ML20198Q283
| ML20198Q283 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 12/30/1997 |
| From: | Schwink W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20198Q276 | List: |
| References | |
| NUDOCS 9801220389 | |
| Download: ML20198Q283 (8) | |
Text
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op.se) u.S. NUCLE A3 cE!ULATOQY CoMMISs40N g
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. Il; MATERIALS LICENSE g
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Pursuant to thq Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, y
l Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,39,40 and 70, and in reliance on statements and representations heretofore g
l' made by the licensee, a liceme is hereby issued authorizing the licensee to receive, acquire, possen. and transfer byprmluct, source, and special l
I nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material I
to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This liceme shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to at pplicable rules, regulations and orders of the Nuclear g
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Regulatory Commission now or hereafter m effect and to any conditions specified below.
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lI ll 1. Westinghouse Electnc Corporeuon
- 3. Ucense number SNM-1107 I!
I Amendment 9 I
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P.O. Box 355 wh A.[Exp9 tion date
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- 5. Docket or % MO-1151 y
Reference No 7 %
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- 7. Chemical and/or physical
- 8. Maximum amount that licensee l
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special nuclear material form mcy possess at any one time 1
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I Ij A. U-235 A.
JAny A.
0.$5 kg i
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s Any, except -
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75,000 kgs i
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' metal, enriched Ili
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5 grams i
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C. U 233 C,
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Sealed sources D.
1,5 grams
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Authorized place of useO The licensee's existing ficilities at Columtna, South Carolina.
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This license shall be doomed to contain two sectsons Safety Conditions and Safeguards Conditions, g
i These sections are part of the license and the licensee is subject to compliance with all listed conditions I
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. In each section.
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FOR THE NUCLEAR REGULATORY COMMISSION g
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/2/b 7 By W "- S. SCAM Actino Chief l
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l Division of Fuel Cycle Safety I
and Safeguards F
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l Washengton, DC 20555 l
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9801220389 971230-g ppR ADOCK 0700 1
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U.s. NUCLEAR RCoVLAToRY CommssioN
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thenne Number l
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.SNM-1107 Amendment 9 l
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MATERIALS LICENSE Docket or Reference Number l
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,8UPPLEMENTARY SHEET 1151 i
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I SAFETY CONDITIONS g
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i SAFETY CONDITIONS g
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1 S1 Authorized use. For use in accordance with statements, representations, and conditions in the u
i license application dated April 30,1995, and supplements dated May 11 and 18, August 4 and g
i 25, September 25,1995; hly 14 and 25, August 11, November 17, and Decembw 17,1997.
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. S 2.
The Crihcahty Safety Evaluations (CSEs) and Crihcahty Safety Analysis (CSAs) will define the g;
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cnticality safety bases utilized throughout the plant and will be completed as described in g"
l Sedions 6.4.1 and 6.4.2 of the hoense apphcation for each step of the process. A submittal to g
i the NRC wiH be made by Westinghouse whiehydd information whidi the staff will review g
I against the commitments listed in*Soction s.t.5:
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not be specific commetrnents, liut are intended as a.
incense apphcahon These submittals wiu q
stration of the adequacy of the bases q,
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I of safety itemized in Seehon' 6.2.3. The contents listed iri Section 6.4.2 of the license appbcabon g
I are commitments. The demonstration will show the logic used by the Columbia Fuel Fabrication g
1 Facility (CFFF) in developing the criticality safety bases, it is understood that this demonstration g
4 may change over time. ~The submittal will consist of a summary of the CSE or CSA as annotated g
i below for each'aystem (which shan include fault trees for those systems for which a CSE will be g
i done). The adequacy of the' commitments in Section 6.2.3 of the license apphcstion will be g
i evaluated and a reply in the form of a letter report will be generated and sent from the staff to u
l Westinghouse. The submittal by the CFFF will be provided according to the following schedule:
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UN tanks - summary of CSE -10/95 l
URRS Dissolver - summary of CSE - 10/95 --
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Solvent Extraction (summary of CSE - TBD*
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e URRS Scrap PE-: ~ ',g:
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Low-Level Waste Pmcessing System "- summary of CSA - 9/96 J g'
l Mop Watysystem Equipment - summary of CSA - 9/96 y
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incinerator System - summary of CSE 9/96 g
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Ash Recovery System - summary of CSE - 9/961 g
l Liquid Honing System - summary of CSE - 9/96 g
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Ultrasonic Cleaning System - summary of CSE - 9/96 y g
l Shredder System ' summary of CSE - 9/96 g
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URRS Waste Treatment - summary of CSA - 11/95 g
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IDR Conversion - summary of CSE - Prior to Restart g
I e-ADU Conversion - summary of CSE-4/96 g
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ADU Pelletag - summary of CSE - 6/96 g
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e Powder Blending - summary of CSE - 1/96 g
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Miscellaneous:
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Ventilation Systems (Geometry Controlled) -
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- summary of CSE - 3/98" g
i VentNetion Systems (Moderation Controlled) -
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summary of CSE - 3/98" g
i Scrubber Systems - summary of CSE - 12/97" g
i Hoods & Containment - summary of CSA - 9/96 g4 i
Laboratories - summary of CSA-9/96 g
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IFBA - summary of CSA - 3/96 Storage Pad - NCS is based on DOE reports K-1920 and K-1663 g
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or 8 PAoEs g
y Ucense Number g
l SNM-1107 Amendment 9 l
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MATERIALS LICENSE SUPPLEMENTARY SHEET q
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l SAFETY CONDITIONS b
e Rods - summary of CSA-3/96 g
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Storage - summary of CSE - 4/97 g
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Final Assembly summary of CSE - 6/97 g
UFe Cylinder Washing - summary of CSE - 12/95 g
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- The CFFF has performed a CSA upgrade and does not have a specrtic date forschedule of this CSE at p
R this time.
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" These systems are to be coupled with the Columbia Plant Risk Management Program (RMP) to be done R
for the EPA 5
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b S-3 The licensee shall maintain and execute then~ sponse measures in the Site Emergency Plan, dated N
I April 30,1990, and revisions dated March'31, and'9ehkMntiet 30,1992; March 25, August 15, and 4
b September 30,1994; January 9,-Februcry 17, August 17, and October 23,1995; or as further revised by 5
I the licensee consistent with 10 CFR 70.32(l).
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N S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the extemal surfaces of packaged
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radioactive material receipts for radioactive contamination, the licensee is exempted from such E
N requirement relative to flatbed traile_r shipments of fuel assemblies received from the General Electric E
N Company for interim storage purposes only, provided the constraints, conditions and controls committed E
N to in the licensee's letter, dated November 30,1993, (identification # NRC 93-036), are satisfied; and ll N
further provided that the total number of such fuel assemblies stored at the licensee's site at any given W
N time does not exceed 250.
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ywC FORM 374A Nn u.s. NUCLEAR REtuLAToMY CotstassioN PAGE 4
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l Licenne Numtet j
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SNM-1107 Amendment 9
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MATERIALS LICENSE onckei or nevennee sumter l
SUPPLEMENTARY SHEET 70-1151
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l SAFEGUARDS CONDITIONS F
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l SAFEGUARDS CONDITIONS t
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SECTION 1.0 - MATERIAL CONTROL AND ACCOUNTING I
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SG-1.1 The licensee shall follow pages i through xvil and Chapters 1.0 through 9.0 of its " Fundamental F
l Nuclear Material Control Plan for the Columbia Fuel Fabncahon Facildy," with all pages identified I
l as Rev6sion 27 (dated May 23,1997). Any further revisions to this Plan shall be made only in
[
l accordance with, and pursuant to, either 10 CFR 70.32(c) or 70.34.
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SG 1.2 -
Operations involving special nuclear potene[
are not referenced in the Plan identitled in l
Condition SG 1,1 shall not bo initisted 6ntitan safeguards plan has been approved s
g by the Nuclear Regulatory Commission.
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p SG-1.3 in lieu of the requirements contained in 10 CFR 74.13(a)(1) and (a)(2) to use the Forms l
DOE /NRC-742 and 742C, the licensee may use computer generated forms provided all g
information required by the latest printed instructions for completing the particular form is included.
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p' SG-1.4 in lieu of the requirements' contained in CFR 70.54 and 74.15 to use the DOE /NRC Form-741, l
g the licensee may use computer generated forms provided all ink,6C Mrequired by the latest g
printed instructions for completing the particular form is included.
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W SG-1.5 Deleted Per Ar.nondment 3, August 1996 Commitment now contained in licensee's Fundamental y
Nuclear Matonal Control Plan.
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l SG-1.6 Notwithstanding the requwements of the FNMC Plan identified in License Condition SG-1,1, the -
p licensee may use (1) a single standerd for measurement control (includeg daily control limi' g
monitoting and bias corrections) for any linear-response tube or rod scales, in any initially g
demonstrated to'be knear over its range of use within the discnminshon of the scale by g
calculating a bias at four levels across the range of use and demonstrating that the four results y
are not statistically different, and (2) that the continued kneanty of response of the scales is y
venfled by monthly calibration against at least four traceable' standards covering the range of r
I use.
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g SG-1.7 Notwithstandmg the requirements contamed in Sections 5.2.2 and 5.2.3 of the licensee's L
g Fundamental Nuclear Matenal Control Plan, the licensee is exempted from physical inventory f
p requirements relative to the material identified in Condition S-4; provided the conditions and k
p tommitments contained in the licensee's November 30,1993, letter (identification # NRC 93-036) E E
g are satisfied.
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g SG-1.8 Notwithstanding the requwement of Section 6.2.1(a).5 of the licensee's Fundamental Nuclear g
Material Control Plan to unpackage and perform an item count upon receipt of special nucisar p
matenal, the licensee is exempted from such requirement relative to the material identified in F
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Condition S-4; provided the conditions and commitments contamed in the licensee's l-p November 30,1993, letter (identification # NRC-93-036) are satisfied.
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PAGE 5
or 8 mots y
g theme Number g
g SNM-1107 Amendment 9
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g MATERIAI,S LICENSE Docket or Reference Number g
l SUPPLEMENTARY SHEET 70-1151 g
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SAFEGUARDS CONDITIONS g
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SG-1.9 Notwithstanding the requirement of Section ll.A.7, block U, of NUREG/BR-0006, which is y
p incorporated via 10 CFR 74.15, to complete receiver's measurements of sxap receipts (following g
g recovery processing) within 60 days of receipt, the licensee shall not be subject to any time limit g
a relative to recovering and measuring received UF, heels when the block U action code (of g
g DODNRC Form 741) is used to book such receipts.
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GG-1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, " allowed number" g
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within the phrase "a# owed number of defects'is hereby specifed as being:
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N (i) up to two defects when each item within 6 batch of items has an assigned value equal to or g
y less than 50 grams U-235; c: [.
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(ii) no more than one defect when each item within a batch of items has an assigned value of g
g less than 500 grams U-235, but one or more items has an assigned value in excess of 50 grams g
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U-235; and 7
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(iii) zero defect when any item within a batch of items contains 500 or more grams U-235.
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SG-1.11 Notwithstandirsg the first paragraph of Section 7.1 of the Plan identified by Condition SG-1.1, the y
W licensee shall conduct shipper-receiver comparisons on all SNM materials received (regardless y
p of whether booked on the basis of receiver's or shipper's values), except for those materials g
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identified in Section 7.1 of NUREG-1065 (Rev. 2) as being exempted from shipper-receiver g
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comparisons.
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SECTION 2.0 - PHYSICAL PROTECTION OF SNM OF LOW STRATEGIC SIGNIFICANCE g
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SG 2.1 The licensee shall follow the " Site Physical Secunty Plan - Westinghouse Electric Corporation, g
g Columbia, S.C.; dated March 1980; Revision 10.0 dated October 1,11987; the " Revision Record" g
g contained in the, approved Physical Secunty Plan (current to Ociober 1,1994); and as may be g
g revised in accordance with the provisions of 10 CFR 70.32(e).
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SECTION 3.0 - INTERNATIONAL SAFEGUARDS g
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g SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility Attachment No. SA dated g
g August 31,1988, to the US/lAEA Safeguards Agreement. Such Transitional Facility Attachment y
g shall be interpreted in accordance with Conditions SG-3.1.1 through SG-3.1.7.
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g SG-3.1.1 With respect to Transitional Facility Attcchment Code 2:
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The reference design information is that dated by the licensee on October 14,1985. "Information g
g on the Facility" also includes other facility information submitted via Concise Notes in accordance y
g with 10 CFR 75.11(c).
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SNM-1107 Amendment 9 l
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MATERIALS LICENSE gegejerence Numter y
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SUPPt.EMENTARY SHEET l
l SAFEGUARDS CONDITIONS l
8 G 3.1.2 With respect to Transthonal Facility Attachment Code 2.2:
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Substantive changes to the information provxiod in the Columbia Plant Design informahon g
I Questionnaire (DlQ) means those changes requiring amendment of the Transitional Facility l
1 Attachmerd. Such changes shall be provided by letter to the NRC Office of Nucisar Material N
I Safety and Safeguards at least 70-days in advance of implementation.
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1
- Non-substantive changes to the information in the DlQ means those changes not requiring l
I amendment of the Transitional Facility Attachment. Such changes shall be provided by Concise W
I Note (From DOFJNRC 740M) within 30 days of receivmg notdication from the NRC that the -
l I
facility has been identified under Article 39(b) of the US/lAEA Safeguards Agreement l
b is required under 10 CFR 75.11, (to The types of modifications with're to I
be submitted in advance), are those items stated in Code 2.2, specificalty:
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(a) "Any change in'the purpose of type of facility" means:
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Any deviation from the described activities involving special nuclear material and any change to l
I the maximum cnrichmerd and/or quantities of U-235 currently authorized by License No. SNM-l N
1107, and/or as desenbod in Paragraph 5 of the Design Information Questionnaire (DlQ) dated N
N October 14,1985, or as modified in accordance with 10 CFR 75.11(c). included also is any 8
N deviation from the described special nuclear material (SNM) production activities described in l
N paragraph 6 of the D'Q dated October 14,1985, or as modified in accordance with 10 CFR N
N 75.11(c).
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N (b) "Any changes in the layout of the facility which affects safeguards implementation of the i
N provisions of the, Protocol" means:
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N Any changeln the existing facility ar%#or site layout or new addihon affecting any activity l
N involving SNM as described in Paragraphs 10 and 11 (per the referenced attachments of l
N the DlQ dated October 14,1985, or as modified in accordance 'with 10 CFR 75.11(c).
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I included also is any modification to, or deviation from, the data provided in Paragraphs 13 g
N and 14 (per the referenced attachments) of the OlQ dated October 14,1985, or as q
I modified in accordance with 10 CFR 75.11(c). y 5
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(c) "Any change that makes the selected Key Measurement Points (KMPs) (as described in l
N Code 3.1.2) inadequate for the Agency's accounhng purpose" means:
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Any change to the KMPs as described in Code 3.1.2 of the Westinghouse-Columbia l
N Transitional Facdoty Attachment to the US/lAEA Safegual. is Agreement, or as modified in l
N accordance with 10 CFR 75,11(c), that results in any KMP alteration affectog the purpose l
N of KMPs as stipulated by 10 CFR 75.4(m)
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N N
(d) "Any change in the physical inventory procedures that would adversely affect the inventory l
N taking for the Agencys accounting purposes" means:
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N Any change to the description data contained in Paragraph 34 (per the referenced l
I attachments) of the OlQ dated October 14,1985, or as mo4 fled in accordance with 10 CFR q
N 75.11(c), that would not permit the Agency to conclude an SNM material balance for the d
N Westinghouse-Columbia facility.
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ij FORM 374A
. U.S. NUCLEAR REOULAToRY Cotham PAGE 7
or 8
PAGES-Licerne Number g
l SNM-1107 Amendment 9 i
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MATERIALS LICENSE thirt or Reference Number i
1
$UPPt.EMENTAFW SHEET 70-1151 g
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SAFEGUARDS CONDITIONS l
I (e) " Introduction of a signmcenpy less accurate ana'ytical method for sooounting purposes" g
I means:
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l Any recalculation of the " Relative Enors-Random and Systematic" as listed in Attachment g.
I 38.2 referenced in Paragraph 36 of the DlQ dated October 14,1985, or as modilled in gl l
accordance with 10 CFR 75.11(c), that results in the estimates of the random and -
gi l
r,:::Tf: errors being affected by a factor of two or more, u,
11 g-l (f) "Docrease in the frequency of calibrating measuring equipment if it significantly decreases g
I the accuracy of the materials accounting system" means:
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Any change that results in the estimates of the 3,2:If: error being affected by a factor of g
p !W M t G- [1; g
i two or more.
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(g) "Any change in the statistical procedures used to combirie individual measurement error g
i estimates to obtain limits of error for shipper / receiver (S/R,) differences and material g
l unaccounted for (MUF)" means:
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e Any deviabon from (or moddication of) the equations and/or ch=hons g
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outlined in Attachments 37.1, 37.2, and 37.3 referenced in Paragraph 37 of g
I the DlQ dated October 14,1985, or as moddeed in accordance with 10 CFR g
l 75.11(c).
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SG-3.1.3 With respect to Transitional Facility Attachment Code 3,1.2:
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KMP* - This is a KMPMwhich all shipper receiver ddleren:es (SRDs).must be recorded and g
I reported even if numerically zero. SRDs are computed and reported by the Nuclear Materials y
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" 7,ep,T, erd and Safeguards System upon receipt of the receiver's measurement results, g
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SG-3.1.4 With respect to Transitional Facility Attachment Code 4:
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,s The licensee shall use the material compoedion codr.s documerYted in the DlO dated October 14, g
l l
1985, and as modified b Concise Notes. Further, notwithstanding any other requirements for g
I advance notWication and/or reporting, the licor. sos may add or delete ce.Tvesition codes for y
I nuclear material routmely processed and on inventory'st CFFF immediately upon telephone g
I notdication to the Office of Nuclear Material Sids4y and Safeguards Follow-up documentation, in g l
the form of a Concise Note accompensed by appropnate changes to Table 1 of Attachment 34.8 -
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to the DlQ shall be submitted w6 thin three regular workdays of the telephone notecahon.
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SG-3.t5 With respect to Transitional Facility Attachment Code 4.1:
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Measured discards should be reported as an SN (Shipment to non-safogaards facility) when g,
I shipped off-site to an authorized bunal ground (The IAEA system will not process measured g
I discards as loss / disposal (LDs) when they are shipped off-site).
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For inventory changes, time of recording, "upon" means: No later than the next regular workday g
y (Monday through Friday).
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For those occasions where natural or depleted uranium is inadvertently enriched above 0.711 y
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p percent through commingling with residual enriched uranium in process equipment, the resultant g
I product shall be considered as being produced through a blending operation and the material y
category change shall be recorded upon obtaining measurement confirmation that a material g
category change has occurred.
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SG-3.1.7 With respect to Transitional Facility Attachment Code 6.2.2:
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For Concise Notes describing the anticipated operational programme, " anticipated operational y
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programme" means: Anticipated physicalinventory schedule /,
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