ML20203C328

Amend 8 to License SNM-1107 for Westinghouse Electric Corp

ML20203C328
Person / Time
Site:	Westinghouse
Issue date:	12/09/1997
From:	Schwink W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203C320	List: ML20203C315 ML20203C328 ML20203C342
References
NUDOCS 9712150282
Download: ML20203C328 (8)

Text

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C FORM 374 U.S. NUCLEAR REGULATORY COMMISSION FPursuant to the Atomio Lncig M ATERI ALS 1.lCENSE i l'ederal Regulations, Chapter 1. Parts 30,31. 32,33,34,35,36,39,40, and 70. and in reliance on statements and representations heretofore made I g La g

gl by the licensee, a hcense is hereby inued authoririnF the hsensee to recene, acquire, pouen, and transfer by product, sourc material designated below; to use such matenal for the purpose (s) and at tLe place (s) desi F nated below; to dehver or transfer such matestal to Li Nlj k N; speciDed prsonsin authorited toAtomic Section lH3 of the rt(ene Energy it in Act accordance with of 1954, as amended, and the regulations is subject to all applicable ofrules, thereFulatiens, applicable Part(s).

and orders of the This license s

$j Nuclear Megulatory Commiuion now or hereaf ter in ef fect and to any conditiom specified below. f5

• Wl l.icensee k

9; si yh hWestinghouseElectricCorporation 3. License Nunkt SNM-1107 Amendment 8 (D

P.O. Box 355

$ll l1 Pittsburgh, Pennsylvania 15230 0355 I

ap;,,,;,n g,g. November 30, 2005 (d a

$. DocLet or 70-131 i

) Reference No. (l hl 6. liy product. Source, and/or 7. Chemical and/or Physical 8. Maximum Amount that 1.icensec 9l Special Nuclear Material Form May Powess at Any One Time Ql pl Under This License gl Q

• 1 i A. U-235 A. Any A. 0.35 kg 5

$ B. U-235 B. Any, except B. 75.000 kgs 5

• i metal, enriched 5

• i to not more &

• I than 5.0 w/o iSl sj C. U-233 C. Any C. 5 grams $l

${ 0. Pu-238. D. Sealed sources D. 1.5 grams 5 '

• i Pu-239 it

$ i!

k 9. Authorized place of use: The licensee's existing facilities at Columbia. South h s

Carolina. $et 9j 10. This license shall be deemed to contain two sections: Safety Conditions and E

% Safeguards Conditions. These sectionc are part of the license and the licensee is subject to compliance with all listed conditions in each section.

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%j FOR THE NUCLEAR REGULATORY COMMISSION 4

}EE jE e s Date: /2 [O'/[f 7 By: Walter S. Schwink d M d .

Division of Fuel Cycle Safety !4 and Safeguards l6 ,

Washington. DC 20555 Ej Wj E bl V

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,I W 97121302e2 971209 ApocK 07001151

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FORM 3744 U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 or 8 eacts y g

Lkeme Numter 'g l

I SNM-1107 N

1. . M ATERI ALS LICENSE coaci or Reference Numhet g 1

' SUPPLEMENTARY SHEET 70-1151 4 I 4 l Safety Conditions a 1 E I N I

p: SAFETY CONDITIONS I

l S-1 Authorized use: For use in accordance with statements, representations and conditions in the license application dated April 30. 1993, and supplements l

g a y dated May 11 and 18. August 4 and 25. September 25, 1995: July 14 and 25. g

August 11. and November 17, 1997. g N

l S-2. The Criticality Safety Evaluations.(CSEs) and Criticality Safet Anal sis

, (CSAs) will define the criticality a and will be completed as in'described Sections 6.4.1 {s'and fety bases 6.4.2 utilizedy throug o of the license U

4 application for each,ste of the process. A6 submittal to the NRC will be made E gi by Westinghouse.which wi 1 include information which the staff will review N N

i against the commitments listed in Section 6.2.3 of the license application. E h These submittals will not be specific commitments 'but are intended as a

$ demonstration of the adequacy of the bases of safety itemized in Sect"n E

% 6.2.3. The contents . listed in Section 6.4.2 of the license a)plicatioa are E

$ comitments. The demonstration will show the logic used by tie Columbia Fuel I

$ Fabrication Facility (CFFF) in developing the criticality safety bases. It isiE I understood.that this demonstration may change over time. The submittal will {N I consist of'a summary of the CSE or CSA as' annotated below;for each system lE (which shall include fault-trees for those systems for which a CSE will be i N

done). The adequacy of the commitments in.Section 6.2.3:of the license j#

application will be evaluated'and;a reply'in the form of a letter report will E i N be enerated and sent from.the staff to Westinghouse, mThe submittal by the W CFF will be provided according toithe following sched l~e: j ll e e

UN tankst-^ sumary of.CSE -10/95 URRS Dissolver - summary of CSE - 10/95 K'

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W N e Solvent Extraction - sumary of CSE - TBD* ',

N 4

e URRS Scrap Processing: ,

e low-level Waste Processing System - summary of CSA - 9/96 4 W Hop Water System Equipment e summary'of CSA - 9/96 4

%p Incinerator System - sumary of CSE - 9/96 4 I Ash Recovery System - sumary of CSE - 9/96 4 M Liquid Honing System - sumary of CSE - 9/96 a l Ultrasonic Cleaning System - summary of CSE - 9/95 u p Shredder System - sumary of CSE - 9/96 g i e URRS Waste Treatment - sumary of CSA - 11/95 g I e IDR Conversion - sumary of CSE - Prior to Restart A e 's ADV Conversion - sumary of CSE - 4/96 a e ADV Pelleting - sumary of CSE - 6/96 y e Powder Blending - sumary of CSE - 1/96 a e Miscellaneous- g Ventilation Systems (Geometry Controlled) - a sumary of CSE - 12/97** g ,

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l FORM 374A U.S. NUCLE A] REGULATORY COMMi&SION PAGE 3 ca 8 eAGts g lxense Nunder 'g l SNM-1107 q l .

MATERIALS LICENSE Luket or Reference Nurider g

. ' SUPPLEMENTARY SHEET 70-1151 g I N l Safety Conditions g I E I W Hj N l Ventilation Systems (Moderation Controlled) - l g, summary of CSE - 12/97** g g Scrubber Systems - sumary of CSE - 12/97** g g Hoods & Contatnment - sumary of CSA - 9/96 g

, Laboratories - summary of CSA - 9/96 g

, e IFBA - summary of CSA - 3/96 g

, e Storage Pad - NCS is based on DOE reports K-1920 and K-1663 y e Rods - summary of CSA - 3/96 l e e Storage - sumary Final Assembly - summaFP of CSE of CSEP4/f%

n ['6/97[/ / l N y e UF, Cylinder Wa91ng'- sumary of CSE - 12/,95 3 g

• The CFFF has performed ~a C A upgrade and does not have s ific date for schedule

• l of this CSE at this time in l - A ln Y **Thesesystemsare'tobecoupledwiththeColumbiaPlantRisk?ManagementProgram ~ " '

N N

(RMP) to be done for the EPA.b 'L N

'+'

I 1 o N W

NI S-3 Plan.

The dated licensee shall maintain andeiecute I April 30. 1990, and revisions dated,Harchthe 31. andresponse measures'(Septembe 30, 1992: 8 I March 25 August-15. and September-30' 1994: January 9. February 17 August 17, and ,

E October 23, 1995: 8 g

10 CFR 70.32(1);3orasfurtherrevisedbylthe:licenseeconsistentwith .

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y N S4 Notwithstanding $5A requirdments of'10hfR!E0.205(b) to monibf the external N li surfaces of packaged radioactive materlaPreceiptsifor radidactive contamination, E d the licensee is exempted f~ rom such requirement relative to; flatbed trailer shipments I ^

p' of fuel assemblies ' received from the General Electric Compariy for interim storage a I purposes only, provided'the constraints.' conditions and controls committed to in the N N licensee's letter, dated November 30,1993, (identification # NRC-93-036), are 4

1. satisfied; and further provided that the total number of such fuel assemblies stored u l at the licensee's site at any given time does not. exceed 250.

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'NRMtKNORwJuum = w w M.m.=Jutw w w_muutm.uumL l NRC FORM 3NA U.S. NUCLEAR REQUL1 fumy COMMISSON g F4GE 4 O? 8 PAGES .

g lxense Number .

p SNM-1107 p . b' ..IALS LICENSE Dx ket or Reference Number p -

d IMENTARY SHEET 70-1151 E I W g ,

Safeguards Conditions t 8

I' p SAFEGUAR9S CONDITIONS i I E t

fSECTION1.0--MATERIALCONTROLANDACCOUNTING g h SG-1,1 The licensee shall follow pages i through xvii and Chapters 1.0 through 9.0 of l j its "Fundamantal Nuclear Material Control Plan for the Columbia Fuel y g Fabrication Facility." with all pages identified as Revision 27 (dated g g K'y 23,1997) . Any further revisions to this Plan shall be made only in y g

accordsr.ce with, and pursuant to, either 10 CFR 70.32(c) or 70.34. g k h SG-1.2 Operat os invohing Plan idencifiad special in Condit.ibri {iDel@1 shall ont,be initiated until anrfisqterjal SG-1.

l w (f t apprepriate safeguards-plan has been approved by)the Nuclear Regulatory E Comission, y

.~ Y A, r l SG-1.3 In lieu of the7 requirements contained in 10 CFR 74.% a)(1) and (a)(2) to use f the Forms 00E/NRC-742 and 742C. the licensee may use computer generated forms E W provided all .information required by the latest printed: instructions for E completing the particular' form is included. >

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' SG-1.4 In lieu of-the requirements contained in CFR 70.54 and 74l.15 to use the z

E DOE /NRC Form-741. the licensee may use compute'r generatsd) forms provided all 5 information required by the latest printedsinstructions for completing the E particular form is nincluded; .

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E SG-1.5 Deleted Per Amendment 3.' August'1996! Commitment now cont 41ned ir licensee's E E

Fundamental y Nuclear  ; ~ Material yContro,llPlan.

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,,% y SG-1.6 Notwithstanding the requircments' of- the FNMG Plan identified in License W Condition SG-L1, the licensee may .use (1)la sing ~le! standard for measurement E control (includir.g. daily control' limit monitoring and bias corrections) for g any linear-response) tube or rod scales. In anyainitially demonstrated to be ~g i

linear over its range oftuse within the discrimination of the scale by a calculating a bias at four ' levels across-the range of use and demonstrating g that the four results are not statistically cifferent, and (2) that the g continued linearity of response of the scales is verified by monthly N l calibrP ion against at least four traceable standards cove-ing the range of g

> use, y E

SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5.2.3 of the y licensee's Fundamental Nuclear Meterial Control Plan, the licensee is exempted y from physical inventory requirements relative to the material identified in y Condition S-4; proaded the conditions and commitments contained in the g licensee's November 30. 1993. letter (identification # NRC-93-036) are E satisfied. g 4

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NR FORM 374A U.o. NUCLEA9 REGULATORY COMMISSION Pt.GE 5 or 8 picts 'g L6ceme Nun.ber g SNM-1107 g MATERIALS LICENSE pockei cr nereience Number g

' SUPPLEMENTARY SHEET 70-1151 g a

Safeguards Conditions 4 a

ig SG-1.8 Notwithstanding the requirement of Section 6.2.1(a).5 of the licensee's Fundamental Nuclear Material Control Plan to unpackage and perform an item count upon receipt of special nuclear material, tha licensee is exempted from g such recuirement relative to the material identified in Condition S-4: y' providec the conditions and commitments contained in the licensee's g November 30. 1993. letter (identification # NRC-93-036) are satisfied, y SG-1.9 Notwithstanding the requirement of L'ction II.A 7. block U. of NUREG/BR-0006. g which is incorporated via 10 CFR 74.15. to complete receiver's measurements of g scrap receipts (following recovery prccessing) within 60 days of receipt, the ,

licensee shall not be subject to ao time limit ielative to recovering and 8 measuring received6 UF heels (dienKkblock, U action code (of COE/NRC Form I 741)isusedtobooksugrecbipts. e gy V ()L n E E

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

" allowed number l"Within the phrase " allowed number of, defects" is hereby U, #

specified as being: s+ g (1) up to tA5)defdcts when each item within a batch of items has an assigned 8

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l value equal 4to or less than 50 grams U-235:i

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(ii) no more than one defect when each item!within a batch of items has an J

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assigned value of less than 500 grams U2235l but one ortmore items has an lE sssigned (value in' excess of;50 grams'U-235:'and  ; 'E

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' , , ,  ::k E (iii) zero' defectMien any<iitiem withinta batch of items.contains 500 or more E grams U-235u '% 1- i E jg[f;!(M.

1 LA M f Notwithstanding theOfirst paragraphiof Secti'on 7.1 offthe Plan identified by 27 E

g i SG-1.11 Condition SGs1cl. the licensee shall conduct shippertrecei ser comparisons on g i all SNM materials received (recardless of'whether booked on the basis of 4 1 receiver's or shipaer's values).Lexcept fo/ those^ materials identified in g i Section7.1ofNUR(G-1065(Rev.2)asbeingexemptedfromshipper-receiver a 1 compacisons, g u q

i S w_uA$ g i SECTION 2.0 -- PHYd.CA_L_$0TECT10N OF SNM 0FILOW STRATEGIC SIGNIFICANCE g E

]SG-2.1 The licensee shall follow the " Site Physical Security Plan - Westinghouse g l Electric Corporation. Columbia. S.C.." dated March 1980: Revision 10.0 dated g October 1. 1987: the " Revision Record" contained in the approved Physical

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a g Security Plan (current to October 1. 1994); and as may be revised in a accordance with the provisions of 10 CFR 70.32(e). g N

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FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 6 OF 0 l' AGES g Laense Mumber g SNM-1107 g M ATERIALS LICENSE Ikdet or Reference Numter g

, SUPPLEMENTARY SHEET 70-1151 g N

SafeguurA Conditions , u N

SECTION 3.0 -- INTERNATIONAL SAFEGUARDS g N

SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility g Attachment No. 5A dated August 31. 1988, to the US/IAEA Safeguards Agreement. g Sech Transitional Facility Attachment shall be interpreted in accordance with a Co.1ditions SG-3.1.1 through SG-3.1.7. g N

SG-3.1.1 With respect to Transitional Facility Attachment Code 2: g E

The reference design information is that dated by the licensee on October 14. g 1985. "Information on ,theTacility taMo includes other facility informatun g submittedviaConcjseNotesfinaccordance,with10CFR75.11(c). g i 7 V y SG-3.1.2 With respect toJransitional Facility Attachment' Code 2.2: g SubstantivechIngestotheinformation3rovidedin#he_Colum t y

Transitional Facility Attachment. Such changes <shall be provided by letter tol the NRC Office of Nuclear Material Safety and Safeguards at least 70-days in igg advance of implementation. i, j Non-substantivechangeszt'o'theinformatiohnItheDIQmealisthosechangesnot E requiring' amendment of the Transitio'al Facility Attachment. Such changes jE E

shall be provided by Concise Note 4(From 00E/NPC-740M) within 30 days of 8

receiving notification from the NRC that the racility has been identified under Article 39(b)'of the US/IAEA; Safeguards Agreement; d

.fer7 g 7 l ~

The types of modificationnith 'respeito which information is required under #

10 CFR 75.11((to be submitted in advanceM are those, items stated in Code #

2.2. specifically; , M J' E (a) "Any change libthe purpose of type of facifity" means:

. _ m a Any deviation from the described +activitics involving special nuclear material

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. and any change to the maximum enrichment and/or quantities of U-235 currently 4 authorized by License No. SNM-1107. and/or as described in Paragraph 5 of the 4 Design Information Questionnaire (010) dated October 14. 1985, or as modified 2 in accordance with 10 CFR 75.11(c). Included also is any deviation from t% E described special nuclear material (SNM) production activities described ;n 4 paragraph-6 of the blQ dated October 14, 1985, or as modified in accordance E with 10 CFR 75.11(c). N 4

(b) "Any changes in the layout of the facility which affects safeguards a implementation of the provisions of the Protocol" means: W ,

N Any change in the existing facility and/or site layout or new addition E affecting any activity involving SNM as described in Paragraphs 10 and 11 E E

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g NMC FORM 374A U.S. NUCLEAR REEAJLAT0QY COMMISSION PQGE OF 8 g 7 PAGES !g Licenw Number I g g 3- SNM-1107 'g g . MATERI ALS LICENSE Da Let or Refererwe Number l

' SUPPLEMENTARY SHEET 70-1151 g lI N E p

r Safeguards Conditions gl I E N E I E p (per the referenced attachment. of the D10 dated October 14. 1985, or as y g "iodified in accordance with 10 CFR 75.11(c). Included also is any y p modification to, or deviation from, the data provided in Paragraphs 13 and y 1 g 14 (per the referenced attachments) of the 010 dated October 14. 1985, or g y as modified in accordance with 10 CFR 75.11(c). g i E y (c) "Any change that makes the selected Key Measurement Points (KMPs) (as p, 4 described in Code 3.1.2) inadequate for the Agency's accounting purpose" g means: I g n, r gl rx n n e O. .

Any change to the KMPs'as' described in'C' ode 3.1.2 of the Westinghouse-

[ g g Columbia Transitional Facility Attachment to the US/IAEA Safeguards '

Agreement, or as modified in accordance with 10 CFR 75.11(c). that results g ,

g in any KMP alteration affecting the purpose of KMPs as stipulated by

, 10 CFR 75'.4(m) l (d) "Any change in the physical inventory procedures that would adversely l aifect the inventory taking for the Agency's accounting purposes" means: h y g N Any change to the description data contained in Paragraph 34 (per the d N{i E

referenced attachments) of the DIO dated October 14.-1985, or as modified f in accordance with 10 CFR 75.11(c). that would not permit the Agency to jE l

conclude an SNM material balance,for the Wastinghouse-Columbia facility. IE A (e) " Introduction ofcasignificantly[lessaccurateanalyticalmethodfor lE acccunt}ngpurposes"means: i

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N Any recalc01ation of the " Relative Errors-Random.and Systematic" as listed

$ in Attachment 36.2 referenced in Paragraph 36 nf the DIO dated October 14 5 1985. or as modified in accordance with 10 CFR;75.11(c). that results in N the estimates'of the random and systematic errors being affected by a N factor of two or more. . E R ,

. _ ; .. A g R (f) " Decrease in the frequency of calibrating measuring equipment if it E R significan'ly decreases the accuracy of the materials accounting system" E R means: ;E N Ej N Any channe that results in the estimates of the systematic error being E R affected by a factor of two or more. E 4 E (g) Any change in the statistical procedures used to combine individual I R W R measurement error estimates to obtain limits of error for shipper / receiver E (S/R) differences and material unaccounted for (MUF)" means:

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. MATERIALS L1 CENSE DocLet or Reference Numhet g

• SUPPLEMENTARY SHEET 70-1151 4 4

Safeguards Conditions g u

Any deviation from (or modification of) the equations and/or calculations outlined in Attachments 37.1, 37.2. and 37.3 referenced in Paragraph 37 of i

a the D1Q dated October 14, 1985, or as modified in accordance with 10 CFR q 75.11(c). g a

SG 3.1.3 With respect to Transitional Facility Attachment Code 3.1.2: a E

K.MP* -- This is a KMP in which all shipper receiver differences (SRDs) must be y recorded and reported even if numerically zero. SRDs are computed and g reported by the Nuclear Materials Management and Safeguards System upon g ,

receipt of the receiver's measure;nent results. g e /\ M H i; Q f , g SG-3.1.4 With respect to Transitional Facility Attachment Code 4: g

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The licensee shall use the material composition codes documented in the DIQ g dated October 147 1985, and as modified by Concise Notes. Further. y notwithstanding any other requirements for advance notification and/or g reporting, the licensee may add or delete ccmosicion: codes for nuclear y material routinely processed and on inventory ai CFFF immediately upon g telephone. notification.to' the Office of Nuclear-Material Safety and g Safeguards. Follow-up documentation, in the' form of a Concise Note y accompanied by appropriate changes to Table 1:of Attachment 34.8 to the DIQ g shall be submitted within three regular workdays of the telephone i y

noti fication, g g

SG-3.1.5 l WithrespecttoTAqsitionalFacilit Attachment Code 4.1:

8 Measureddiscardsshb61dbereporUdd'aseanSNJ(Shipmentdonon-safeguards

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N 1 d facility) when shipped off-site to'an euthorized burial ground. (The IAEA W N, system will not process measured discards as' loss / disposal (LDs) when they are 8 N shipped off-site). < , ,

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'E N E N SG-3.1.6 WithrespecttoTrSsitionalFacilityAttachmept' Code 5.1.1: E N .

E N For inventory changes, ' time;of recordinC"upon" means: No later than the E R next regular workday (Monday'through' Friday) W R E N For those occasions where natural or depleted uranium is inadvertently 8 N enriched above 0.711 percent through commingling with residual enriched W R uranium in process equipment, the resultant product shall be considered as E N being produced through a blending operation and the material category change d N shall be recorded upon obtaining measurement confirmatiore that a material N N category change has occurred. N N 5 B SG-3.1.7 With respect to Transitional Facility Attach ant Code 6.2.2: a d

For Concise Notes describing the anticipated operational programme. 4

" anticipated operational programme" means: Anticipated physical inventory E schedule. N E

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