL AND ACCOUNTING I

1 I i

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

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

l 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 l Condition SG-1.1 shall pthe irfitiated uitil an a ,spjeguards plan has been approved N l

i l by the Nucioar RegulMory" Commission. 7A E i 1 'U r l III SG-1.3 In lieu of the reqdi monts contained in 10 CFR 74.13(a)(1) and h to me the Forms Jorms provided all N

i DOE /DC-742r" 742C, the licensee may use computer 5

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

! 4 included.

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I SG-1 A in lieu of the requirements  %\  ; G '. [' 2 contained in CFR 70.54 and? 4.15 to useN tfie

( E i i 4 the licensee'thay use computer generated forins pdised'all informstion' required ty the latest N j printed instructions for'complebr$ inejarticularifornds included

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I SG-1.5 Per AmendmerW gust 19963, Cc<runstmerit Au& nrm now &b3W Ul contained in licensee's Fundam N L I Nuclear Material Control s% e.y i l J (j j j e$ ydEp M N h 4

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NotwithstandirQ the requiri...dti'b FNMC thi[Pliin'id$ntified in Li6epse Condition SG-1.1, the N

F 1 SG-1.6 d I 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 - 4 I 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 1 - 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. I 8 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) E I are satisfied.' E I E I 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 L.. I November 30,1993, letter (identificatson # NRC-93 036) are satisfied.

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N MATERI Al,S 1,1 CENSE wei or neference Numdei g SUPPLEMENTARY SHEET 70-1151 SAFEGUARDS CONDITIONS g

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M SG-1.9 Notwithstanding the recuirement of Section ll.A.7, block U, of NUREGIBR-0006. which is lB incorporated via 10 CFR 74.15, to complete receivers measurements of scrap receipts (following B recovery processing) within 60 days of receint, the licensee shall not be subject to any time limit L 8

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. R N 5 N 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: E 5 lE E

5 (i) up to two defects when each item within a batch of items has an assigned value equal to or less than 50 grams U-235;

• U R reg, ems has an assigned value of R (ii) no more than one defeck N lass than 500 grams.U-235, but enone each or more itemitems within has a anbat b @E.ofpigned value in excess jE of 50 gra vW 'O N U-235; and E N E (iii) zero detect when any item within a batch of items contains 500 N more grams U-235. Il Nl #J

N; a x - E I SG-1.11 Notwithstandin'g'the first pa'regraph of Section 7.1 dof thii badidentifi$g'byjECondition S N licensee shaft conduct shipper-receiver comparisons on'all SNM materiais received (regardless E

M N 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. Q~miyrmMM

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1. f') .a , jE Nj SECT!ON 2.0 - PHYSICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE jE E

N SG-2.1 n . . _ . . 1) silt!%

The licensee shall fcilow the " Site Physical Security Plan - Westinghouse Electric Corporation,

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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 N E N

i SECTION 3.0 - INTERNATIONAL SAFEGUARDS ,' M N ., E 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. jE il 'E

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

$ ,e il j The reference design information is that dated by the licensee on October 14,1985. "Information jE il on the Faciiity" also includes other facility information submitted via Concise Notes in accordance jll N

with 10 CFR 75.11(c). ju N E N SG-3.1.2 With respen to Transitional Facility Attachment Code 2.2: f'u ikA jE Substantive changes to the information provided in the Columbia Plant Design Information jE 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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6 oF 5 PAGES g g . L6 cense Number y W SNM-1107 Amendment 11 g g MATERIALS LICENSE oocaci ar neverence Number g l SUPPLEMENTARY 3HEET 70-1151 g SAFEGUARDS CONDITIONS N E N N g 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. g N E g 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 N N $

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 y!

g modifiedgeccordsoce with 10 CFR 75.11(c) fpy J~ g g l% MX - -

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

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g provisWis of the Protocot" rneans:

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y Any change in the; existing facility and/or site layo;ut'or new additier(affectingl any activity g 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). !g

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

g and 14 (per the referenced attachments)'of the DR.1 dated October 14,1985, or as modified i g in accmdance with 10 CFR 75.11(c). ' ~T ,X A; 4; M (c) "Any changithAt makes the selected Kep Measuiement Points (KMPs) (as described in fl 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 Transitional Facility Attachment to the US/lAEA Safeguards Agreemer.t, or as modified in y 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) i g

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

y taking for the Agency's accounting purposes" means: (Jg 3 Ig g 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. g N W N W N N N W N d I N g E 4 L am m m m = = = = m m m = = = = = = = nrreir= = . . . . . . . . . . . . - - . . . = _. . J

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y SNM-1107 Arnendment 11 r l MATERIALS LICENSE DxLet a Reference Number l l SUPPLEMENTARY SHEET 70-1151 l I r g SAFEGUARDS CONDITIONS I I L I I l (e) " Introduction of a significantly less accurate analytical method for accounting purposes" g i means: y I i l 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. g (f) " Decrease in the frequency of calibrating measuring equipment if it significantly decreases I

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q the accuracy of the materials a un m" means: g i Any change that re hs tre estimates of the ptic error being affected by a factor of 1 two or more. g (g) %idual measurement error g 1

"Any change esi; mates s ittihe to obtain limitsstatistical of error for shipper procedures / receiverused(S/R) to combine i(d!!!erences andg material i

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1 g j outlinedjn A'.tachments 1, 37.2,'and37.3 37i.ification referen6ed of),the equatip in Paragraph ar,d/or calculat,g ions 37 of

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

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M g 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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l 6 I e g SG-3.1.6 With respect to Transitional Facility Attachment Code 5.1.1: y N R g For inventory changes, time of recording, "upon" means: No later than the next regular workday ,

p (Monday through Friday). g N N p 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. ,

i g SG-3.1.7 With respect to Transiti Attachment g. : E g

I gEhme," anticipated operational lg For Concise Notes de' scribing the anticipated operational g programme" %'knticipated physical inventory schedule. Q g N

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