ML20137G064
| ML20137G064 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 03/27/1997 |
| From: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20137G022 | List: |
| References | |
| NUDOCS 9704010304 | |
| Download: ML20137G064 (9) | |
Text
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^ 3 U.S. NUCt. EAR REGULATORY COMMISSION 9,
I MATERIALS LICENSE 2:
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j Pursuant to the Atomic Energy Act of 1954, as amended, the Enetp> Reorgani/ation Act of 1974 iPubbe Law 93 43M. and Title 10. Code of Q l t ! Federal Regulations. Chapter 1. Parts 30. 31. 32. 31. 34. 35. 36. 39. 40. and 70. and in reliance on statements and representations heretofore made $l C
h bs he licensee, a license is hereby iwued authori/ing the licensee to receise. A pm eu and transfer by product, source. and special nuclear
(( material de ignated below: 10 use such material f or the purposeN and at the placeN designated below; to deiner or transfer such material to $
l persons authorved to receise it in accordance with the regulanons of the applicable PartN. This been e shall be deemed to contain the conditio
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j 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 ettect and to any conditions specified below.
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Licensee E l 1.
Westinghouse Electric Corporation
- 3. License Number SNM-Il07 Amendment 4 i
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P.O. Box 355
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Pittsburgh, Pennsylvania 15230-0355 s
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- 4. Expiration Date November 30, 2005 s :
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- 5. Docket or 70-1151 G1 l
Reference No.
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- 6. ' Byproduct. Source, and/or
- 7. Chemical and/or Physical
- 8. Maximum Amount that Licensee (l
i Special Nuclear Material Form May Possess at Any One Time s,
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A.
U-235 A.
Any A.
0.35 kg
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U-235 B.
Any, except B.
75,000 kgs l
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to not more g-I' than 5.0 w/o 43 C.
U-233 C.
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Pu-238, D.
Sealed sources D.
1.5 grams 4:
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9.
Authorized place of use: The licensee's existing facilities at Columbia, South (i
1 al Carolina.
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This license shall be deemed to contain two sections:
Safety Conditions and Ql l&
Safeguards Conditions. These sections are part of the license and the licensee is 7l lh subject to compliance with all listed conditions in each section.
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FOR THE NUCLEAR REGULATORY COMMISSION
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1 Date:
3 27 D By: Michael F. Weber O
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Division of Fuel Cycle Safety yl I
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Washington, DC 20555 Ij b1 i
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g gI License Number
_ g SNM-1107 Amendment 4 El g
p MATERIALS LICENSE omei or nererence Number g
g SUPPLEMENTARY SHEET 70-1151 gj E'
N SAFETY CONDITIONS fEi y
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SAFETY CONDITIONS N
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S-1 Authorized use:
For use in accordance with statements, representations, and E
I conditions in the license application' dated April 30, 1995, and supplements E
I dated May 11, 18; August 4, 25; and September 25, 1995.
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E' N
S-2.
The Criticality Safety Evaluations (CSEs) and Criticality Safety Analysis E
y (CSAs) will define the criticality safety bases utilized throughout the plant E
W and will be completed as described in Sections 6.4.1 and 6.4.2 of the license E
i application for each step of the process. 'A' submittal to the NRC will be gl g
made by Westinghouse.which will include information which the staff will i!
g review against the comitments listed in Section-6.2.3 of the license p
g application. These submittals will not be specific comitments, but are E!
y intended as a demonstration of the adequacy of the bases of safety itemized E
g in Section 6.2.3.
The contents listed in Section 6.4.2 of the license gi y
application are commitments. The demonstration will show the logic used by g'
the Columbia Fuel Fabrication Facility (CFFF) in developing the criticality y
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safety bases.
It is understood that this demonstration may change over time.
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The submittal will consist of a sumary of the CSE or CSA as annotated below g!
for each system (which shall include fault trees for those systems for which g
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a CSE will be done). The adequacy of the comitments in Section 6.2.3 of the E
license application will be evaluated and a reply in the form of a letter g
y report will be generated and sent from the staff to Westinghouse. The y
submittal by the CFFF will be provided according to the following schedule:
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UN tanks - summary of CSE -10/95 l
3 URR!, Dissolver - sumary of CSE - 10/95 5
Solvent Extraction - sumary of CSE - TBD*
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URR!. Scrap Processing:
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Low-level Waste Processing System - summary of CSA - 9/96 5
Hop Water System Equipment - summary of CSA - 9/96 5
Incinerator System - sumary of CSE - 9/96 I
5 Ash Recovery System - summary of CSE - 9/96 5
Liquid Honing System - summary of CSE - 9/96 I
5 Ultrasonic Cleaning System - sumary of CSE - 9/96 I
5 Shredder System - sumary of CSE - 9/96 I
5 URRS Waste Treatment - summary of CSA - 11/95 I
5 IDR Conversion - summary of CSE - Prior to Restart I
B ADU Conversion - summary of CSE - 4/96 I
N ADU Pelleting - sumary of CSE - 6/n6 I
N Powder Blending - summary of CSE - 1/96 I
B.
Miscellarmous:
I N
Ventilation Systems (Geometry Controlled) -
I N-sumary of CSE - 12/97**
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MATERIALS LICENSE Docket or Reference Number j
g SUPPLEMENTARY SHEET 70-1151 i
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SAFETY CONDITIONS p
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N Ventilation Systems (Moderation Controlled) -
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W sumary of CSE - 12/97**
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i Scrubber Systems - sumary of CSE - 12/97**
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Hoods & Containment - summary of CSA - 9/96 E
p Laboratories - sumary of CSA - 9/96 g
IFBA - summary of CSA - 3/96 i;
g Storage Pad - NCS is based on DOE reports K-1920 and K-1663 E
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Rods - sumary of CSA - 3/96 E
W Storage - summary of CSE - 4/97 g i g
Final Assembly. - sumary of CSE - 6/97 g
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UF, Cylinder Washing - summary of CSE - 12/95 E :
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- The CFFF has performed a CSA upgrade and does not have a specific date for g
g schedule of this CSE at this time.
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- These systems are to be coupled with the Columbia Plant Risk Management Program l
p (RMP) to be done for the EPA.
y ljl S-3 The licensee shall maintain and execute the response measures in the Site Emergency Plan, dated April 30, 1990, and revisions dated March 31, and September 30, 1992; E
y March 25, August 15, and September 30, 1994; January 9, February 17, August 17, and g
October 23, 1995; or as further revised by the licensee consistent with y
y N
I S-4 Notwithstanding the requirements of 10 CFR 20.205(b) to monitor the external I
N surfaces of packaged radioactive material receipts for radioactive contamination, i
N the licensee is exempted from such requirement relative to flatbed trailer I
N shipments of fuel assemblies received from the General Electric Company for interim i
N storage purposes only, provided the constreints, conditions and controls committed E
E to in the licensee's letter, dated November 30, 1993, (identification # NRC N 036), are satisfied; and further provided that the total number of such fuel
.E N
assemblies stored at the licensee's site at any given time does not exceed 250.
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OF 9
PAGES E
Lkense Number E
, g SNM-1107 Amendment 4 g
y g
MATERIALS LICENSE oockes or sererence Number
.[
g SUPPLEMENTARY SHEET 70-1151 g
!l l
I, SAFEGUARDS CONDITIONS N
N E
N
!E N
SAFEGUARDS CONDITIONS
's N
E N
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SECTION 1.0 -- MATERIAL CONTROL AND ACCOUNTING g
W E
W SG-1.1 The licensee shall follow Chapters 1.0 through 9.0 of its " Fundamental y
y Nuclear Material Control Plan for the Coiumbia Fuel Fabrication Facility,"
E g
with all pages identified as "Rev. No. 25.0" and dated "07AUG96." This Plan E
y may be revised in accordance with, and pursuant to, either 10 CFR 70.32(c) or g
g 70.34.
g N
E y
SG-1.2 Operations involving special nuclear materials which are not referenced in y
the Plan identified in Condition SG-1.1 shall not be initiated until an y
y y
appropriate safeguards plan has been approved by the Nuclear Regulatory g
Commission.
g E
SG-1.3 In lieu of the requirenants contained in 10 CFR 74.13(a)(1) and (a)(2) to use l
l the Forms DOE /NRC-742 and 742C, the licensee may use computer generated forms g
9 provided all information required by the latest printed instructions for g
y completing the particular form is included.
SG-1.4 In lieu of the requirements contained in CFR 70.54 and 74.15 to use the l!
l DOE /NRC Form-741, the licensee may use computer generated forms provided all
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information required by the latest printed instructions for completing the particular form is included.
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N SG-1.5 Deleted Per Amendment 3, Augoic 1996 --- Commitment now contained in E
licensee's Fundamental Nuclear Material Control Plan.
I l, 5
E1 I'
N SG-1.6 Notwithstanding the requirements of the FNMC Plan identified in License E
N Condition SG-1.1, the licensee may use a single standard for measurement N
control (including daily control limit monitoring and bias corrections) for 8l E
N any linear-response tube or rod scales, in any initially demonstrated to be i
N linear over its range of'use within the discrimination of the scale by E'
N calculating a bias at four levels across the range of use and demonstrating N
that the four results are not statistically different. and (2) that the E
N continued linearity of response of the scales is verdied by monthly E
i' N
calibration against at least four traceable standards covering the range of j
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use.
E N
N SG-1.7 Notwithstanding the requirements contained in Sections 5.2.2 and 5.2.3 of the E
N licensee's Fundamental Nuclear Material Control Plan, the licensee is E
N exempted from physical inventory requirements relative to the material E
N identified in Condition S-4; provided the conditions and commitments jE N
contained in the licensee's November 30, 1993, letter (identification # NRC-lE
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93-036) are satisfied.
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PAGES g
g License Number g
g SNM-1107 Amendment 4 g
N MATERIALS LICENSE Docket or Reference Number l
g SUPPLEMENTARY SHEET 70-1151 g
j SAFEGUARDS CONDITIONS N
i N
SG-1.8 Notwithstanding the requirement of Section 6.2.1(a).5 of the licensee's i
N Fundamental Nuclear Material Control Plan to unpackage and perform an item i
N count upon receipt of special nuclear material, the licensee is exempted from i
N such requirement relative to the material identified in Condition S-4; i
MI provided the conditions and commitments contained in the licensee's E
November 30, 1993, letter (identification # NRC-93-036) are satisfied.
E E
p SG-1.9 Notwithstanding the requirement of Section II.A.7, block U, of NUREG/BR-0006, E
N which is incorporated via 10 CFR 74.15, to complete receiver's neasurements E
W of scrap receipts (following recovery processing) within 60 days of receipt, E
N the licensee shall not be' subject to any time limit relative to recovering E
p and measuring received UF, heels when the block U action code (of DOE /NRC E
g Form 741) is used'to book such receipts.
E N
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SG-1.10 With respect to Section 5.1.4 (b) of the Plan identified by Condition SG-1.1, E
g
" allowed number" within the phrase " allowed number of defects" is hereby p
g specified as being:
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(i) up to two defects when each item within a batch of items has an assigned 5
g value equal to or less than 50 grams U-235; E
N E
y (ii) no more than one defect when each item within a batch of items has an g
g assigned value of less than 500 grams U-235, but one or more items has an y
assigned value in excess of 50 grams U-235; and j
l (iii) zero defect when any item within a batch of items ~contains 500 or more l
g grams U-235.
SG-1.11 Notwithstanding the first paragraph of Section 7.1 of the Plan identified by l
l Condition SG-1.1, the licensee shall conduct shipper-receiver comparisons on all SNM materials received (regardless of whether booked on the basis of l
receiver's or shipper's values), except for those materials identified in Section 7.1 of NUREG-1065 (Rev. 2) as being exempted from shipper-receiver g
comparisons.
g l
SECTION 2.0 -- PHYSICAL PROTECTION 0F SNM 0F LOW STRATEGIC SIGNIFICANCE E
N SG-2.1 The licensee shall follow the " Site Physical Security Plan - Westinghouse N
Electric Corporation, Columbia, S.C.." dated March 1980; Revision 10.0 dated jE N
October 1, 1987; the " Revision Record" contained in the approved Physical lE E
N Security Plan (current to October 1, 1994); and as may be revised in
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accordance with the provisions of 10 CFR 70.32(e).
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RAGES Ig License Number lg
~
SNM-1107 Amendment 4 g
y y
MATERIALS LICENSE oncket or Reference Number
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SUPPLEMENTARY SHEET 70-1151 g
l SAFEGUARDS CONDITIONS f
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3
,E I 3
y SECTION 3.0 -- INTERNATIONAL SAFEGUARDS g
3 Ei g
SG-3.1 The licensee shall follow Codes 1 through 6 of Transitional Facility E
g Attachment No. 5A dated August 31, 1988, to the US/IAEA Safeguards Agreement.
g 3
Such Transitional Facility Attachment shall be interpreted in accordance with 8
3 Conditions SG-3.1.1 through SG-3.1.7.
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SG-3.1.1 With respect to Transitional Facility Attachment Code 2:
El M
E 3
E' The reference design information is that dated by the licensee on October 14, g!
y 1985.
"Information on the Facility" also includes other facility information gl g
submitted via Concise Notes in accordance with 10 CFR 75.11(c).
g 3
SG-3.1.2 With respect to Transitional Facility Attachment Code 2.2:
l E
l Substantive changes to the information provided in the Columbia Plant Design Information Questionnaire (DIQ) means those changes requiring amendment of the Transitional Facility Attachment.
Such changes shall be provided by
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g; g
letter to the NRC Office of Nuclear Material Safety and Safeguards at least I, l y
70-days in advance of implementation.
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5 Non-substantive changes to the information provided in the DIQ means those 5
changos not requiring amendment of the Transitional Facility Attachment.
l Such changes shall be provided by Concise Note (Form DOE /NRC-740M) as part of the routine quarterly update of the DIQ, i
3j The types of modifications with respect to which information is required jf 3l under 10 CFR 75.11, (to be submitted in advance), are those items e ed in i
3j Code 2.2, specifically:
3 lE 3
(a)
"Any change in the purpose of type of facility" means:
if
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i 3'
Any deviation from the described activities involving special nuclear i
3 material and any change to the maximum enrichment and/or quantities of j
3 U-235 currently authorized by License No. SNM-1107, and/or as described li 3;j in "Iragraph 5 of the Design Information Questionnaire (DIQ) dated ti 3j October 14, 1985, or as modified in accordance with 10 CFR 75.11(c).
3l Included also is any deviation from the described special nuclear i
3 material (SNM) production activities described in paragraph 6 of the 1
3 DIQ dated October 14, 1985, or as modified in accordance with 10 CFR E
I 75.11(c).
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3 3
(b)
"Any changes in the layout of the facility which affects safeguards i
l; implementation of the provisions of the Protocol" means:
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PAGES g
g License Number g
g SNM-1107 Amendment 4 g
y fg p
MATERIALS LICENSE Docket or Reference Number y
SUPPLEMENTARY SHEET.
70-1151 I
g SAFEGUARDS CONDITIONS b
N N
N Any change in the existing facility and/or site layout or new addition l
N affecting any activity involving SNM as described in Paragraph 10 and El N
11 (per the referenced attachments of the DIQ dated October 14, 1985, E I I
or as modified in accordance with 10 CFR 75.11(c).
Included also is Ei I
any. modification to, or deviation from, the data provided in Paragraph E1 i
N 13 and 14 (per the referenced attachments) of the DIQ dated October 14, E
b 1985, or as modified in accordance with 10 CFR 75.11(c).
E 1
E W
(c)
"Any change that makes the selected Key Measurement Points (KMPs) (as p
p' described in Code;3.1'2) inadequate for the Agency's accounting E
g p
purpose" means:
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N p
Any change to the KMPs as described in Code 3"1.2 of the Westinghouse-El g
Columbia Jransitional Facility Attachment to the US/IAEA Safeguards El I
g Agreement, or as modified in accordance with 10 CFR 75.11(c), that g
y results in any KMP alteration affecting the purpose of KMPt as g
g stipulated by 10 CFR 75.4(m)
E N
E1 y
(d)
"Any change in the physical inventory procedures that would adversely y;
4 affect the inventory taking for the Agency's accounting purposes" gj y
means:
gl g
l Any change to the description data contained in Paragraph 34 (per the l
referenced attachments) of the DIQ dated October 14, 1985, or as g
modified in accordance with 10 CFR 75.11(c), that would not permit the y
Agency to conclude an SNM material balance for the Westinghouse-y Columbia facility.
,l y
i N
(e)
" Introduction of a significantly less accurate analytical method for l
accounting purposes" means:
ll 4
i N
Any recalculation of the " Relative Errors-Random and Systematic" as E
N listed in Attachment 36.2 referenced in Paragraph 36 of the DIQ dated 8
October 14, 1985, or as modified in accordance with 10 CFR 75.11(c),
E,i il N
that results in the estimates of the random and systematic errors being affected by a factor of two or more.
l i
N.
(f)
" Decrease in the frequency of calibrating measuring equipment if it i,
E significantly decreases the accuracy of the materials accounting I
N system" means:
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Any change that results in the estimates of the systematic error being E i N'
affected by a factor of two or more.
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PAGES lj g
i License Number g
g SNM-1107 Amendment 4 g
y g
MATERIALS LICENSE Docket or Reference Number g
g SUPPLEMENTARY SHEET 70-1151 l
SAFEGUARDS CONDITIONS N
E1 N
E N
E, N
(g)
"Any change in the statistical procedures used to combine individual E
N measurement error estimates to obtain limits of error for-E N
shipper / receiver (S/R) differences and material unaccounted for (MUF)"
E W
means:
E N
E N
Any deviation from'(or modification of) the equations and/or
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calculations outlined in Attachments 37.1, 37.2, and 37.3 referenced in E1 g
Paragraph 37 of the DIQ dated October 14, 1985, or as modified in W
accordance with 10 CFR 75.11(c).
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SG-3.1.3 With respect to Transitional Facility Attachment Code 3.1.2:
gl N
E' g
KMP* -- This is a KMP in which all shipper receiver differences (SRDs) must EI l
g be recorded and reported even if numerically zero.
SRDs are computed and E
g reported by the Nuclear Materials Management and Safeguards System upon l
g receipt of the receiver's measurement results.
E' SG-3.1.4 With respect to Transitional Facility Attachment Code 4:
ll l
The licensee shall use the material composition codes documented in the DIQ y,
g dated October 14, 1985, and as modified by Concise Notes. Further, E
y notwithstanding any other requirements for advance notification and/or g
y reporting, the licensee may add or delete composition codes for nuclear g
material routinely processed and on inventory at CFFF immediately upon g
y telephone notification to the Office of Nuclear Material Safety and
,4 y
Safeguards.
Follow-up documentation, in the form of a Concise Note E
accompanied by appropriate changes to Table 1 of Attachment 34.8 to the DIQ I
U shall be submitted within three regular workdays of the telephone I
notification.
i s
E SG-3.1.5 With respect to Transitional Facility Attachment Code 4.1:
E U
Measured discards should be reported as an SN (Shipment to non-safeguards E
N facility) when shipped off-site to an authorized burial ground.
(The IAEA E
E system will not process measured discards as loss / disposal (LDs) when they E
5 are shipped off-site).
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MATERIALS LICENSE Dockt or Reference Number g
g SUPPLEMENTARY SHEET 70-1151 g
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SAFEGUARDS CONDITIONS E
g, II lE Nj E
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N SG-3.1.6 With respect to Transitional Facility Attachment Code 5.1.1:
E N
E N
For inventory changes, time of recording, "upon" means: No later than the E
W next regular workday (Monday through Friday).
E N
E N
For those occasions where natural or depleted uranium is inadvertently E
R enriched above 0.711 percent througn i.ommingling with residual enriched E
N uranium in process equipment, the resultant product shall be considered as E ;
W being produced through a blending operation and the material category change g
W shall be recorded upon obtaining measurement confirmation that a material y
g category change has occurred.
E E
y SG-3.1.7 With respect to Transitional Facility Attachment Code 6.2.2:
y N
E y
For Concise Notes describing the anticipated operational programme, E
y
" anticipated operational programme" means: Anticipated physical inventory g
4 y
schedule.
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