ML19282B542
| ML19282B542 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 02/21/1979 |
| From: | Partlow J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Nilson R SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| References | |
| NUDOCS 7903150324 | |
| Download: ML19282B542 (6) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMisslON 3
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9 WA9HNGTON, D. C. 20555
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FEB 2 ' 1979
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SGMC:DRJ 70-1257 Exxon Nuclear Company, Inc.
ATTN:
Dr. R. Nilson, Manager Lic<nsing 2955 George Washington Way Richland, Washington 99352 Gentlemen:
We have reviewed and accepted the revised measurement control plan submitted with your letter of June 5,1978 and the revisions attached to your letter of June 19, 1978, all of which were submitted pursuant to 10 CFR 70.57(c) and to our request dated November 17, 1977.
Although we are approving your measurement c,..irol plan, we have determined that the degree of standards verification (power of the test) is not adequately described in Section 4.2.1.2 of your Plan.
The values assigned to reference standards involved in your measure-ment systems should be verified to an extent that minimizr s the potential undetected bias associated with che material unaccounted for (MUF) quantity.
Therefore, we request that you submit, within two months of the date of this let.ter, an assessment of the potential magnitude of MUF bias due to the degree of verification that you currently perform on each reference standard.
Please feel free to contact us if additional assistance or guidance is necessary.
In order to incorporate your measurement control program as a condition of license, and te withdraw obsolete conditions and to clarify certain existing conditions, Sections 1.0 through 8.0 of Amendment No. MPP-2 to Special Nuclear Material License No. SNM-1227 are hereby revised in their entirety at set forth in the enclosure to this letter, to be implemented 30 days after the date of this letter.
It should also be noted that your request of March 2,1977 asliing for clarification of License Condition 4.5 has been resolved by your revised measurement control program.
7903150S2f'
. We have determined that your initial and revised measurement control plans of November 6,1975 and June 5,1978, the revisions of June 19, 1978 to said plan, and your letter of March 2,1977 all contain information of a type specified in 10 CFR 2.790(d). Accordingly, pursuant to Section 2.790(d)(1), such information is deemed to be commercial or financial information within the meaning of 10 CFR 9.5(a)(4) and shall be subject to disclosure only in accordance with the provisions of 10 CFR 9.12.
Sincerel
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Jam as G. Partlow, Chief Mat arial Control Licensing Branch Div,ision of Safeguards
Enclosure:
Amendment to MPP-2 e
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Enclosure Revision of Sections 1.0 Through 8.0 In Their Entirety To Materials and Plant Protection Amendment MPP-2 To License No. SNM-1227 Effective March 21, 1979 1.0 FACILITY ORGANIZATION Currently, no conditions in this section. All appropriate requirements have been incorporated in an approved plan.
2.0 FACILITY OPERATION 2.1 The licensee shall follow Sections 1.0 through 8.0 of the fundamental nuclear material control plan titled, " Nuclear Material Safeguards Procedures Descri,ntion for the Fuels Fabrication Plants," XN-12, Rev. 5, dated February 1977; as amended May 20, 1977 (pages dated April 1977, Rev. 5), October 17,1977 (pages dated September 1977, Rev. 6), and June 1, 1978 (pages dated July 1978, Rev. 8); and as revised June 5,1978 and amended June 19, 1978 (pages dated June 1978, Rev. 7); and as may be revised or amended in accordance with the provisions of 10 CFR 70.32(c).
2.2 No statement in the licensee's Plan identified in Condition 2.1 shall relieve the licensee of a requirement of 10 CFR Part 70 unless granted in a specific exemption or exception set forth as a condition of this license.
2.3 Operations involving special nuclear naterials which are not described in the Plan identified in Condition 2.1 shall not be initiated until an appropriate safeguards plan has been approved by the Nuclear Regulatory Comission.
2.4 All SNM not in transit shall be physically within an MBA or an ICA.
2.5 The custody of all special nuclear material within each MBA and ICA shall be the responsibility of a single designated individual. Each MBA shall have a different custodian and no individual shall be the custodian of a MBA and an ICA with the exception that one individual may be the custodian of MBA-4, ICA-4 and ICA-5 while the plutonium.
plant is in shutdown status.
2.6 The input to the uranium scrap recovery process shall consist only of material generated from in-house processes.
3.0 MEASUREMENTS 3.1 The licensee or his designated agent shall measure, except as specified in 10 CFR 70.58(e), the uranium, plutonium, and U-235 content of all special nuclear material receipts,ial inventoried; shipments, waste discards, internal transfers from MBAs, and mater and the isotopic content of offsite plutonium receipts and shipments.
Amendment No. MPP-2 Page 2 of 4 Docket No. 70-1257 License No. SNM-1227 3.2 Each fuel rod shall be nondestructively scanned to verify the presence of the assigned SNM content. Appropriate standards and quality assurance programs shall be maintaired to assure the continuing reliability of the overcheck measureraents.
4.0 MEASUREMENT CONTROL 4.1 All identifiable covariance effects shall be taken into account in the calculation of LEID (LEMUF).
4.2 Notwithstanding the requirement of 10 CFR 70.57(b)(4) to provide sampling systematic errors and to conduct engineering tests on all material types, the licensee shall follow Section 4.3.1 of the Plan identified in Condition 2.1.
4.3 Notwithstanding the requirements of 10 CFR 70.57(b)(8) to run standards and replicates for. volume systems, to generate bulk and NDA random errors from process materials, to perform analysis on replicate waste stream samples, and to require separate random errors for sampling and analytical on all sampling systems, the licensee shall follow Sections 4.2.2 and 4.4.1 of the Plan identified in Condition 2.1.
4.4 Notwithstanding the requirement of 10 CFR 70.57(b)(10) to calculate and make bias corrections relative to all measurement systems, the licensee shall follow Section 4.2.4.1 of the Plan identified in Condition 2.1 and also need not make bias corrections on volume measurements.
4.5 Notwithstanding the requirement of 10 CFR 70.57(b)(8)(i) to maintain an ongoing use of standards for calibration, the licensee shall follow Section 4.2.3.2.1 of the Plan identified in Condition 2.1,
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to liquid waste tank volume calibrations.
4.6 Notwithstanding the requirement of 10 CFR 70.57(b)(ll) to establish and maintain control charts for mass standards measurement data and replicate NDA measurement data, the licensee shall follow Sections 4.5.1.2.1 and 4.5.1.2.2 of the Plan identified in Condition 2.1.
5.0 INVENTORY 5.1 For low enriched uranium, the book value based on measurements for an inventory item may be used for physical inventory, if the inventory verification measurement compared with item value does not exceed the larger of 25 grams or 0.1 percera relative for weight, 0.5 percent relative for element, and 3.0 percent relative for isotope.
Amendment No. MPP-2 Page 3 of 4 Docket No. 70-1257 License No. SNM-1227 5.2 All plutonium stored in the tamper-safed vault may be inventoried on the basis of prior list.ing after verification of the integrity of tamper-indicating seals identified in Condition 9.3.7.
6.0 RECORDS AND REPORTS 6.1 The licensee shall use his or his designated agent's measured values, for SNM accounting except as specified in Conditions 3.1, 6.5, and 6.6.
6.2 The licensee shall report on a monthly basis all intentional discards and material unaccounted for.
The MUF shall be that which has been determined during the month as a result of completing a material balance around a single operation, a number of operations, or the entire plant.
This report shall be made within fifteen (15) days after the end of the month in which the discard was made or the material unaccounted for was determined. Reports shall be sent to the Regional Office of the Nuclear Regulatory Conmission.
6.3 All bias calculations and bias adjusted ID (MUF) values shall be maintained as part of the records required by 10 CFR 70.57(b)(12).
6.4 In lieu of the requirement in 10 CFR 70.54 that the Form NRC-741 be completed and distributed within 10 days Jter receipt of nuclear material, the licensee may use a Form NRC-284 to acknowledge receipt where measurements cannot be completed in the time specified. Receipt measurements shall be completed and reported on the Form NRC-741 within 30 days after receipt of material.
6.5 The shipper's UF values for weight, element, isotopic analyses, 6
and limits of error may be accepted for material accounting i g pc;;; if the UF is received from an DOE-owned, contractor-operated facility,6provided the licensee or his agent has:
(a) Witnessed the weighing and sampling of the UF cyli nders 6
at the time they are filled, and acquired receiver's
- samples, (b) Tamper-safed the cylinders with tamper-indicating devices in accordance with the criteria specified in '
Regulatory Guides 5.10 and 5.15, (c) Determined that the containers were received at the licensee's facility in an inviolate condition, (d) Measured gross weights of cy!inders immediately upon receipt and determined that they agree with the shipper's values at the 95% confidence level,
Amendment No. MPP-2 Page 4 of 4 Docket No. 70-1237 License No. SNM-1;27 (e) Measured the element and isotopic composition of the receiver's samples and the results agree with the shipper's values at the 95% confidence level, and (f) Recorded the receiver's valuet on Form NRC-741 and certified therein that shipper's values are accepted on the basis of independent measurement verification.
6.6 Notwithstanding the requirement of 10 CFR 70.51(f)(1)(1), the licensee may use, for material accountir:p purposes, the U-235 receipts, as determined by enrichment of UF6 or UO 7 measurement, for the U-235 content of U0, powder and U0 pellets derived from such receipts provited that materi$1 identity and isotopic integrity are maintained and provided that'such U-235 values are verif.ied by measurement as specified in Section 3.7 of the Plan identified in Condition 2.1.
7.0 INTERNAL CONTROL 7.1 The same individual shall not sign a document as both the Shipper and Receiver.
7.2 The licensee shall perform an overcheck measurecent on plutonium receipts within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using non-destructive analysis techniques.
7.3 Accurate records shall be established and maintained on a dsily basis for plutonium and high enriched uranium and on a bi-weekly basis for low enriched uranium to provide knowledge of the identity, location, and quantity of all SNM within each plant in discrete items and containers.
8.0 MANAGEMENT 8.1 Any apparent 19ss of a discrete item or container of special nuclear material which cannot be resolved by an immediate investigation shall be reported to the Manager, Quality Assurance and Licensing who shall romptly notify the Regional Office of the Nuclear Regulatory Coinmission, and shall conduct an investigation of the loss.
The Manager, Quality Assurance and Licensing shall document the results of his investigation and maintain the t-ecord for five years.
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