ML20203C328

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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:
References
NUDOCS 9712150282
Download: ML20203C328 (8)
v • d • e


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FPursuant to the Atomio Lncig C FORM 374 U.S. NUCLEAR REGULATORY COMMISSION M ATERI ALS 1.lCENSE g

La 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 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 nated below; to dehver or transfer such matestal to Li Nlj F

k N; prsons authorited to rt(ene it in accordance with the regulations of the applicable Part(s). This license s speciDed in Section lH3 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, reFulatiens, and orders of the

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

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l.icensee hWestinghouseElectricCorporation SNM-1107

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3. License Nunkt Amendment 8 D

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P.O. Box 355 l1 Pittsburgh, Pennsylvania 15230 0355 November 30, 2005 ap;,,,;,n g,g.

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Reference No.

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6. liy product. Source, and/or
7. Chemical and/or Physical
8. Maximum Amount that 1.icensec 9l l

Special Nuclear Material Form May Powess at Any One Time Ql pl Under This License gl Q

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

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0. Pu-238.

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Sealed sources D.

1.5 grams 5

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

Carolina.

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9j 10.

This license shall be deemed to contain two sections:

Safety Conditions and 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

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Date:

Division of Fuel Cycle Safety

!4 and Safeguards l6,

Washington. DC 20555 Ej Wj E

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FORM 3744 U.S. NUCLEAR REGULATORY COMMISSION PAGE 2

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I SNM-1107 N

M ATERI ALS LICENSE coaci or Reference Numhet g

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' SUPPLEMENTARY SHEET 70-1151 4

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Safety Conditions a

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I SAFETY CONDITIONS p :

I S-1 Authorized use:

For use in accordance with statements, representations and l

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conditions in the license application dated April 30. 1993, and supplements 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.

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

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

U4 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

Ni against the commitments listed in Section 6.2.3 of the license application.

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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

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consist of'a summary of the CSE or CSA as' annotated below;for each system lE N

(which shall include fault-trees for those systems for which a CSE will be i

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:

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UN tankst-^ sumary of.CSE -10/95 m'

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e URRS Dissolver - summary of CSE - 10/95 K'

Solvent Extraction - sumary of CSE - TBD* ',

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URRS Scrap Processing:

4 low-level Waste Processing System - summary of CSA - 9/96 4

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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

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URRS Waste Treatment - sumary of CSA - 11/95 g

IDR Conversion - sumary of CSE - Prior to Restart A

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'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**

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l FORM 374A U.S. NUCLE A] REGULATORY COMMi&SION PAGE 3

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eAGts lxense Nunder

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l SNM-1107 q

l MATERIALS LICENSE Luket or Reference Nurider g

' SUPPLEMENTARY SHEET 70-1151 g

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l Safety Conditions g

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Ventilation Systems (Moderation Controlled) -

l summary of CSE - 12/97**

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g Scrubber Systems - sumary of CSE - 12/97**

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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 Storage - sumary of CSE P4/f% ['6/97[/ /

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Final Assembly - summaFP of CSE -

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N UF, Cylinder Wa91ng'- sumary of CSE - 12/,95 e

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  • 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

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    • Thesesystemsare'tobecoupledwiththeColumbiaPlantRisk?ManagementProgram N

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

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NI S-3 The licensee shall maintain andeiecute the response measures'(Septembe W

I Plan. dated April 30. 1990, and revisions dated,Harch 31. and 30, 1992:

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March 25 August-15. and September-30' 1994: January 9. February 17 August 17, and E

8 3orasfurtherrevisedbylthe:licenseeconsistentwith October 23, 1995:

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10 CFR 70.32(1);

Notwithstanding $5A requirdments of'10hfR!E0.205(b) to monibf the external

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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

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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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lxense Number g

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..IALS LICENSE Dx ket or Reference Number d IMENTARY SHEET 70-1151 E

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Safeguards Conditions t

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SAFEGUAR9S CONDITIONS i

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E fSECTION1.0--MATERIALCONTROLANDACCOUNTING g

t SG-1,1 The licensee shall follow pages i through xvii and Chapters 1.0 through 9.0 of l h

j its "Fundamantal Nuclear Material Control Plan for the Columbia Fuel y

Fabrication Facility." with all pages identified as Revision 27 (dated g

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K'y 23,1997). Any further revisions to this Plan shall be made only in y

accordsr.ce with, and pursuant to, either 10 CFR 70.32(c) or 70.34.

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SG-1.2 Operat os invohing special {iDel@1 shall ont,be initiated until anrfisqterjal w l

(f Plan idencifiad in Condit.ibri SG-1.

E apprepriate safeguards-plan has been approved by)the Nuclear Regulatory t

Comission, y

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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

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completing the particular' form is included. >

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

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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

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particular form is included; m-

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

E Fundamental Nuclear ~ Material Contro,llPlan.

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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 linear over its range oftuse within the discrimination of the scale by a

i 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.

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NR FORM 374A U.o. NUCLEA9 REGULATORY COMMISSION Pt.GE 5

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'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 Notwithstanding the requirement of Section 6.2.1(a).5 of the licensee's i

SG-1.8 Fundamental Nuclear Material Control Plan to unpackage and perform an item g

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 received UF heels (dienKkblock, U action code (of COE/NRC Form 6

I 741)isusedtobooksugrecbipts.

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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 specified as being:

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

J 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

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(iii) zero' defectMien any<iitiem withinta batch of items.contains 500 or more E

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SG-1.11 Notwithstanding theOfirst paragraphiof Secti'on 7.1 offthe Plan identified by E

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

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compacisons, g

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SECTION 2.0 -- PHYd.CA_L_$0TECT10N OF SNM 0FILOW STRATEGIC SIGNIFICANCE g

]SG-2.1 E

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

a October 1. 1987: the " Revision Record" contained in the approved Physical

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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).

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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).

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7 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, Non-substantivechangeszt'o'theinformatiohnItheDIQmealisthosechangesnot E

j 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 d

under Article 39(b)'of the US/IAEA; Safeguards Agreement; g

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

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10 CFR 75.11((to be submitted in advanceM are those, items stated in Code 2.2. specifically; M

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(a) "Any change libthe purpose of type of facifity" means:

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Any deviation from the described +activitics involving special nuclear material E.

and any change to the maximum enrichment and/or quantities of U-235 currently 4

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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).

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(b) "Any changes in the layout of the facility which affects safeguards a

implementation of the provisions of the Protocol" means:

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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

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PAGES !g g

I Licenw Number g

g 3-SNM-1107

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MATERI ALS LICENSE Da Let or Refererwe Number l

' SUPPLEMENTARY SHEET 70-1151 g

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p Safeguards Conditions gl I

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(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).

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(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:

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

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

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

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

10 CFR 75'.4(m) l (d) "Any change in the physical inventory procedures that would adversely h

aifect the inventory taking for the Agency's accounting purposes" means:

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N{i Any change to the description data contained in Paragraph 34 (per the d

N referenced attachments) of the DIO dated October 14.-1985, or as modified f E

E in accordance with 10 CFR 75.11(c). that would not permit the Agency to j

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conclude an SNM material balance,for the Wastinghouse-Columbia facility.

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(e) " Introduction ofcasignificantly[lessaccurateanalyticalmethodfor lE acccunt}ngpurposes"means:

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

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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.

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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:

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Any channe that results in the estimates of the systematic error being E

R affected by a factor of two or more.

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R (g) Any change in the statistical procedures used to combine individual 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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FAGES g

NRj FORM 374A Lxense Number g

SNM-1107 g

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 i outlined in Attachments 37.1, 37.2. and 37.3 referenced in Paragraph 37 of a the D1Q dated October 14, 1985, or as modified in accordance with 10 CFR q

75.11(c).

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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.

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g SG-3.1.4 With respect to Transitional Facility Attachment Code 4:

g

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xq 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

i shall be submitted within three regular workdays of the telephone y

g g

noti fication, l

WithrespecttoTAqsitionalFacilit Attachment Code 4.1:

SG-3.1.5 N

Measureddiscardsshb61dbereporUdd'aseanSNJ(Shipmentdonon-safeguards 8

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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

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shipped off-site).

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N 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.

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