ML19260D305
| ML19260D305 | |
| Person / Time | |
|---|---|
| Site: | 05000268 |
| Issue date: | 06/02/1972 |
| From: | Page R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Vanhoomissen J GENERAL ELECTRIC CO. |
| Shared Package | |
| ML19260D295 | List: |
| References | |
| FOIA-79-520 NUDOCS 8002080288 | |
| Download: ML19260D305 (13) | |
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CBS:lrm:.iT RC?cac 5/2 6/ 72 l9
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17 May 1972 1
PROPOSED LICENSE CONDITIONS MIDWEST FUEL RECOVERY PLANT, MORRIS, ILLINOIS 1,0 FACILITY ORGANIZATION 1.1-The Plant Manager, Midwest Fuel Recovery Plant (MFRP), shall establish, maintain, and manage a system of controls to safeguard special nuclear material.
1.2 Nuclear material control procedures and revisitn thereto shall be approved by the Plant Manager, MPRP, and by the Manager, Nuclear Materials Management-MFRP (NMM-MFRP).
1.3 The Manager, NMM-MFRP, shall maintain the official plant records pertaining to nuclear materials management and safeguards, including a manual containing all current nuclear material control procedures.
1.4 The Plant Manager -MFRP shall assure that the nuclear material control procedures are appropriately reflected in process specifications, manufacturing instructions, standard operating procedures, or similar detailed management instructions.
1.5 All delegations of safeguards responsibilities shall be in writing.
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2.0 FACILITY OPERATION 2.1 Material Balance Areas (MBA's) shall be established by the Manager, NHM-MFRP, with the concurrence of the Plant Manager-MFRP. Each 12A shall be an identifiable physical area into and out of which move-ment of special nuclear material can be measured, and shall be established in such a manner as to identify and appropriately localize lasses of special nuclear materials.
2.2 The custody of all special nuclear material within a designated M3A
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shall be the responsibility of a single custodian.
3.0 MEASUREMENTS AND STATISTICAL CONTROLS 3.1 The licensee shall measure the content of total uranium, U-234, U-235, U-236, U-238, total plutonium, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242 in all input solutions and product loadouts. The licensee shall determine total uranium, U-235, total plutonium, and (Pu-239 + Pu-241) content for measured discards and for transfers to Waste Storage Area.
The licensee shall make sufficient measure-ments on a current basis to substantiate each stated quantity and-its k.
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17 Fay 1972 PROPOSED LICZEE COriDITIONS
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MILVEST FUEL RE00VE3Y PLANT, MORRIS, ILLINOIS associated limit af error. Limit of errar (LE) as used herein neans the uncertainty companent used in constructing a 959 7
c.nfidence interval after any recognized bias has been eliminated
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or ace :unted f.ir.
32 The frequency and quality of the measurements made to c.;= ply with the license conditions shall be controlled so that:
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(a) Between drain-down invent 3 ries made pursuant to Candition 6.2, the limit of erri:r associated with the caterial unaccounted for (LEEJ/) for the material-balance interval does not exceed the larger af:
(1) for plutonium, 200 grams of plutonium or 1.0j ;f the quantity of plutonium in the measured input for the interval, (ii) for (Pu-239 -1 Pu-2 +1), 200 grams of (Pu-239 + Pu-241)
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2 or 1.0% of the quantity of (Pu-239 + Pu-241) in the neasure'd input for the interval; (iii) for uranium, 200 kilograms of uranium or 0.6% of the quantity of uranium in the measured input for the interval; (iv) for U-235, 2,000 grams of U-235 or 0.7') of the quantity of U-235 in the measured input for the interval.
(b) Between shutdown inventories made pursuant to Condition 6.1, the LEVP for the material-balance interval does not exceed the larger of:
(1) for plutonium, 200 grams of plut :nium or 1.0% of the quantity of plutonium in the measured input for the intervul; (ii) for (Pu-239 i Pu-241), 200 cra=3 of (Pu-239 Pu-241) or 1.Oj of tne quantity of (Pu-239 -i Pu-241) in the measured input for the interval; (iii) for uranium, 200 kilograms of urgh or 0.4A of the quantity of uranium in the =eae c.
,, ut far the interval; and D
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c PROPOSED LICENSE CONDITIONS MIDWEST FUEL RECOVERY PLANT, MORRIS, ILLINOIS a (iv) for U-235, 2,000 grams of U-235 or 0.5% of the quantity of U-235 in the measured input for the interval.
3.3 A measurement quality control program, including calibration of equipment and standardization of analytical methods, shall be established and maintained to provide current measurement data to substantiate the LE's associated with all measurements required for safeguards purposes.
3.4 The Manager, NKX-MFRP, shall annually review all measurements required pursuant to this amendment, including a review of the quantitative calculation of the LE's of the measurement system.
Data obtained through the measurement quality control program carried out pursuant to Condition 3.3 shall be utilized to monitor performance of the measurement system to assure that calculated LE's are maintained between reviews.
Records of reviews, calculations, and the use of calibration data shall be kept by the Manager, NMM-MFRP.
3.5 After each physical inventory taken pursuant to Conditions 6.1, 6.2, and 6.3, tha material unaccounted for (MUF) and the LEMUF shall be computed within 14 days of the start of the inventory.
The LEMUF shall be calculated by statistically combining the LE's determined for beginning process inventory, ending process inventory, measured discards, transfers to Waste Storage Area, and quantities of material dissolved and loaded out for the period since the last inventory.
3.6 If (a) the quantity of MUF exceeds its associated LE and 200 grams of plutonium, 200 kilograms of uranium, or 2,000 grams of U-235, or (b) the LEMUF for plutonium, (Pu-239 + Pu-241), uranium, or U-235 exceeds the limit specified in Condition 3.2, the licensee shall promptly notify Directorate of Regulatory Operations, U.S.
Atomic Energy Commission, Region III Office, 799 Roosevelt Road, Glen Ellyn, Illinois 60137, and shall take immediate action to investigate the cause for the excessive values. Within thirty days after the initial notice, the licensee shall notify the Region III office of the Directorate of Regulatory Operations in writing of the probable reasons for the excessive values, and the corrective action taken or planned.
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Z PROPOSED LICENSE CONDITIONS u
MIDWEST FUEL RECOVERY PLANT, MORRIS, ILLINOIS.. _
4.0 SHIPPING AND RECEIVING 4.1 Receipt of special nuclear material may be provisionally accepted at the FTRP at the amount shown on the nuclear material transfer document. The book inventory and material transfer forms for all fuel in a process lot shall be adjusted to the amounts of special nuclear material measured as input as soon as the processing of the lot has been completed.
4.2 All irradiated fuel assemblies and all containers of ruptured or loose assemblies shall be piccc-counted and verified by serial number, if any, upon receipt.
4.3 All shipping and receiving measurement data and analyses of measurement uncertainties shall be kept by the Manager, NMM-MFRP.
4.4 The Manager, NMM-MFRP, shall evaluate all shipper-receiver differences to determine if the differences are statistically significant and/or of sufficient magnitude to warrant investi-gation. The shipper-receiver dif ference shall be considered statistically significant when (a) the difference exceeds the combination of the LE's of the shipper's and receiver's measurements, or (b) the difference exceeds twice the LE for the receiver's measurement for the case where the shipper's LE is unknown.
4.5 Upon request from the AEC Directorate of Regulatory Operations, the licensee shall retain for AEC use designated samples identical to those taken for his accountability measurements.
5.0 STORAGE AND INTERNAL TFANSFERS 5.1 A documented control system over special nuclear material stored and processed within the MFRP shall be maintained that will provide continuous knowledge of the location and quantity of all material contained in discrete, identifiable items or containers and within the process.
5.2 All nuclear materials on the MFRP premises ahall be assigned to one of three inventory control areas (ICA's) or to the waste W( >
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PROPOSED LICENSE CONDITIONS MID'e.ST FUEL RECOVERY PLAhT, MORRIS, ILLINOIS
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storage area (WSA). The three inventory control areas shall be the Fuel Receipt and Storage Area (ICA-1), the Processing Area (ICA-2), and the Product Storage and Shipment Area (ICA-3).
5.3 An internal transfer document shall be executed each time that special nuclear material is moved from one ICA to another.
Each internal transfer document shall show piece identity (if
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applicable), and quantity and type of material transferred, and shall be signed by the delegated individual.
Internal transfer forms will be issucd through the MBA custodian and controlled through Nuclear Materials Management.
5.4 Permanent records shall be kept of the total quantities of special nuclear material transferred to and contained within each vault of the WSA.
6.0 INVENTORY 6.1 A shutdown physical inventory of the processing area (ICA-2) including c1 caning and flushing of all process equipment shall be performed at intervals.not to exceed twelve months.
6.2 A drain-down inventory shall be taken between process lots in accordance with procedures specified in Table 3.7 of the MFRP Safeguards Manual dated April, 1971, at intervals not to exceed the processing of 30 tonnes of fuel or 45 calendar days, whichever occurs first.
6.3 A special shutdown inventory of the processing area shall be conducted whenever there is reason to believe that abnormal conditions have adversely affected the expected loss or placement of nuclear materials.
6.4 The Manager, NMM-MFRP, shall review and approve procedures for inventorying of nuclear material, and shall audit the actual taking of the inventory for compliance with approved procedures.
6.4.1 Materials in the processing area shall be combined in those vessels that facilitate sampling and accounting.
6.4.2 Residual quantities of nuclear materials ins rocessing g
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PROPOSED LICE::SE CCOITIO:iS MIDWEST FUEL RECOVERY pLA:??, MORRIS, ILLC:OIS
-o-ec,uipment that cannot be isolated in vessels for sampling shall be calculated oy cualified personnel on the basis af process parameter =casurements at the time of the inventory, using approved estinati,n techniques.
6.4 3 Paterials that have been inventoried shall, uhere accessible, be tagged ta minimisc the possibility of duplicate c.sunt and to facilitate internal audit of inventcry conpleteness.
65 Itens af special nuclear matcrial in the Fuel Receipt and c
Storace Arca (ICA-1) shall be inventoried on the basis of piece cou.t and esticated contents as rep;rted by the shipper an F.rm AEC-7hl. All such caterial shall be invent,ried for verification ;f physical presence in its assignei location at intervals of one month.
6.6 Ite=s or special nuclear naterial in the Praduct Stora.e anc Shipment Area (ICA-3) shall be invent,ried on the tasis of net weight and chemical and isotopic analysis at the time af inventary, except that previously made measurements may be accepted if the integrity of the measurement has been assured by an approved tamper-indicating device. All such naterial shall be inventoried for verification of its physical presence in its assigned location, and for verification of intact tanper-indicating devices, at intervals not to exceed seven calendar days.
6.7 The book inventory shall be reconciled with and adjusted to the results of each shutdown physical inventory within 14 calendar days after the day the inventory was started.
70 RECORDS /d:D REPORTS 71 'Jhe licensee shall estnblish and maintain a records systc= that shall contain information pertaining to all rece'. pts, shipments, ucasured discards, transfers to WSA, inventories, and I'J for each material balance, and shall provide sufficienv. infs m.ation to supp.>rt the material-balance calculation. All entries in the records shall be supported by appropriate documents.
72 Subsidiary records related ta processing and production activities o%h O
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?ROPOSED LICE::SE CO3DI'2IO::S h':
MID'.CS't FUEL R3CGVZRY PLA:72, MORRIS, ILLIliOIS
[}i r of each process lot shall be maintained by plant engineering
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and plant producti:an for a minimu:n of three years follaving completion of pr., cessing.
- "'r 73 The licensee shall submit Material Status Reports
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AEC-742, completed in accardance with the printed instractions, as of the last day of each n nth far all special nuclear catcrial.
Separate Material Status Reports shall be submitted for (i) the Inventory Contrsl Areas (ICA-1, ICA-2, and ICA-3), and f >r (ii) the Uaste Storage Area.
'the reports shall be filed uithin cight (d) days after the end of the period c..vered by the repvrt, and shall be filed with the U. S. Atc=ic Energy Co=is-sion, P. O. Box E, Cak Ridge, dennessee 37830, with a copy to the Region III Office, Directorate of Regulatory Operations, U. S. Atomic 2nergy Commission, Glen Ellyn, Illinois 00137 74 After each inver. tory, the Ieanager, rao:-leRP, shall issue a report including such infacation as beginning and ending inventury, verified clerical errors, weight or volume dis-crepancies, required perpetual inventory corrections, and material-balance data. This report shall be issued to the Plant Manager-ERP and to the Mana;;er, NIG-ED, with copics to concerned plant organizational components.
75 Within thirty (30) days after the first anniversary of the issuance af this license, the licensee shall report the results of the review rcouired by Conditivn 3.4, and an analysis of per-f >=ance c ) pared with the " pro forma" predicticn in the Safe-guards Ihnual, to the Directorate of Licensing, U. S. Atomic Energy Co= mission, Washington, D.C. 20545, with a copy to the 7.
Region III Office of the AEC Directorate of Regulatory Operations.
8.0 FEAGEMENT OF MATERIALS COX'JROL SYSE4 8.1 Company management, independent of Nuclear Materials I'.anagement, shall conduct an internal revicu of the nuclear materials c2n-trol systos at intervals n>t ta exceed twelve months. Results of the aucit shall be documented, and capics of the rep rt shall be sent to the General Manager, Huclear Fuels Department, and to the Directorate of Regulatory Operations, U. S. Atomic Energy Co= ission, Washington, D.C. 20545 A
9 y #s 1938 257 9
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PROPOSED LICENSE CONDITIONS MIDWEST FUEL RECOVERY PLANT, MORRIS, ILLINOIS 8.2 Any unresolved apparent loss of a discrete item af ter 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or verified loss of a discrete item shall be reported imme-diately to the General Manager, Nuclear Fuels Department, and to the Directorate of Regulatory Operations, U.S. Ai:omic Energy Commission, Region III Office, 799 Roosevelt Road, Glen Ellyn, Illinois 60137.
9.0 PHYSICAL PROTECTION REQUIREMENTS 9.1 Definitions applicable to Physical Protection Requirements 9.1.1 Except where specifically noted, the requirements con-tained in these license conditions are in addition to those specified in 10 CFR Part 73.
In any case where inconsistencies may appear, the license conditions shall prevail, 9.1.2 The following terms shall have the meanings defined in 10 CFR Part 73:
authorized individual, guard, lock, physical barrier, protected area, vault, and watchran.
9.1.3
" Intrusion alarm" means an electrical, electrouechanical, electro-optical, electronic, or similar device capable of detecting intrusion by an individual into a building, protected area, or plutonium access area, and capable of annunciating the intrusion by means of actuated visible and audible signals.
9.1.4
" Plutonium access area" means any location (i) within a building which, in turn, is located within a protected area, and (ii) which is enclosed by a second physical barrier or substantial interior partitions, and (iii) which contains plutonium other than plutonium contained in irradiated fuel or in the Waste Storage Area.
9.2 Physical Protection Organization 9.2.1 A force of guards, watchmen, and employees shall be established to protect special nuclear material against theft and diversion, and to protect the facility against sabotage which could result in a radiological hazard to the public health and safety.
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PROPOSED LICENSE CONDITIONS CT4EST ^ FUEL RECOVERY PLAW., MORRIS, ILLIX0IS 9
9 2.2 The co==cnd and responsibility structure during both normal and threat situations shall be documented.
93 Access Constraints 931 Plutonium shall be stored or processed only in a plutonium access area.
932 The licensee shall establish a separate plutonium access area for each vault or other location used primarily as a plutonium storage area.
933 Uhen manned, a plutonium access area shall be =anned by two or mare authorized individuals, or the activities of a lone authorized individual shall be observed by another auth>rized individual. When unmanned, a plu-tonium access area shall be locked.
934 Access to ea'ch plutonium access area shall be under the control of an authorized individual and limited to individuals who require such access to perfonn their duties.
935 Packages entering a plutonium access area shall be searched for devices that could aid an individual in the theft or diversion of plutoniu: or in sabotage of a facility.
936 Persannel access to the protected area shall be controlled by a guard or wate'e.an.
r 937 No personal vehicles shall be permitted within the pratected area.
938 The licensee shall register visitors, vendars, and other non-employees entering the protected area, recerning name, date, time, purpose of visit, and person visited.
939 Visitors, vendors, and other non-e:aployees shall be 4~~
escorted by a guard, vatchman, or auth)rized individual vhile within the protected area.
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9310 Keys, locks, combinations, and related equipment used in
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the physical protection system shall be controlled to minimize the possibility of co= promise, and shall be
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