ML20203A416

Amend 10 to SNM-1107 for Westinghouse Electric Corp

ML20203A416
Person / Time
Site:	Westinghouse
Issue date:	02/04/1998
From:	Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20203A406	List: ML20203A400 ML20203A416 ML20203A436
References
NUDOCS 9802240030
Download: ML20203A416 (7)

Text

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I M ATERI Al.S I.ICI'NSI' W Purtuant to the Atonne 1:ncip) Art of 1954, as amended, the I:ncrgy Reorganuatmn Att of 1974 (Pubhc l.aw 93 43% and 'litle 10. Code of 'g

[g I ederal kerulattom. Chapter 1. Parts 30. 31,32, U. 34,35. %. 39,40, and 70, and in rehanc (

g h) the licensee, a hcense is hereby inued authorusop the hcensee to receise, atquire, pouru, and transfer byproduct, s.ource, and qwial nutieur b h material designated below; to use such material for the purposeN and at the place (s) designated below; to deliser or transfer such material to 0 4 perwn authorned to re(ene it in atcordance with the regulatiom of the applicable Partht 1his hceme shall be deemed to contain the conditions $l h speafied in Net tion IM of the Atomic l.nerFy me of 1954, as annended, and n subject to all apphceble rules, regulations, and ordcrv, of thei hl

% Nuclear Regulatory Commission naw or hereaf ter in ef fect and to any nindstiota speahed behw. t Q Y lir- - 1.icensee k

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$l l. 3.1.icense Number

• Westinghouse Electric Corporation SNM 1107 h  !

dj Amendment 10 f'l 5 P.O. Box 355 j l

%; 2. *P '"'i"" D 'e Pittsburgh, Pennsylvania 15230-0355 i November 30,2005 h.l! l p'

l 5. DocLef or (

j Reference No 70-1151 g h h Ilyproduct. Source, and/ot 7. rhenhal and/or Physical 8. Masimum Anmunt that I.icensee Q g.

l Special Nuclear Material Form May Powess at Any One Time (

Under This License Q Q h 9 Q

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1. A. U-235 A. Any A. 0.35 kg 4, B. U 235 B. Any, except B. 75,000 kgs %y 4, metal, enriched he' 4; to not more ij than 5.0 w/o k 9 C. U 233 C. Any C. 5 grams gi I D. Pu-238, Pu-239 D. Sealed sources D. 1.5 grams

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g Al 9 il 9. Authorized place of use: The licensee's existing facilities at Columbia, South Carolina. Q El Q il 10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. Q 5! These sections are part of the license and the licensee is subject to compliance with alllisted M conditions in each section, W@

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g FOR THE NUCLEAR REGULATORY COMMISSION k5

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Date: D By: Michael F. Weber 1 Division of Fuel Cycle Safety @

4 g and Safeguards !sl y Washington, DC 20555 %l 9l b l

F hl 9802240030 900204 8*

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$NM-1107 Amendment 10 l1 1

M ATERI ALS LICENSE twei or neverrme Nwer h h, SUPPLEMENTARY SHEET 70-1151 ( '

, S pl SAFETY CONDITIONS

, SAFETY CONDITIONS g H

i't G-1 Authorized use: For use in accordance with statements, representations, and conditions in the li license application dated April 30,1995, and supplements usted May 11 and 18, August 4 and g

g y

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

, December 17,1997; and January 9,1998. W S-2. The Criticality Safety Evaluations (CSEs) and Criticality Safety Analysis (CSAs) will d9 fine the l criticality safety bases utilized throughout the plant and will be completed as described in

, y

, Sections 6.4.1 and 6.4.2 of the licen ap ' n for each step of the process. A submittal to y

, w'f if$ e information which the staff will review y the NRC against thewill be madelisteYir commitment by Wettin@Section 6.2.3 ofth se application. These submittats will

,. y

, not be specific com tYbut are intended as a dem fhtion of the ariequacy of the bases y

, of safetyitemizedIr> n 6.2.3. The contents listed in Se6tjdh 6.4.2 of the license application y y

are commitment demonstration will show the logic used tV e Columbia Fuel Fabrication g

, Facility (CFFF) in developing the enticality safety bases. It is unc e od that this demonstration y g may change o4rfimexThe, submittal will consist of a summary of SE or CSA as annotated y

,1 below for es stem (wh' $allinclude fault trees fophose syst for which a CSE will be g I done). The uacy of th9 niitments in Sect ' 2 6f the lice application will be y

, evaluated a reply in the f ,' of ja lekr~ report generated a ent from the staff to y

, Westinghou( The submittalb he CFfT w ed according @e following schedule: y

• UN tanh summary.ofC E-1Y 5 U j ,

~{ f e URRS solver- sur , . * <'

5

• Solvent Extracuor@pmary,0f0/95 ummar of %$ " 780*

• CSE8Of" ' e D g 5

• Processhg; / l- -

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• URRS Low.Leve S@l Waste Processin9 System l[tulmtpary of CSA - 9/96 g Mop Wats (System Equipment - summary of CSAi 9/96 incinerator System summary of,CSE- 9/96 Wy g)d y y

Ash Recoverp System summary 6f CSE 9/96 g Liquid Honing Syster. - summary of CSE - 9/96 y Ultrasonic Cleaning Syste[n summary of CSE - 9/96\4 .y Shredder System - summary of CSEr 9/96, M g

• URRS Waste Treatment - summary'ef CSO 11/95 hi e IDR Conversion - summary of CSE - Prior to Restart g

g

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• ADU Conversion summary of CSE - 4/96 y g

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

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• Powder Blent,ing - summary of CSE - 1/96 y

• Miscellaneous:

Ventilation Systems (Geumetry Controlled) -

, summary of CSE - 3/98" y

, Ventilation Systems (Moderation Control!ed)- g summary of CSE - 3/98" y Scrubber Systems - summary of CSE 12/97" g Hoods & Containment - summary of CSA - 9/96 g Laboratories - summary of CSA - 9/90 g

• IFBA - summary of CSA - 3/96 g g{

• Storage Pad - NCS is based on DOE reports 41920 and K 1663 y B 8 I e I! N

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L NR TORM 374A U.S. NUCLE AR CEOULATo Y CoMMISSloN MLWJELNJUBLEJEL$

PAGE 3 OF 7 PAGEE !g l La enw Number  %;

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SNM-1107 Amendment 10 hl M ATERI AI,S I,1 CENSE rxaci w Reierence Numter 'g i llp; -

SUPPLEMENTARY SHEET 70-1151

!gN II g SAFETY CONDITIONS 'g .

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Rods summary of CSA 3/96 Storage - summary of CSE 4/97 l

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• Final Assembly- summary of CSE 6/97 y

,

• UF, Cylinder Washing - sumrnary of CSE - 12/95 g y

• The CFFF has performed a CSA upgrade and does not have a specific date for schedule of this CSE at g this time.

" These systems are to be coupledq Col bia Pia t s n ment Program (RMP) to be done for the EPA g g S3 The licensee shall mainte@and execute the response measures in the Emergency Plan, dated g y April 30,1990, and re sions

^

dated March 31, and September 30,1992; 25, August 15, and g

September 30,1994 ry% February 17, August 17, and Octobet23,  ; or as furthar revised by g the licensee consist +

g 10 Cf 70.02(i). y 1 N -f y

S-4 4

Notwithstanding thefpquirements N

'the extemhrfaces of packagud g

y g FF 20:265'(b) t p radioactive materialveceipts for radi ve contaminatio g iconsee is exotipted from such g g requirement miativ to flatbed trailer shiptnents of fuel ass _

received from the General Electric g

Company for interi p(orage purpose (tmly,$tovided thetionstrs,ints,' condition (,end controls committed g g! to in the I;censee's ter, dated November 30 1 g gl further provided that }he totalnurnber of sdch s sl06lf()kntification # NRC-93,D36 are satisfied; y andul

, time does not excee4260. j?g Q g

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Lu rtne Numtxt Ill i

SNM-1107 Amendment 10 l 4 M ATERI Al.S I,1 CENSE t w enn w a rsumto 70-1151 StJPPLEMENTARY SHEET Q@

SAFEGUARDS CONDITIONS

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lh pl r? l g SAFEGUARDS CONDITIONS

> E g SEC flON 1.Q- MATERIAL CONTRCL AND ACCOUNTING h E

3 h SG-1.1 The licensee shall follow pages i through xvil and Chapters 1.0 through 9.0 of its " Fundamental y g! Nuclear Material Control Plan for the Columbia Fuel Fabrication Facility," with all pages identified g j

/ as Revision 27 (dated May 23,1997). /.r,y further revisions to this Plan shall be made only in accordance with, and pursuant to, either 10 CFR 70.32(c) or 70.34.

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N y SG-1.2 Operations involving special nuclear material which are not referenced in the Plan identified in g y Condition SG 1.1 shall not b9 initiate ntil p by the Nuclear Regu'atory C i - p(qpriate y safeguards plan has been appr y g fai m SG-1.3 in lieu of the requiremebcontained in 10 CFR 74.13(a)(1)$dja)(2) to use the Forms

/ DOE /NRC-742 and 7@C, the licensee may use computer generated forms provided all y

[ the particular form is g l information

'""d *d '

cp xe requirk by th3 latest printed instruction , l l/

/

SG-1.4 In lieu of the requirements cortt ained in CFR 70.54 and 7 ,15 to use the DOE /NRC Form-741, the licensee y use compute (generated (orms 'vid_ all information required by the latest y

g printed inst tions for completing the particdlar f is)ngluded. \/ g gl h '('

! 61 O g SG-1.5 Deleted Per Amendment 3, Aupost 1996 Commitment now contained inicensee's Fundamental n h W#, ,

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SG 1.6 Notwithstandipg iN Nucleor Ma(Wefial Control PlanJQl { { ((C the r$of. th(ljh hp {$3an idenlified In' Licen(se Condition equirements g

y S h

y licensee may pse (1) a single standard for (nehu'rement control (includine daily control limit g I monitoring and bias corrections) for arVifnetr! ret.ponse IObe or rod wik:s, in any initially p I 4 demonstrated t'o be linear over its range of Ose within the discriminiti6n of the scale by g y

ca!culating a bias at four levels across the range of use'and demonstrating that the four results g Q are not statistically different, and (2) that the continued linearity of response of the scales is g y

y verified by monthly calibration against at least four traceab}e' standards covering the range of g I use. q g N y l

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,4 SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5 2.3 of the licensee's g U Furidamental Nuclear Mate.ial Control Plan, the licensee is exempted from physical inventory g requirements relative to the materialidentified in Condition S-4; provided the conditions and g commitments contained in the licensee's November 30,1993, letter (identification # NRC-93-036) y are satisfied. E is SG-1.8 Notwithstanding the requirement of Section 6.2.1(a).5 of the licensee's Fundamental Nuclear y g

Material Control Plan to unpackage and perform an item count upon receipt of special nuclear g q y material, the licensee is exempted from such requirement relative to the material identified in fg Condition S-4; provided the conditions and commitments contained in the licensee's q

' November 30,1993, letter (identification # NRC-93-036) are satisfied. p W

SG-1.9 Notwithstanding the requirement of Section li.A.7, block U, of NUREG/BR-0006, which is E h incorporated via 10 CFR 74.15, to complete receiver's measursments of scrap receipts (following g I

recovery processing) within 60 days of receipt, the licensee shall not be subject to any time limit y relative to recovering and measuring received UF. heels when the block U action code (of E g

DOE /NRC Form 741) is used to book such receipts. g 3OgonTis a m a a mumiert a mKgepp mp~eXMCeXm mEMETeFmTEN mE =

] KNMR.ws.wmmxwm wxmxwxwsaxwxwxwsxw_w w_wmxwxwysawxwxw., q NR FORM mA U s. NUCLE AR CEQULAToRY CoMMISsloN 5 or PAGE 7 pacts Ij Lkcrac NumN r I q

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, i SNM-1107 Amendment 10 4 M ATERI Al,S 1.lCENSE

( tmen, werence Numa r -!1 l . . SUPPLEMENTARY SHEET 70-1151 D

-g p i SAFEGUARDS CONDITIONS P 1 ' SG 1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1,1, ' allowed number [ l 4 I within the phrase " allowed number of defects

• is hereby specified ris being: i l l

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

l (ii) no more than one defect when aach item within a batch of items has an assigned value of l less than 500 grams U-235, but one or more items has an assigned value in excess of 50 grams '

4 U-235; and L 0

(iii) zero debt when any item within a batch of items contains 500 or more grams U 235. (

SG 1.11 Notwithstanding the first licensee shall conduct h 1hyP an identified by Condition SG-1,1, the ceiver comparisons M i SJM materials rta.eived (regardless I of whether booked on sis of receiver's or shipper's vafybskexcept for those materials (

ident,fied in Sectio h of NUREG 1065 (Rev 2) as being exerMied from shipper-receiver l l

comparisons. Q l l SECTION 2 0 - PHYSICALkT C ON OF SNM OF LOW STRATEGIC'8IG K%NCE l ,

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i SG-2.1 The license / dell follow the 't;4e Physical Securit/ s 4Westingh Electric Corporation, i Columbia, S.Q ," dated March 11$80', Reviolon 10.4 October 1,  ; the " Revision Record" I contained in'the approved Physical Security Plan ( t to October ); and as may be I revised inmaboordance'with r

they%'ovislohs

.32(e).,

of, 10 Cp c p I

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i SECTION 3.0-INTERNATIONAL 8AFEGUARD$p 7

y l SG-3.1 The licenseehall foi '

it pg o TrInsMior lity At chment No. 5A dated i I August 31,1988lto the US/tAEA' Safe s Agre4 menti Such TrinSitional Facility Attachment I 1

4 shall be interpreted n accordance with Conditions g.1.1 throug3BG-3.1,7. I A A '. I , t & h  % I SG 3.1.1 With respect to Transit al Facility Attachment Code 2: I The reference design information is that datew - he licensee on October 14,1985. "Information u l

I on the Facility" also includes'otherjecility"lnformanon submitted via Concise Notes in accordance g

I with 10 CFR 75.11(c). g i u 1 SG 3.1.2 With respect to Transitional Facility Attachment Code 2.2: -

1 J I

( Substantive changes to the information provided in the Columbia Plant Design Information I

] Questionnaire (DlQ) means those changes requiring amendment of the Transitional Facility I

% Attachment. Such changes shall be provided by letter to the NRC Offee of Nuclear Material u Safety and Safeguards at least 70 days in advance of implementation. I I

lI .

Non substa clm -hanges to the information in the DlO means those changes not requiring amendment of the Transitional Facility Attachment. Such changes shall be provided by Concise i

I I Note (From DOE /NRC-740M) within 30 days of receiving miiGcet;en from the NRC that the I N facility has been identified under Article 39(b) of the US/lAEA Safeguards Agreement. I E

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

be submitted in advance), are those items stated in Code 2.2, specificalty-g

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, NR ORM 374A U.S, NUCLE A") REOULAToRY Commission pc 6 or 7 pas I nense Numhet pl SNM-1107 Arnendmnat 10 g M A'l ERI AI,S 1.lCENSE l ig g*Iewnee Numner SUPPLEMENTARY SHEET v]

SAFEGtJARDS CONDITIONS g (a) "Any change in the purpose of type of facility" means: $

Any deviation from the described activities involving special nuclear ridarial and any change to the r.'.aximum enrichment and/or quantities of U-235 currently authorized by I License No. SNM-1107, and/or as desenbed in Paragraph 5 of the Design Information !e(

Questionnaire (DIO) dated October 14,1985, or as modified in accordance with 10 CFR I 75,11(c). Included also is any deviation from the described sp3cial nuclear material (SNM) f g

production activities described in paragraph 6 of the DIQ dated October 14,1985, or ac g modified in accordance with 10 CFR 75.11(c). g (b) "Any changes in the layout of thp.(acirty vyhich affects safeguards implementation of the g provisions ofit # Proto rgd1CG g fiig facility and/or site layout or, f% addition affecting any activity Any change in t involving SNM g escribed in Paragraphs 10 and 11 (pepthe referenced attachments of f l h

f}

g the DlQ htqdh ober 14,1985, or as modified in accordarQ with 10 CFR 75.11(c).

included alsSis any modification to, or deviation from, the dat3 provided in Paragraphs 13 y

g y and 14 (pirjhe referenced attachments) of the OlQ dated,0ctob 14,1985, or as modified g p+

f 1

q in accorday with 10 KR 7f : ;(c).

(c) "Any chge that mak5s i elected, Key M sdr9n t Polots (bps)(as described in y Code 3(2) inadequate f6r;the Agency's acc uhtipg purpose" means: _

g y 4  ;[ e'mij y g Any change to the $lPs as(described in Code)342 of,the. Westingh g

j Transitidnal Facility $ttachrpent to Die;UGflAE(Safeguards Agreement, or as modified in g accordance with 10 CFR.75.11(c) esults m an) KMP alteration affecting the purpose g 4' of KMPs'al stipulate'd by 10 CFR 7 *

\Q MQ*Jki Al4Q }0' f (d) "Any change,in it.e physical inventory procedures that would adSrsely affect the inventory fg taking for the Agency's accounting purpones" means:

g y

y  % -

n Any change to the description data contained in Paragraph 34 (per the referenced u

'g g{ attachments) of the'DlQ dated October 14,1985, or as modified in accordance with 10 CFR g

f I 75.11(c), that would not pemut the Agency to c6riclude an SNM material balance for the Westingbouso-Columbia facility, ;i 6 '

g y

(e) " Introduction of a significantty less accurate analytical method for accounting purposes" means: g j Any recalculation of the " Relative Errors-Random and Systematic" as listed in Attachment 36.2 referenced in Paragraph 36 of the OlQ dated October 14,1985, or as modifed in g 4

- accordance with 10 CFR 75.11(c), that results in the estimates of the randum and f systematic e:rors being affected by a factor of two or more. f (f) " Decrease in the frequency of calibrating measuring equipmerit if it signifcantly decreases y the accuracy of the meterials accounting systerr' means: g.

k' n Any change that results in the estimates of the systematic error being affected by a factor of g two er more. g E

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j NMe FOnM 374A U.s. NUCLE AQ REoVLAToRY commission PaGE 7 OF 7 PAGES l Lkenw Number SNM-1107 Amendment 10 I

! MATERI ALS LICENSE twri m Referran Numter l , , SUPPLEMENTARY SHEET 70-1151 SAFEGUARDS CONDITIONS i

j (g) "Any change in the statistical procedures used to combine Individual measurement error

estimates to obtain limits of error for shipper / receiver (S/R) differences and material u

l. unaccounted for (MUF)" means:

l 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 I

!- the DlQ dated October 14,1985, or as modified in accordance with 10 CFR l 75.11(c).

SG-3.1.3 With respect to Transitional Facil' '" nt- P 3.1.2:

l 1 C .U N

ka s (SRDs) must be recorded and KMP*

reported -evenThisif nis a 'e KMP i@py SRDs zero.l shipper receiver are computed ed by the Nuclear Materials i Management and uards System upon receipt of the roce a measurement results. I SG-3.1.4 With respect to_Tr sitional Facility Attachment Code 4:

OA CQ N' ' # f /*

) The licensee 40pil use tlkto al composition codes '

' tod the DlQ dated October 14, i 1985, and a modified by es,4urther sfanding er r requirements for advance ion and/or , @thi$ci .

, or delete i sition codes for

, nuclear met routinely promssed and on irty rp1OFFFi upon telephone notification 5Aho Offloe of Nudikt Matiwial Sefety' (" sefoguards. F documentation, in  ;

chandes to T 1 of Attachment 34.8 l the form to the DlQ sH of )Iail be sUtsjnstled withiri tu " Concise ar%gdidays of the t Note sepoeipapied notification. by a

h]q iM p l f  ;

! SG-3.1.5 7)"Of#t 3 %y4.}p'[y With res Sect hrensNior$} Facil,ity At  ;

y

! \,0 DA Measured discarde should be reported as an SN (Shh, ment to uards facility) when i shipped off-site t'o. art authorized burial ground 3 (The A,EA s 11 not process measured discards as loss /di (LDs) when they are shipped off l SG-3.1.6 With respect to Transitional Facility Attachment Code 5.1.h

! T4 L 45 For inventory changes, time of rec 6tWird NpM means: No later than the next regular workday (MoMay through FrMay),

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

percent through comminging with residual Eriched uranium in process equipment, the resultant product shall be considered as being produced through a blending opersbon and the material category change shall be recorded upon obtaining measurement confirmation that a material category change has occurred.

f SG 3.1.7 With respect to Transibonal Fadirty Attachment Code 6.2.2:

For Concise Notes describing the anticipated operat6onal programme, " anticipated operational programme" means Anticipated physical inventory schedule.

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