ML20216J652

From kanterella
Jump to navigation Jump to search
Amend 5 to License SNM-1227,authorizing Organizational Changes to Facilities at Richland,Wa
ML20216J652
Person / Time
Site: Framatome ANP Richland
Issue date: 08/29/1997
From: Weber M
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20216J644 List:
References
NUDOCS 9709180026
Download: ML20216J652 (4)


Text

_ _.

iOiOiOiOiDiOiOiDiDiOIOiGiOiOiDiOiOiOiOIDiOiGiOiOiO3OfCTOiDiDiOiOiDiOffOiOIDIOiOi 330@j jf %RC g, FORM 374 U.S. NUCLEAR REGULATOHY COMMISSION

-~ #

h M ATERI Al.S 1,ICENSE h j5 0 l Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganitation Act of 1974 (Public 1.aw 93 4%), and Title 10, Code of l

l4 Federal Regulations. Chapter I, Parts 30,31,32,33.14,35, %,39,40, and 70, and in reliance on statements and representations heretofore made Q Q by the licensee, a license is hereby iwued authorinng the licensee to recene, acquire, possea, and transfer by product, source, and speci Q material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deiner er transfer iuch material to p

!$ persons authorized to receise it in acco dance with the regulauons of the applicable PartM This license shall be deemed to contain the conditions;

% specified in Section 183 of the Atomie Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the g 3 Nuclear Regulatory Commisdon now or hereafter in ef fect and to any conditions specified below.

h I 1.icensee p {

3 1. Siemens Power Corporation 3.1.icense Number SNM-1227 lc la, Amendment 5 I

I

,y l

I j,~ 2101 Horn Rapids Road l' E

l j Richland, WA 99352-0130 4.1!viration Date November 30, 2001 I

lJ

5. Docket or
h. ,

g 70-1257 El Refereree No. g h

6. !!) product, Source, and/or 7. Chemical and/or Physical 8. M<uimum Amount that 1.ieensee

$ Special Nuclear Mater;al Form h

May Possess at Any One Time Under This I icense k

g& Q a

2 o

Q A. Uranium enriched A. Any A. 350 g U-235 h

$ in U-235 9 p G h B. Uranium enriched up to B. Uranium B. 25,000 kg U-235 d 5.00 wt 4 U-235  %

compounds 6 a

e a Q C. Plutonium C. Sealed sources C. I mg Pu and not more %l 9 and standards than 1.5 millicuries w W T l;i D. Plutonium Q

D. Pu0,-U0, stored waste D. 500 g Pu 2 Q @

g 9. Authorized place of use: The licensee's existing facilities at Richland, Washington. @  ?

Q 2 g 10. This license shall be deemed to contain two sections: Safety Conditions and 2 P Safeguards Conditions. These sections are part of the license, and the licensee @

E!

6; is subject to compliance with all listed conditions in each section. @

a l$

l3  ![

al IEl w FOR THE NUCLEAR REGULATORY COMMISSION 0l y

9 C

\

' 2j,44 [Ok $

i Date: A'M '

By: liichael F. Weber a Division of Fuel Cycle Safety r l6 and Safeguards  ;

@ Washington, DC 20555 r

& N S w O 97o9100026 970829 r" Q PDR ADOCK 07001227 b C PDR i

kdOM3030E303i4U5U!U!U!U*t*J5Ufu!UF3FJ!iMUNEU50!G!Uff30!O!O!O!O!OIO!O!O!O!Gs30105Q101050h l

Lkense Nurthr SNM-1227 Amendment 5 h

l p MATERI ALS LICENSE Met w Reference Number -

( SUPPLEMENTARY SHEET 70-1257 E I SAFETY ONDITIONS SAFETY CONDITIONS

(,

s S 1.

q Authorized use: For use in accordance with the statements, representations, and conditions of Part I of the licensee's application dated October P8, 1996, and (

E revised pages submitted with letter dated November 11, 1996, and February 21, t y March 7, May 1 and June 9, August 13, 1997, and with letters dated June 14, 1996, W y March 5, March 12, May 22, July 15, August 8, and August 28, 1997, g W E g S-2 The licensee shall maintain and execute,the response measures in the g g Emergency Plan, Revision 20,-datedd. January 8,'1996; or as further y revised by the licensee consistent with 10 CFRt70/32(I). ,

l S-3 NotwithstandingSection"$.5ofPartIofthelicensedstedOctober l 28, 1996, new g y uranium hexafluoride '(UF ) cylinders purchased by SPC shall conform to ANSI N14.1 ,g g or to the tinning requirements specified in NRC's Certificate of Cor.pliance lg g No. 9196 for Model UX-30 packages.

{g N

m 16

' n' m

a l4 E s # lE m it s

jk d >

> < '~ is

? ~ > ;5

<!lfi'.

m . E y , - -

, , , g n -

, t '

"u O 8

'N s  !! ,f E h ,

l + , #9 1 s

g h W n

p N E

R y $

E M

M N

p M

E N

' M s M

wFOnM ummwxwin.iost=GiGitwompXmitmi&OlusLKamauwasosuwmw.wEJw_wLws.mxx$

374A u.S. NUCLE AR GEoVLA?o9Y COMMISSION PAGE 3 or 4 PAGES I y:. , . Lunsesumwr i SNM-1227 Amendment 5 6

p. MN1 Eltl AIS 1.lCENSE g SUPPLEMENTAFtY SHEET D.gegrpmNnNr =

8; SAFEGUARDS CONDITIONS i r

p' SAFEGUAkOS COND1T10NS i M

h Snifon_,1.0 - Ma,t.enial Centrol & Accoun.t.ing I l

I ghSG-1.1 The licensee shall follow Sections 0.0,1.0, and 6.0 (with all pages designated '

as Revision 28 and dated June 1996), and Sections 2.0 through 5.0, and 7.0 I Wl g through 8.0 (with all pages designated as Revision 30 and dated February 1997) of its Fundamental Nuclear Material Control Plan, titled " Nuclear Materials I

Safeguards Procedures Description for the Fuels Fabrication Plants, EMF-12(P)." I

!g Revisions to this Plan shall be made in accordance with, and pursuant to, the provisions of either 10 CFR 70.32(c) or 70.34. !q y SG-1.2 Notwithstanding Chapter 0.0 of the Plan identified by Condition SG-1.1, i

.g l which connits to meeting all Affirmation Statements contained in NUREG- .

g l

1065 (Rev. 1), the licensee is hereby granted a limited exception from the first Affirmation contained in Section 4.3 of NUREG-1065 in that t lj y;i receipt of returned fuel rods and/or fuel assemblies (that were originally fabricated at the licensee's facility and whose SNM f!g g encapsulation has not been compromised) need not be measured if the !g y orig-inal fabrication values are booked as receipt values. g fSG1.3 A special shutdown, cleanout physical inventory shall-be initiated I whenever: f (i) a loss / theft indication involving an SNM quantity equal tc or glh N

1 l

greater than the licensee's Cetection-Quantity (as defined in 3~

3 Section 8.2.'7 of the Plan identified by Condition SG-1.1) cannot h

$ otherwise be resolved within 60 days of_the initial recognition of E N such indication, and x E

$j E bi (11) a Regulatory ID (as defined in Section 5.13 of the Plan identiDed ,E al in condition SG-1.1) equels or exceeds the licensee's Detection E El Threshold Quantity (as defined in Section 8.2.7 of the Plan E identified by Condition SG-1.1)".' E 8

Whenever a special inventory is required by either (i) or (ii) above, all E unsealed and unencapsulated SNM items that are on hand at the time that E D such a situation.Is determined to exist, shall be measured (even if E R previously measured) for SNM content, E B E h SG-1.4 Operations involving special nuclear materials which are not described in b the Plan identified in Condition SG-1.l_shall not be initiated until an '

approp'iate safeguards plan has been approved by the appropriate safeguards licensing authority of the Nuclear Regulatory Commission.

N -

e n.

f\

is 4 w ~E = = @ RONUKliGiGR E 50i M F am N N 7= W N M Jai X M X K @ X M M X 6 ~= D

ALIEMERR_uLW_W5_WER_WERR.NLWE.NLW_WLWLW MLWLWLWLW W3 _ _ .. -

NRC FORM 374A U.S. NUCLEAR REoVLATORY_ COMMIS$loN 4 PAGE or 4 PAGES '

. uww soner i(g

, SNM-1227 Amendment 5 !g Ff*.

MATERIALS LICENSE in ket or Referen Nunder I SUPPLEMENTARY SHEET 70-1257_ I(g m;

SAFCGUARDS CONDITIONS f E II I I

N,  :

R I

I(E g lection 2.0 - Physical Protqqtion_f,qr SNM of Low Strateoic Sionificance g N E s SG 2.1 The licensee shall follow the physical protection plan entitled "Siemens Power

!q g Corporation Physical Protection Plan for Special Nuclear Material of Lou !q .

y Strategic Significance," Revision 13, dated October 1995 (letter dated Ig l t October 16,1995); and as it may be further revised in accordance with the !g l

g provisions of 10 CFR 73.32(e). g i y .. .

t4 L g SG-2.2 The licensee shall ensure that the'U0; Building is locked when lg g! unoccupied, l g

l hSection3.0-InternationalSafeauards f SG-3.1 The licensee shall' follow, as applicable, Codes 2 through 7 of Transitional Facility Attachment No. la dated May 1, 1986, to the US/IAEA f

!g Safeguards Agreement.

Q y

g SG-3.2 Notwithstanding the requirements of 10 CFR 75.11(d) to submit facility data on forms-supplied by the Commission (including IAEA DIQs), the f

!g y licensee may submit required data in the Advanced Nuclear Fuels I Corporation license paper format. g g g N ;E W. E

  1. lE b

N R

R E R: IE

{. l E

B E, R E N E B E N' E n E N E N,

E B e p

4-p E

R E

b W D E N

lW k.r= = -rmm - orm - a = = == rwr.cg*_r;. cur mc rg_ g= m_ .m_ g-r -3 _;-r4= mO