ML20041E506
| ML20041E506 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 12/21/1981 |
| From: | Randy Erickson NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Schneider R SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| References | |
| NUDOCS 8203110023 | |
| Download: ML20041E506 (6) | |
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" Return to f4 MSS /SGML, Mail Stop 881-SS" DISTRIBUTI0ft:
$8 DEC 2 ' N Docket file 70-1257 f1 MSS r/f Case file MCL r/f Exxon iluclear Company Inc.
tz ATTil: Mr. R. A. Schneider, Senior Specialist RBrightsen liuclear Material Safeguards DWeiss 2955 George Washington Way WBrown, IE Richland, Washington 99352 FGillespie, RES RPage, FC Gentlemen:
Litorderhaug, Reg. V This is in response to your letters dated January 6,1981 which transmitted Revision 11 to your Fundamental fluclear Material Control Plan (Fi4MC) and August 28, 1981 which transmitted revised Chapter 6, " Material Accounting Systems" to your Fundamental fluclear Material Control Plan.
We have determined that these revisions will'not adversely affect the common defense and security and are otherwise.in the public interest.
Accordingly, Safeguard Amendment MPP-2 to License Stim-1227, Sections 1.0 through 8.0 have been revised in its entirety and is effective immediately. This amendment is included as an attachment to this letter.
It has been established that the attachments to your letters dated January 6, 1981 and August 28, 1981 contain information of a type specified in 10 CFR 2.790(d). Accordi,ngly, 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 pmvisions of 10 CFR 9.12.
Sincerely, l
LJ dM}&t O 0
M Robert A. Erickson, Acting Chief Material Control and Accountability Licensing Branch
Enclosure:
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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 DEC 211981 1.0 FACILITY ORGANIZATION Currently there are 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 the Fundamental Nuclear Material Control Plan titled, " Nuclear Materials Safeguards Procedures Description for the Fuel Fabrication Plants, XN-12, Revision 5 dated February 1977; as amended according to the schedule of pages, Revision 11, XN-12, dated August 1980 and was transmitted with his letters dated January 6,1981 and August 28, 1981; and as may be revised in accordance with the provisions of 10 CFR 70.32(c). All reference to the Solid Waste Recovery Process found in XN-12, Revision 11 have been deleted from NRC review in accordance with the licensees request dated October 14, 1981 (R. Nilson to R. A. Erickson).
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 materials 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 Commission.
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 an MBA and an ICA with the exception that one individual may be the custodian for all activities involving plutonium.
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, shipments, waste l
discards, internal transfers from MBAs, and material inventoried; and the isotopic content of offsite plutonium receipts and shipments.
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Anendment No. MPP-2 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 maintained to assure the continuing reliability of the overcheck measurements.
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 nake 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 neasurements.
4.5 Notwithstanding the requirement of 10 CFR 70.57(b)(8)(1) 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, relative to liquid waste tank volume calibrations.
4.6 Notwithstanding the requirement of 10 CFR 70.57(b)(11) to establish and maintain control charts for mass standards measurement data and replicata 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 Notwithstanding the requirements found in 10 CFR 70.51(f)(3)(ii), the quantity of contained element and fissile isotope of pellets of uranium oxide or mixed oxide for inventory verification in boats, trays and boxes may be determined by weighing such pellets and using factors based on current measurements.
Amendment No. MPP-2 Docket No. 70-1257 License No. SNM-1227 5.2 Notwithstanding the requirements of 10 CFR 70.51(f)(2)(ii) to verify the integrity of the tamper-safing devices the licensee shall follow the following procedures for barrels, drums, or boxes containing special nuclear material in the form of waste or filters:
1.
Measure each container for special nuclear material and tamper-safe the container before it is removed from the material balance area.
2.
Transfer each sealed container to a storage item control area.
3.
For physical inventory verification:
Identify each iten on an inventory listing by a unique a.
identification such as item number, material category, inventory number, etc.
b.
Visually inspect each item for evidence of tampering or loss of container integrity, to the extent possible without movement of the container.
c.
Items rejected under 3.b (above) shall be remeasured and an investigation conducted in accordance with the provisions of 10 CFR 70.52.
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, 6.3, and 6.4.
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6.2 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).
6.3 The shipper's UF values for weight, element, isotopic analyses, and limits of er or may be accepted for material accounting purposes if the UF s received from an DE-owned, conuactor-operated facility,6provided the licensee or his agent has:
l (a) Witnessed the weighing and sampling of the UF cylinders g
i at the time they are filled, and acquired receiver's
- samples, t
(b) Tamper-safed the cylinders with tamper-indicating devices in accordance with the criteria specified in Regulatory Guides 5.10 and 5.15, j
(c) Determined that the containers were received at the licensee's facility in an inviolate condition, i
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(d) Measured gross weights of cylinders immediately upon receipt and determined that they agree with the shipper's l
values at the 95% confidence level,
Amendnent No. MPP-2 Docket No. 70-1257 License No. SNM-1227 (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 values on Form NRC-741 and certified therein that shipper's values are accepted on the basis of independent measurement verification.
6.4 When uranium hexafluoride containing less than 5 weight % U-235 is received from a foreign supplier under conditions in which the licensee or his agent cannot witness the loading, sealing, weighing and/or sampling of such cylinders, the licensee shall:
gross weigh each cylinder upon receipt at his facility, a.
b.
sample each cylinder during unloading to process in accordance with NRC approved procedures, c.
analyze each sample for percent uranium and percent uranium-235 within 30 days of unloading, d.
use licensee measured values for accounting records, e.
perform statistical tests for significant shipper-receiver differences on the data, f.
review and evaluate shipper-receiver differences in accordance with procedures found in 10 CFR 70.58(g).
6.4.1 In lieu of the requirenent found in 10 CFR 70.54 that the Nuclear Material Transaction Report, Form NRC-741 shall be completed and distributed within 30 days after receipt of material, the licensee shall prepare and distribute this report for uranium hexafluoride from a foreign source within ten days after receipt of all assay data from his contractor laboratory. Should any item of measurement data for this material indicate a possible shipper-receiver difference, greater than the calculated limits of error, this information shall be communicated to the NRC Regional Office of the Division of Inspection and Enforcement.
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i Amendnent No. MPP-2 Docket No. 70-1257 License No. SNM-1227 6.5 Notwithstanding the requirement of 10 CFR 70.51(f)(1)(1), the licensee may use, for material accounting purposes, the U-235 enrichment of UF E
measurement,fortheU-$35contentofU0 powder and U0 6
pellets derived from such receipts provi$ed that materi$1 identity and isotopic integrity are naintained and provided that such U-235 values are verified 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 measurement on plutonium recei-ts 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 recoros shall be established and maintained on a daily 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 f
8.1 Any apparent loss of a discrete item or container of special nuclear raterial which cannot be resolved by an immediate investigation shall be reported to the Manager, Quality Assurance and Licensing who shall promptly notify the Regions!
Office of the Nuclear Regulatory Conmission, and shall concuct an investigation of the loss. The Manager, Quality Assurance and Licensing shall document the results of his investigation and maintain the record for five years.
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