ML20126M108
| ML20126M108 | |
| Person / Time | |
|---|---|
| Site: | Westinghouse |
| Issue date: | 04/15/1985 |
| From: | Brown W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20126L931 | List: |
| References | |
| NUDOCS 8508010233 | |
| Download: ML20126M108 (7) | |
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i UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE AMENDMENT FOR SPECIAL NUCLEAR MATERIAL SAFEGUARDS Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974, and Title 10, Code of Federal Regulations, Chapter 1, Part 70, the following amendme.it to the special nuclear material license identified below is hereby issued, incorporating specific safeguards requirements for special nuclear material.
Licensee:
Name:
Westinghouse Electric Corp.
License No.:
SNM-1107 Nuclear Fuel Division Safeguards Amendment:
SG-2 Address:
Drawer R Columbia, South Carolina 29205 Docket-No.:
70-1151 A Reissue of SG-1 in its entirety Date issued:
April 15,1985 CONDITIONS 1.0 FACILITY OPGANIZATION Currently there are no license conditions in this section.
The I
necessary infomation has been incorporated into an 6pproved plan.
2.0 FACILITY OPERATION 2.1 The licensee shall follow Chapters 1.0 through 8.0 and Appendices A, B, C, D, and AA of its Fundamental Nuclear Material Control Plan dated April 18,1984, except as noted in Condition 2.1.2 below; as revised by its submittals dated Seatember 1, 1984, and December 1, 1984; as amended by its submittal (#or Appendix AA) dated December 1,1984; and as may be revised in accordance with the provisions of 10 CFR 70.32(c). All revised pages associated with the above stated revisions are identified by, and are in accordance with, the
" Schedule of Revisions" as contained in pages ix through xiii (Revision 2 dated 12/1/84) of the Plan described above.
2.1.1 The licensee shall fullow Codes 2. throtagh 7., as applicable, of Transitional Facility Attachment No. 5 dated August 1,1983, to the l
Protocol of the US/IAEA Safeguards Agreement.
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Amendment No. SG-1 Docket No.
License No. SNM-1107 2.1.2 Limited exceptions for full compliance of the Plan identified in Condition 2.1 shall be in accordance with the schedule given in
" Addendum A" to the licensee's Plan submittal letter dated April 18, i
1984.
Dates for full compliance, by. Plan section numbers, are as j
specified in " Addendum A."
2.2 Operations involving special nuclear materials which are not referenced in the Plan identified in Condition 2.1 shall not be initiated until an appropriate safeguards plan has been approved by the Nuclear Regulatory Commission.
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2.3 All SNM not in transit shall be physically located within MBA-31, i
i 3.0 MEASUREMENTS j
3.1 Notwithstanding the requirement of 10 CFR 70.58(e) to measure all SNM receipts, the licensee may follow Sections 7.1.1, 7.1.2 and 7.1.3 of I
the Plan identified in Condition 2.1 for determining the receipt value of UF, uranyl nitrate solutions, sealed rods, and fuel assemblies.
6 3.2 Notwithstanding 10 CFR 70.58(e) which requires the quantities of element and isotope assigned to SNM to be measured values, the licensee
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may (1) determine the uranium content of baled waste, barrelled waste, l
incinerator ash, and laundry using the methcd described in Section 3.6 1
of the Plan identified in Condition 2.1, and (2) determine the U-235 i
content of liquid effluents by applying an average enrichment factor o the measured uranium element value.
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3.3 Notwithstanding the requirement of 10 CFR 70.57(b)(8)(1) to maintain traceability by calibrating measurement systems with reference standards, calibration of the laser flucrcaetric method, used for low level effluents from the Advanced Waste Water Treatment process, need not involve the use of calibrated (or certified) glassware with respect I
to cbtaining solution aliquots o.f the calibration standard, provided:
(1) at least one standard aliquot is measured each shift in which the l
methed is used and at least one standard is measured for each three i
unknowns, (2) a different pipet is used for each standard aliquot ar.d i
each unknown aliouot, and (3) the SNM quantity contained in AWWT i
effluents during the material balence pericd is less than 300 grams U-235.
3.4 Nctwithstanding the recuirement o' 10 CFR 70.58(e) which requires the i
measurement of all opened receipts, the licensee may determine the i
SNM quantity contained in a repaired, vender-supplied fuel rod in accordance with Section 7.1.3(b) of the Plan identified in Ccndition i
2.1, provided no more than five pellets are involved in the addition i
and/or removal of pellets from a given repaired red.
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Amendment No. SG-1 Docket No.
License No.
SNM-1107 4.0 MEASUREMENT CONTROL 4.1 Notwithstanding the requirements of 10 CFR 70.58(b)(8) to measure standards and replicates for volume systems, to not provide de minimis quantities for bias significance, bias corrections and error signific-ance, to determine separate random errors for sampling and analytical, to generate random errors for weight measurements from replicate weighing of process materials, and to perform replicate measurements for gaseous and service liquid effluents, the licensee shall follow Sections 4.2.2, 4.2.4, and 4.4.1 of the Plan identified in Condition 2.1.
4.2' Notwithstanding the requirements of 10 CFR 70.57(b)(4) to determine systematic sampling error and to conduct process and engineering tests on sampling systems for all material types, the licensee shall follow Section 4.3 of the Plan identified in Condition 2.1.
4.3 Notwithstanding the requirement of 10 CFR 70.57(b)(11) to establish and maintain control charts and control limits for all SNM accountability measurements, the licensee need not maintain control charts (or logs) and control limits for control standard measurements and/or replicate measurements in those cases where such measurements are shown as
" exempt" or "not necessary" in Figures 3.1, 3.2 and 3.3 of the Plan identified in Condition 2.1.
4.4 Notwithstanding 10 CFR 70.57(b)(11) which requires all control chart limits to be set at the 0.05 and 0.001 levels of significance, the licensee shall follow Section 4.5.2 of the Plan identified in Condi-tion 2.1, except as noted in Condition 4.4.1 below.
4.4.1 Notwithstanding Section 4.5.2(a).1 of the Plan identified in Condi-tion 2.1, the.05 and.001 control limits for scales may be replaced by fixed limits equal to two and three thes the scale discrimina-tion, respectfully, only if the standard deviation of the control standard data equals or exceeds 0.80 of t;,a applicable scale discrimi-nation. When the standard deviation of.9ntrol standard data is less than 0.80 of the applict.ble scale discri'nination, the 0.05 and.001 limits may be. replaced by fixed limits equal to one and two times the scale discrimination, respectfully.
4.5 Notwithstanding the reouirement of 10 CFr. 70.57(b)(8) to measure control standards for all measurements systems for the purpose of determining) bias, and notwithstanding the requirement of 10 CFR 70.57(b)(ll to maintain a statistical control system to monitor such control standard measurements, the licensee need not measure nor monitor such control standards for point calibrated, bias-free, systems.
To be regarded as bias-free, a measurement system must either (1) be calibrated (by one or more measurements of e represen-tative standard) at least once during any eight-hour time frame in
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Amendment No. SG-1 Docket No.
License No.
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which process unknowns are measured, and the measurement'+alue assigned to a given unknown must either be based on the single most recent calibration or the average of two or more calibrations performed during such eight-hour time frame, or (2) incorporate a bias correction into the measurement response for each process unknown measured (at the time of measerement) where such bias correcticr is based upon tbepverage of the eight (or more) most recent measurements of a representative standard pyrfremed within the past 14 calendar days.-- at least one of which wts performed withinthepasteighthours./
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When utilizing the approach'given in (2) abov'e @[ Nich can only be
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applied in the case of mass or NDA systems), ea:h bias correction must be calculited to the nearest.01 gram (gross weight, tare weight, or grams U-235 as appropriate) and
- applied to an iteta before rounding tbe item's value to its nearest accounting unit (e.g., the nearest tentn of a gr'am for fuel rods).
Notwithstanding the requirement of 10 CFR 70.57.b)(iQ which prohibits l
4.6 measurements performed during the or.-of-i.ontro,l tituation from being used for accounting purposes, the Heensee shall Dolltw Section 4.5.3 of the Phn identified in Condition 2.1.
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N twith y.anding herecuirementof10CFR70.\\7(b)(S'/1 to base all 4.7 measurement syMam calibrations on reference standar$s,)cthe licensee may (1) derive ' gaseous effluent volumes from farr4 peed calculations, and (2) derive bulk volene measurements from caHhratiens based on dimensional relatio,nships. l
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3 4.8 Notwithstanding the requ.remait df 10 CFR 70.57(I-)(d) to perform sampling engineering tests sampling, the licensee ned, r>i O' measurement sysyms involving ict verify the representativeness of gaseous effluent sampling.
- I 4.9 t,otwitnstanding the requirement of 10 CFR 70.57(b)(8) to detennine bias corrections for all measurement systems, the licensee need not calculate, nor apply, bias /t,rrections fpr those meaturement systems that are utilized to measur'e less than 3t'0 crams uranium, or less than
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10 grams U-235, during an inventcry pered, provided'the to'tal of all such exemot systems measurrJ'less than 3000 grams uranium and less than 100 grams U-235 during the' inventory period.
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4.10 The licensee shall regard the uncertainty asso;;iated wf 6 an average "MA0" (ght value, as determined by either measurement systa "M-7" cr tare we.i as described in Section 3.2 andfigure 3.1'c' the P7an identi-fpdinCondition2.1)assystematicerrge.
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'e Amendment No. SG-1 Docket No.
License No.
SNf t-1107 4.11 Notwithstanding the requirements of 10 CFR 70'.57(b)(11) to establish 3
and maintain both.05 and.001 control limits for replicate measure-ments, and not to use for accounting purposes any measurements gene-rated from a system during a replicate related out-of-control condition, the licensee shall follow Sections 4.5.2(b).1, 4.5.3(c).1, (c).2 and (c).3 of the Plan identified in Condition 2.1.
5.0 INVENTORY 5.1 Notwithstanding 10 CFR 70.51(e)(3)(ii) which requires low enriched uranium physical inventories to be conducted at intervals not to exceed six calendar months, the licensee shall follow Section 5.1.3 of the Plan identified in Condition 2.1.
5.2 Notwithstanding 10 CFR 70.51(f)(1)(i) which requires a measured value for each item on inventory, the licensee shall follow Section 5.2.2(a) of the Plan identified in Condition 2.1, with respect to determining j
equipment hold-up quantities.
5.3 Notwithstanding the requirement of 10 CFR'70.51(e)(4)(1) to calculate the limit of error for all SNM contained in " material in process", the licensee need not calculate the limit of error.on the SNM contained in samples, standards, and other minor material categories provided the total SMM content of such materials, which could affect ID or LEID, is I
less than 10 kilograms uranium and less than 300 grams U-235.
5.4 Notwithstanding the requirements of 10 CFR 70.51(e)(4)(1) to calculate LEID (or LEMUF) values within 30 days following each ending inventory date, and 10 CFR 70.53(b) to submit any reports that may be required 4
i by 70.53(b)(1), or (b)(2) within 30 days following the associated ending inventory date, the licensee shall:
i (1) Calculate uranium element and U-235 LEID values for each physical inventory within 40 calendar days following the inventory date. -
and (2)
Submit any) report required by either 10 CFR 70.53(b)(1) or 70.53(b)(2 within 50 calendar days, following the date of a physical inventory.
5.5 Notwithstanding requirements contained in 10 CFR 70.51(d), (e)(2), and (f), waste discards (both solid and liquid) stored within MBA-31 need not be included in physical inventory listings, nor subject to other inventory requirements, provided such waste has been transferred (accountability-wise via DOE /NRC Form 741) to an official Plant holding account.
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O Amendment No. SG-1 Decket No.
License No.
SNM-1107 5.6 Notwithstanding the requirements of 10 CFR 70.51(e)(4)(1) to calculate the limit of error for all SNM contained in " material in process," the licensee may exclude from LEID calculations systematic errors and random errors contributing less than.100 grams U-235 each to the LEID, up to a total contribution of 1000 grams U-235.
However, this condi-exceed the 100 and/or 1000 gram limits (g the licensee to actuallyspecified abo tion is not to be interpreted as allowin beforehand that such limits would be met.
Notwithstanding)the requirements of 10 CFR 70.51(f)(1)(1) and 10 CFR -
5.7 70.51(f)(2)(iii which require the quantity of SNM associated with each item on inventory be a measured value, and the reverification of identity and quantity of contained SNM for each item not tamper-safe sealed at~ the time of physical inventory, the licensee may follow the procedure contained in " Appendix A" of his letter dated October 17, 1984 (LA 84-101), with regard to inventorying stored samples.
6.0 RECORDS AND REPORTS
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6.1 In lieu cf the requirements contained in 10 CFR 70.53(a)(1) and (a)(2) to use the Forms DOE /NRC-742 and 742C, the licensee may use computer generated forms provided all information required by the latest printed instructions for completing the particular from is included.
6.2 In lieu cf the requirements contained in CFR 70.54 to use the DOE /NRC Form 741, the licensee may use computer generated forms provided all information required by~the latest printed instructions for completing i
the particular form is included.
7.0 INTERNAL CONTROL 7.1 Notwithstanding 10 CFR 70.58(h) which requires storage and internal controls for all SNM contained in discrete items and containers, the licensee shall follow Section 7.2.1 of the Plan identified in Condition 2.1.
7.2 Notwithstanding the requirement of 10 CFR 70.51(f)(2)(iii) to verify the identity and SNM ouantity of each item inventoried whose tamper-safing is found to have been compromiseo, the licensee may fullow Section 7.2.1(b).6 of the Plan identified in Condition 2.1.
8.u PANAGEMENT Currently there are no license conditions in this section.
The necessary information has been incorporated into an approved plan.
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Amendment No. SG-1 Docket No.
License No. SNM-1107 9.0 FIXED SITE AND IN-TRANSIT PHYSICAL PROTECTION REQUIREMENTS FOR SPECIAL NUCLEAR MATERIAL 0F LOW STRATEGIC SIGNIFICANCE 9.1 The licensee shall maintain and fully implement all provisions of the approved security plan titled, " Site Physical Security Plan, Westinghouse Electric Corporation, Columbia, S.C.," dated March 1980; as amended by letters dated September 2, 1980, April 9, 1981, January 25, September 1, and December 1,1984, and March 1,1985; and as may be revised in accordance with the provisions of 10 CFR 70.32(e).
For the Nuclear Regulatory Commission tica& 6.P-Willard B. Brown, Chief Fuel Facility SG Licensing Branch Division of Safeguards, HMSS Cate of Amendment:
April 15, 1985
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