ML20053B722
| ML20053B722 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 02/24/1982 |
| From: | Evans L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Vaughn C GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8206010180 | |
| Download: ML20053B722 (6) | |
Text
-
c.
" Return to NMSS/SGFF, Mail Stop 881-SS" DISTRIBUTION:
PDR Docket file 70-1113 Case file FEB H M SGFF r/f s/f NMSS r/f NMCL r/f SGFF:DAH CNSmith 70-1113 DAHuff DWeiss WBrown, IE RPage, FC
- AGibson,
- g General Electric Company e
ATTH: fir. C. f t. Vaughen, Acting !!anager g
h Licensing and Conpliance Audits S
4D 0-Itail Stop J-26 s
a Castle Hayne Road
. $k 11 3 Yw
}
g*4i '$ '
~
P. O. Box 7R0 Wilmington, North Carolina 28401 Gentlenen:
- g This is in response to your letters dated Decenber 7,1981 and January 57 1982 which transmitted changes to your Fundamental Nuclear itatorial Control Plan.
We have detemined that approving these changes will not adversely affect the common defense and security nor the public health and safety and is otherwise in the public interest.
In addition, we have determined that six of your present license conditions are obsolete. Therefore, we are hereby modifying License Condition 2.1 and deleting existing License Conditions 2.3, 4.6, 4.7, 6.1, 6.2, and 6.3, effective immediately. Revised Sections 1 through 8 of Safeguards Amendment MPP-3 to License No. Sil!1-1097 is contained in the er; closure to this letter.
We have established that the attachments to your letters dated Decenber 7,1981 and January 26, 1982 contain infomation of a t,ype specified in 10 CFR 2.790(d).
I Accordf roly, pursuant to Section 2.790(d)(1), such infomation is deened to be conmercial or financial information within the meaning of 10 CFR 9.5(a)(4) and i
I shall be subject to disclosure only in accordance with the provisions of 10 CFR 9.12.
Sincerely, l
L. J. Evans, Jr., Chief l
Fuel Facility Safeguards Licensing Branch l
8206010lB0e nivision er safeguares, ass
Enclosure:
As stated l
l Iq..kGg..
....Sg.;
....M.F......
4
- q. O fu7f;ah CNpj
.ue
- s.,. Jr...
^"1..avm2.......2rg/82 afjg82...
NPC FORM 318 10-80) NRCM 0240
g O
ENCLOSURE Page 1 of 4 UNITED STATES NUCLEAR REGULATORY COMMISSION-l LICENSE AMENDMENT FOR SPECI AL NUCLEAR MATERI AL 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 amendment to the special nuclear material license-identified below is hereby issued, incorporating requirements for the control and account,ing of special nuclear material.
Licensee Name:
General Electric Company License No.
SNM-1097 Address:
Castle Hayne Road Amendment No. MPP-3 P.O. Box 780 Wilmington, No. Carolina Docket No. 70-1113 28401 CONDITIONS 4
l.0 FA_CILITY ORG ANIZATION:
Currently there are no license conditions in this section.
The necessary information has been incorporated into an approved plan.
2.0 FACILITY OPERATION 2.1 The licensee shall f.ollow the Fundamental Nuclear Material Control Plan specified on pages xix through xxiv dated December 7,1981 (except pages 3-16 through 3-22 and pages 7-7 through 7-17), as specified on page xxvi dated July 6,1981 (which contains descriptions of acceptable alternative safeguard systems for meeting regulatory requirements), as amended by pages dated August 7,1981 and January 25,1982; and as revised in accordance with the' provisions of 10 CFR 70.32(c)..
2.2 No statement in the licen.see'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.
~
Amendnent No. MPP-3 Page 2 of 4 Docket No. 70-1113 License No. SNM-1097 3.0 MEASUREMENTS Measurem~ nts are not required on sealed sources, and those samples 3.1 e
intended for analysis and testing which have been determined by other means to contain less then 10 grars U-235 each.
3.2 Th.e arch.ive material described in the licensee's letter of November 17, 1978 shall be measured prior to any shipment (except for return to the General Electric, San Jose, California facility in as received condition), processing, disposal and/or scrap recovery.
4.0 P.EASUREMENT CONTROL 4.1 Notwithstanding the requirements of 10 CFR 70.57(b)(8) to measure standards and replicates for volume measurement systems, to determine random errors for volume, NDA and weighing from process materials, and to separate random analytical and random sampling errors; the licensee shall follow Sections 4.2.3.2 and 4.4 of the Plan identified in Condition 2.1.
4.2 Notwithstanding the requirements of 10 CFR 70.57(b)(10) to perform bias corrections, and to propagate systematic errors in the calculation of LEID; the licensee shall follow Section 4.2.4 of-the Plan identified in Condition 2.1.
4.3 Notwithstanding the requirements of 10 CFR 70.57(b)(ll) to use control cbarts to monitor the quality of each type of program measurement
~
and to establish control limits at the 0.05 and 0.001 level of significance, the licensee shall follow Sections 4.5.1 and 4.5.2 of the Plan identified in Condition 2.1.
4.4 Secondary standards used in the calibration of nondestructive assay systems shall be representative of the m' terial to be measured; a
consideration shall be given to matrix composition, and SNM geometrical distribution, quantity and isotopic content.
The licensee may use generic standards for items to be measured which are non-routine and l
which do not have significant effect on ID and LEID.
4.5 Notwithstanding the requirements of 10 CFR 70.57(b)(4), the. licensee shall define systematic sampling error as zero, and conduct sampling, l
mixing and sample integrity studies. in accordance with Section 4.3 l
of the Plan identified in Condition 2.1.
I l
s Amendment No. MPP-3 Page 3 of 4 Docket No. 70-1113 Licensa No. SNM-1.097 4.6 Notwithstanding the requirement of 10 CFR 70.57(b)(11) to establish and maintain control limits at the.05 and.001 s~ignificance levels for accountability measurements, the licensee may allow their present contractor laboratory to continue the practice of using the NBL or NBS standards certified tolerance limits for measurement systems cont rol.
4.7 Notwithstanding 10 CFR 70.57(b)(3),. the licensee may. utilize national laboratories ~ and DOE contractor laboratories for the purpose of certifying standards and resolving shipper / receiver differences without performing reviews and audits of such laboraterias.
4.8 Notwithstanding 10 CFR 70.57(b)(3), the licensee is not required to perform reviews and audits of contractors who are NRC licensees subject to the requirements of 10 CFR 70.57(b).
5.0 INVENTORY 5.1-Notwithstanding the requirer..ents of 10.CFR 70.51(e)(3)(ii), the licensee shall conduct physical inventories in accordance with the criteria set forth in the Plan identified in Condition 2.1 at intervals determined from the start of the beginning inventory to the start of the ending inventory not to exceed twelve (12) calendar months.
5.2 If the inventory difference (ID) for the annual physical inventory exceeds the limits specified in 10 CFR 70.51(e)(5), the licensee will revert to the semi-annual physical inventory until such time as the resultant investigation has satisfactorily resolved the reasons for the ID and NRC written concurrence has been received to return to the annual ~ inventory schedule.
5.3 Each plant ID and LEID determination shall be reviewed by an individual not involved in the original calculations.
5.4 Notwithstanding 10 CFR 70.51(e)(3)(i), the licensee may conduct physical inventories of SNM containing less than or equal to 350 grams of U-235 in high enriched uranium or containing less than or equal to 7 grans of plutonium in accordance with their inventory schedule for low enriched uranium.
~
~
w.
Amendment No. MPP-3 Page 4 of 4 Docket No. 70-1113 License. No. SNM-1097 6.0 RECORD.S 'AND REPORTS:
Currently there are no license conditions in this i
section.- The necessary information has been incorporated into an approved plan.
7.0 INTERNAL CONTROL 7.1 Not~ withstanding the definition of scrap contained in 10 CFR 70.4(u),
SNM-containing trash and oil retained for further processing via incineration may be classified as disposable waste with no associated time limit for retention.
Ash residues generated by incineration shall
.either be classified as scrap and treated as required by 10 CFR 70.58(i)(2).
or classified as waste and buried if further processing is not approp ri ate.
8.0 MANAGEMENT
Currently there are no license. conditions in this section.
The necessary information has been incorporated into an approved plan.
FEB 241982 (Date of Revision)
~
l l
l l
i
-