ML20216J652

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: ML20216J639 ML20216J652 ML20216J666
References
NUDOCS 9709180026
Download: ML20216J652 (4)

Text

_

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

-~

g, hj5 M ATERI Al.S 1,ICENSE h0 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 p3 1.

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

,y I

l l j, 2101 Horn Rapids Road l'

I E

~

lJ h.

I j

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

5. Docket or 70-1257 El g

Refereree No.

g h

6. !!) product, Source, and/or

7. Chemical and/or Physical

8. M<uimum Amount that 1.ieensee h

Special Nuclear Mater;al Form May Possess at Any One Time k

g&

Under This I icense Q2 a

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

ae 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 D.

Pu0,-U0, D.

500 g Pu 2

Q stored waste 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 FOR THE NUCLEAR REGULATORY COMMISSION 0l w9 y

C

\\

2j,44

[Ok A'M i

Date:

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

h Lkense Nurthr SNM-1227 Amendment 5 p

MATERI ALS LICENSE Met w Reference Number l

(

SUPPLEMENTARY SHEET 70-1257 E

I SAFETY ONDITIONS SAFETY CONDITIONS

(

s q

S 1.

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 28, 1996, new g

l 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 l4 n'

m E

a s

lE m

it jk d

s is

? ~ >

5

'~

m

<!lfi'.

E y

g n

t "u

O 8

'N

,f E

s h

l

+

1. 9 1

s h

g W

n N

p E

R y

E M

M N

M p

E N

M s

M

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

FOnM 374A u.S. NUCLE AR GEoVLA?o9Y COMMISSION I

PAGE 3

or 4

PAGES y:.

Lunsesumwr i

SNM-1227 Amendment 5 6

p.

MN1 Eltl AIS 1.lCENSE D.gegrpmNnNr

=

g SUPPLEMENTAFtY SHEET 8;

SAFEGUARDS CONDITIONS i

r p'

SAFEGUAkOS COND1T10NS i

Mh 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 Wl as Revision 28 and dated June 1996), and Sections 2.0 through 5.0, and 7.0 I

g through 8.0 (with all pages designated as Revision 30 and dated February 1997) of I

its Fundamental Nuclear Material Control Plan, titled " Nuclear Materials 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 SG-1.2 Notwithstanding Chapter 0.0 of the Plan identified by Condition SG-1.1, i

y l

which connits to meeting all Affirmation Statements contained in NUREG-

.g lg 1065 (Rev. 1), the licensee is hereby granted a limited exception from lj the first Affirmation contained in Section 4.3 of NUREG-1065 in that t

receipt of returned fuel rods and/or fuel assemblies (that were f

originally fabricated at the licensee's facility and whose SNM

!g y;i encapsulation has not been compromised) need not be measured if the

!g g

y orig-inal fabrication values are booked as receipt values.

g fSG1.3 A special shutdown, cleanout physical inventory shall-be initiated f

I whenever:

glh 3~

1 l

(i) a loss / theft indication involving an SNM quantity equal tc or N

greater than the licensee's Cetection-Quantity (as defined in Section 8.2.'7 of the Plan identified by Condition SG-1.1) cannot h

3 otherwise be resolved within 60 days of_the initial recognition of E

N such indication, and E

$j x

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 f\\

n.

is 4

e 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 _ _..

Ff*.

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

or 4

PAGES i(g uww soner SNM-1227 Amendment 5

!g I

MATERIALS LICENSE in ket or Referen Nunder SUPPLEMENTARY SHEET 70-1257_

I(g f

SAFCGUARDS CONDITIONS m;

E II I

N, I

I(

I R

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 l

g!

unoccupied, lg hSection3.0-InternationalSafeauards f

SG-3.1 The licensee shall' follow, as applicable, Codes 2 through 7 of f

Transitional Facility Attachment No. la dated May 1, 1986, to the US/IAEA

!g Safeguards Agreement.

Q y

Notwithstanding the requirements of 10 CFR 75.11(d) to submit facility f

SG-3.2 g

data on forms-supplied by the Commission (including IAEA DIQs), the

!g y

licensee may submit required data in the Advanced Nuclear Fuels I

g Corporation license paper format.

g g

N

E W.

lE E

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