ML20151X003

From kanterella
Revision as of 21:53, 10 December 2021 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Amend 13 to License SNM-1227 for Siemens Power Corp
ML20151X003
Person / Time
Site: Framatome ANP Richland
Issue date: 09/01/1998
From: Emeigh C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20151W999 List:
References
NUDOCS 9809160216
Download: ML20151X003 (4)


Text

.- -. - - - . - . - .- _ .

NRC FORM 374 u.S. NUCLEAR REGULATORY Commission PAGE 1 oF 4 PAGEs l l

l MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10 Code l of Faderal Regulations, Chaptor I, Parts 30,31,32,33,34,35,36,39,40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, i source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such materia l to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license i shill be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

Licensee

1. Siemens Power Corporation 3. Ucense Number SNM-1227 Amendment 13
4. Expiration Date November 30,2001 lan WA 9352-0 30 pRC7 '
5. Docket No. 70-1257 l l

/ Reference No.

.a 6 Byproduct Source, and/or @ 7. Chemical and/or Physical ,6. Maximum amount that Licensee Special Nuclear Material 3 Form ".*',May Possess at Any One Time qf  ; -p +'tJnder This License n , U,  : 1f. O A. Uranium enriched in U-235 4

w A.i 'Any ,

-^

Qf. A.b350 g U-235 r?y>

j g, W ~

_my  :-

C. Plutonium /' Q C. Sealed sourcei y b. 1 mg Pu and not more

% T, and standards 0" than 1.5 millicuries

s. .

.p D, Plutonium D. PuO2 -UO, ' ~ D. 500 g Pu stored waste

9. Authorized place of use: The licensee's existing facilities at Richland, Washington.
10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. These sections are part of the license, and the licensee is subject to compliance with alllisted conditions in each section.

FOR THE NUCLEAR REGULATORY COMMISSION D9e: 9// /#if Br. a es 5'rYh' A ing Chief Division of Fuel Cycle Safety and Safeguards 9909160216 990901

'Vashington, DC 20555 PDR ADOCK 07001257 C PDR g

=

NRC FORM 3744 U.S. NUCLEAR RE uLAToRY CoMMISsloN PAGE 2 of 4 PAGEs

, License Number SNM-1227 1 MATERIALS LICENSE oxket or Reference Number l SUPPLEMENTARY SHEET 70-1257 l Amendment No.13 l

l SAFETY CONDITIONS S-1 Authorized use: For use in accordance with the statements, representations, and conditions of Part I i of the licensee's application dated October 28,1996, and supolements dated February 21, March 12, l March 18, May 1, June 9, July 30, August 4, August 13, August 28, January 28, and September 29, 1997; and February 6, April 23, and May 29,1998.

S-2 The licensee shall maintain and execute the response measures in the Emergency Plan, Revision 21, dated April 28,1997; or as further revised by the licensee consistent with 10 CFR 70.32(i).

S-3 Notwithstanding Section 6.5 of Part i of the license dated October 28,1996, new uranium hexafluoride I

(UF.) cylinders purchased by SPC shall conform to ANSI N14.1 or to the tinning requirements specified in NRC's Certificate of Compliance No. 9196 for Model UX,-30 packages.

x X 3 S-4 The licensee shall not p,rocess alcohol rags through the Mo'dular Extraction / Recovery Facility.

,% - . :. n S-5. Before processing in the Solids Processing Facility l(SPF) filtrate tank, the licensee shall assure through periodic sampling of the lagoons and independerit sampling of,the SPF feed tank, which is before the  ;

mors than 4.0 wt& U-235.

SPF filtrate tank, that 1he enrichment isg& =

. m  : i 1 <;;M jlp

o e .

i l

l  !

. .- _- - . -,-~.- ,

NRC FORM 374A U.S. NUCLEAR RE0uLAToRY Commission PAGE 3 of 4 PAGEs

. Ucense Number l SNM-1227 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1257 l Amendment No.13 l

SAFEGUARDS CONDITIONS Section 1.0 - Material Control & Accounting SG-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 through 8.0 (with all pages designated as Revision 30 and dated February 1997) of its Fundamental Nuclear Material Control Plan, titled

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

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. n

, pf, n b_ o t ,

SG-1.2 Notwithstanding Chapter 0.0 ofihe Plan identifidd by Condition SG-1.1, which commits to meeting l all Affirmation Statements contained in NUREG-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 receipt of retumed fuel rods and/or fuel, assemblies (that were originally fabricated at the licensee's facility i and whose SNM encapsuiation has not been compromised) need not be measured if the original

~

I fabrication values are booked as ' receipt values.

/-

l SG-1.3 A special shutdown; cleanout phpsicat inventory shall be initiated whenever:

(i) a loss / theft indication ir tving an antity ' equal or greater than the licensee's Detection Quantity (as defined in Section 8.2.7 of the PlarOdentified by Condition SG-1.1) i l

cannot otherwise be resoly,ed within 60 days of the initialiecognition of such indication, and m f (ii) a Regulatory ID (as definkd in Section 5.13_of the Plan identified in Condition SG-1.1) equals or exceeds the licensee's Detection Threshold Quantity (as defined in Section 8.2.7 of the Plan identified by Condition SG-1.1).

Whenever a special inventory is required by either (i) or (ii) above, all unsealed and unencapsulated SNM items that are on hand at the time that such a situation is determined to exist, shall be measured (even if previously measured) for SNM content.

SG-1.4 Operations involving special nuclear materials which are not described in the Plan identified in Condition SG-1.1 shall not be initiated until an appropriate safeguards plan has been approved by the appropriate safeguards licensing authority of the Nuclear Regulatory Commission.

Section 2.0 - Physical Protection For SNM of Low Strategic Significance l

SG-2.1 The licensee shall follow the physical protection plan entitled "Siemens Power Corporation Physical j Protection Plan for Special Nuclear Material of Low Strategic Significance," Revision 15, dated January 1998 (letter dated January 22,1998); and as it may be further revised in accordance with l the provisions of 10 CFR 70.32(e).

i SG-2.2 The licensee shall ensure that the UO 2Building is locked when unoccupied.

[

NRC FORJ 374A U.S. NUCLEAR RE!uLAToRY COMMISSloN PAGE 4 of 4 PAGEs Ucense Number SNM-1227 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 70-1257 Amendment No.13 Section 3.0 - International Safeguards SG-3.1 The licensee shall follow, as applicable, Codes 2 through 7 of Transitional Facility Attachment No.

1a dated May 1,1986, to the US/lAEA Safeguards Agreement.

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 licensee may submit required data in the Advanced Nuclear Fuels Corporation license paper format.

, ei .: c -

^

lG ' '

, s t .

v e.,

, ;s

e

  • r

- *[4[

h.  %:A .

4

"(p; l O

,.., ,// e,

. f ..

N~ ~l% ',

w _S.,' , ' k' t j'; ~ 'ugg s y' - .,. _

G i .. e

(,, , >)

'1% , , . *

< jy'
  • ie V,

9:, ..lg~, y fu (y,

Fj

<, . :l j .,i 1 e s

'4

/

, . . J l.

1 1

i i

!