ML20147C202

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Forwards Replacement for 771202 Appl W/Part III of SNM-1174 Termination Plan.New Submittal Contains Addl Details Requested by NRC Staff During 781102-03 Site Visit
ML20147C202
Person / Time
Site: 07001193
Issue date: 11/29/1978
From: Shelley W
KERR-MCGEE CHEMICAL CORP.
To: Rouse L
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 7812180185
Download: ML20147C202 (21)


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,o(kss KERR-McGEENUCLEAR CORPDRMIGN uaw. css canna. oxuwour em. exuwour nus RECEIVED November 29,~1978 D'iC 4 PM 12 I 2

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  • / T Mr. Leland C. Rouse, Chief

. Fuel Processing & Fabrication Branch N

y Division of Fuel Cycle & Material Safety p

th [ps a /dje U. S. Nuclear Regulatory Commission (g~

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RE: Docket #70-1193 m

Dear Mr. Rouse:

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Our application dated December 2,1977, containin,g Part' III.'

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of our SNM-1174 termination plan is hereby replaced with the attached plan. This new submittal contains additional details requested by your staff during their inspection of our Cimarron Facility plutonium plant on November 2 & 3, 1978.

We will appreciate your prompt review of this submittal. If you have any questions or need more information, please call in order that we may expediate our reply as early as possible.

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SNM-ll74 TERMINATION PLAN - PART III (Revised November 29,1978) 1.0 Solvent Extraction Glovebox and Equipment 1.1 Introduction j

The solvent extraction (S.X.) area floor plans are shown on pages 9-5 and 9-8 of our application of August 7, 1976.

The S.X. glovebox is' designated as number 2.A.

This U shaped box, if rectangular, would measure about 36' x 36' x 2.5' deep.

The basement portion of the S.X.

system is in room B-05 while the above g und level portion is indi-cated to be part of room 127.

The U shan box surrounds a personnel working area. This working area has two tal floored levels above the basement level.

Each level has a door. When these doors are closed, the S.X. area is isolated from the rest of the building.

Drawing No. CPP-600M-114-0 (attached) shows the floor plan view of the S.X. glovebox 27A, its air supply and its air exhaust glovebox No. 27B.

The S.X. system was sized for scrap recovery feed rates much larger than the amounts generated during the operations of the plutonium plant.

The system was seldom used and is considered obso-lete even if the plutonium plant were to return to. operating status.

The S.X. area was cleaned in preparation for the standby status of the plant.

The cleaning methods inside Box 27A included complete draining of all vessels and piping, sludge removal, circulating fresh TBP and dodecane through the equipment (twice), followed by a trichlo-roethane rinse.

The box walls were pressure spray cleaned with trichloroethane.

Analysis of the collected cleaning solutions showed that the concentration of plutonium in them never exceeded 10 grams per liter.

These solutions were properly disposed of.

Monitoring, contamination controls, administrative controls, precautions and procedures will apply as described in our letter of November 8, 1977

" General Aspects of the Termination Plan", and our letter of October 11, 1977 " Termination Plan Part I".

In addition, the following actions will be taken to accomplish the removal and disposal of the S.X. process.

1.2 Description of S.X. Equipment Within glovebox 27A are four inch (I.D.) tanks and pulse columns most of which are made of stainless steel.

Some have flange fitted glass sections.

The stainless steel. piping ranges in thickness from schedule 80 to thin

. all tubing.

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tanks, and six pulse columns all of which are approximately 32 feet tall.

There are two agitator equipped organic - acid wash tanks each 10 feet tall, two overflow and catch tanks each 10 feet tall, two feed break tanks six feet tall,16 miscellaneous tanks three feet tall and 18 smaller tanks (Pots) ranging from six inches to one foot tall.

Of the glass columns, there are four which are eight feet tall, six are four feet tall and six which are two feet tall.

There is approximately 1,550 feet of piping.

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1 There are six pulse generating remote-head diaphragm pumps outside of l

the glovebox each with a slave unit housed within the box, coupled through a hydraulic line. Similarly, there are 29 feed and circulating pumps.

Other equipment within the box includes valving, liquid level control sensors, fire suppression equipment (Halon system) and ventilation ducts.

The box itself is made of stainless steel with plexiglass windows and glove ports. Ventilation within the box will be maintained until the box no longer exists. The halon fire extinguishment system within the box will be preserved until all other equipment has been removed and until i

the inner box surfaces have been cleaned. The halon system protecting the personnel working area will be preserved until the box disassembly is completed.

Room working area ventilation shall be maintained throughout the S.X. box dismantling activity.

Lighting by fluorescent lamps and high intensity lights will provide good j

visibility through the ample number of glove box windows.

If needed, flashlights can be bagged into the box.

.l.3. Special Equipment J..

Prior to further glovebox cleanout or'disassemblyj ~special equipient as described below shall be constructed, tested and evaluated.

Personnel training to assure proper and safe operation shall be accomplished before the equipment is committed to the disassembly activities.

1,3.1 N.D.A. Glovebox and Shipping Container " Bag-Out" Box

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Provisions are to be provided which will permit pieces of equipment to be transferred from the S.X. glovebox into a new gl.ovebox or tunnel which has N.D.A. instruments. After the equipment pieces have been measured, they will move directly into a new drum loading glovebox, exiting the box through the drum liner sleeve which is attached to the box bag-out port.

The pieces are thusly placed into the drum.

The drum has two plastic liners. The first is a bag liner placed into the drum forming the sleeve described above, while an inner liner (with lid) is a heavy self supporting plastic insert. This insert protects the i

1.ighter bag from puncture.

After the drum is loaded, the lid is placed on the heavy plastic insert and the drum is rotated, twisting the sleeve above the drum contents.

The twist is taped and cut. The outer drum lid, with a gasket, is then secured in place.

The drum is then transferred to the vault or to room 121, awaiting shipment to a licensed disposal site.

The drum is tampersafed (using the two men rule) and identified as

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e qv An especially designed rotating fixture will be provided to permit a plasma arc cutting torch to slowly encircle a four inch (I.D.) pipe.

When cutting, the torch and the fixture are in a non-combustible enclosure or shroud into which a nitrogen rich atmosphere is provided.

A long length i

of pip.e, suspended in:a vertical posit on, is lowered into the fi.xture and a section cut'off which can be safely handled, N.D.A. counted and 1

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t packaged. The pipe is again lowered and cut repeatedly until the pipe is completely sectioned.

l 2.0 Further Cleaning of the S.X. Area Before dismantling the S.X. equipment, gloves and bags will be placed on Box 27A which will permit the placement of a single five inch diameter, i

two or four liter poly bottle in the bottom of the box into which hydra-ulic pump oil will be placed. Only one bottle will be permitted in the i

box at a time. The bottles will contain absorbant in a quantity sufficient to absorb twice the amount of oil in the bottle. The filled bottle will be bagged out of the S.X. box before another empty bottle is bagged into the S.X. box.

Filled bottles will be stored in a safe array not to exceed 10 bottles separated one from the other with a minimum of 2 feet of air space.

The bottles will be individually counted using N.D.A. equipment.

l The bottles will be cemented into 55 gallon drums in guch a manner as not i

to exceed an average concentration of 5 grams per ft.

in the drum.

The S.X'. pumps and piping external to the S.X. glovebox will. be removed.

Instrumentation, control cabinets and unneeded electrical circuitry external to_the: box will also be removed from box 27A.

A small electric

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steam ~jennyiorf a circulation pump will be used-to: pump. decontamination

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' solutions to' box 27A. The 'used decontamination solutions' will' be pumped from the bottom of the box and transferred to two or four liter five inch diameter poly bottles which are then cemented into drums in the manner l

used for pump oil.

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' Additional gloves will be placed on box 27A as needed to facilitate the 4

final cleaning of equipment and ' surfaces inside of the box.

Cleaning will j

start at the top of the box and progress downward. Spray nozzles will be used as well as manual cleaning methods.

Previous cleaning.of this box by these methods never produced solutions with plutonium concentrations exceeding 10 g/1.

Plutonium solutions at 10 g/l has a safe slab thickness exceeding 12 inches. The liquid accumulating in th5 bottom of the box will i

be maintained less than two inches deep. A liquid level probe / alarm is installed at a height of one inch above the bottom of the box. This alarm i

i will be maintained until box 27A is empty of equipment and has had its a

final wash.

3.0 S.X. Disassembly 3.1 Removal of Equipment from Box 27A l

Please refer to drawing CPP-600M-114-0.

Plans are made to completely cremove'all-of-the: equipment from..the box between E0 and E5,

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Wrenches, cutting. tools, drills, chain falls and "come alongs', large cye bolts, tackle and other tools will' be bagged into the glovebox.

Small diameter tubing and other small items will be removed first by disjoining

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un fasteners or cutting into pieces fitting the shipping drum. This will make room for working on the larger and heavier five inch (0.0.) columns and tanks. Eye bolts or other devices will be fastened into the top of the box above the five inch diameter vertical pipes. A chain fall or similar device will be attached snugly to tie bolt and the pipe.

The pipe supports will then be cut from the pipe. The pipe will then be lowered by 10 to 18 inch increments into the plasma arc cutter.

Only one column at a time will be sectioned in this manner.

Glass column sections will need to be removed whole. Those sections too long for drums will be removed using conventional bag out methods or by window removal using " greenhouse" techniques. They will then be N.D.A.

evaluated and packed in Specification 7A boxes.

At the end of each working shift, or more frequently, cuttings which have accumulated in the bottom of the box.will be collected in a single quart ice cream container, N.D.A. counted and drummed to assure that a safe slab of two inches is not exceeded. This will be repeated until the gross accumulation of the cuttings are properly disposed of. The quart containers are cylinders with diameters < five inches. -

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' ' 3.' 2 Removing ~Gl'vebox'27A'

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o The interior of the box will be washed and dried after all items are re-moved from it.

Plastic tape will be placed on the exterior surfaces of the box to identify cutting lines.

Paint will then be applied to the l

inner surfaces of the glovebox using rollers and brushes.

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Starting at the top of the glovebox, sections of the top, sides and front will be cut to a size convenient for bagging and for packaging. The cutting may be done using a sabre saw fitted with a vacuum hose which will have filtered exhaust.

Fresh tape will be placed behind the saw cut j

keeping the opening as small as possible. The cut section will be placed into a pre-prepared plastic envelope while following it with plastic sheeting to close the opening. Other cutting tools such as nibblers, saws and manually operated cutting torches, etc., may also be used.

" Greenhouse" or tent enclosures as described in Section 4 of our letter dated November 8, 1977, will be used,,as necessary. Where windows can be unbolted, cutting will be avoided.

Guard rails will be placed around the edge of the metal flooring of the upper two working area levels as the adjacent box sections are removed.

As the sections are removed, the back of the box and the bottom will still be._in place, covered wi_th the. plastic sheeting. Working downward, the i

- _ _ back of_the.sboxmill becloosened, fro.m:the:bu ldiny wall.and sections cut phen MndWainl-baggbdf&ItpiboLtorrAirlityc(bessecEionednar.d1bpgaede ME;p;T/!MPE 3.3 Glovebox 278 g

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Glovebox 27B contains the primary HEPA filters serving box 27A's ventila-tion system.

Af ter box 27A has been removed, the llEPA filters shall be bagged out from box 278.

Box 27B will then be cleaned, disassembled, t

bagged, N.D. A. measured, and packaged for disposal. ' The used filters will'be counted and packaged also. The duct to the secondary filter bank will be. sealed.

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.4.0 Assay of Plutonium.

All bagged' equipment parts, piping pieces, glovebox sections and solid waste packages will be N.D.A. measured.

Cleaning solution liquids absorbed

.and contained in '2t or 41 polly bottles will be N.D. A. measured before they are cemented into 55 gallon drums. Data from these analysis will be documented.

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5.0 Packaging and Disposal

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It is estimated that 3300 cu. ft of material will be packaged.

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specification drums and boxes will be used to package the material. Bagged-out material, glovebox sections, etc. may be packaged in rooms B-01, B-02, B-05, 127 and 128. Completed containers may await shipment in the vault and in room 121. The lid of each outer container shall be tampersafed promptly after the lid is attached.

NEC0,will transport the packages 4

within its Supertiger.

1 6.0 Work Schedule and Control i

Dismantling of glovebox 27/, is planned to be done on the day shift.

Each porning,ra review.of-the planned activities for the day shall precede.

commencement of the work. This planning'shall include the end-of-shift.

l clean-up needs, a safety inspection by the Health and Safety (HP) Techni-cian and security sealing each of.the entrance ways to the S.X. room.

In the event that difficulties are encounterd which prevent the safe con-clusion of the work or clean-up activity on the day shift, work may be authorized into the swing shift until the safe shut-down is accomplished.

.7,0 Monitoring Provisions 7.1 ' Air Monitoring i

Health Physics personnel conducts the air monitoring program.

All three stationary air samplers in the S.X: area and all six in the general'labora-J tory, eight in room B-01, six in room B-02, eight in room 127, eight in room 128, two in the vault, three in room 121, one in room 120 and two in the hallway adjacent to the rooms will be in use.

Fresh sample filter 5

papers will be installed at the beginning of each work shift during decommissioning activities, and will be gathered at the end of the shift (or sooner if desired). The S.X. area and rooms Nos. B-01, B-02,127, 128, vault and general laboratory shall have at least one constant air l

monitor with alarm (CAM) operating.

At least 50% of the personnel working

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in the S.X. area shall wear lapel air samplers.

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i 7.2 Surface Contamination Monitoring

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Contamination surveys conducted by Health Physics personnel will be made

,on a frequency basis to reliably demonstra.te contamination control in accordance with the requireme.nts.of procedure KM-NP-10-66.

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4 7.3 Nasal Smears & Bioassay Sampling Nasal smears will be obtained from each person at least at the end of each work shif t spent on the decommissioning activity. Nasal smears, urine samples, fecal samples and In-Vivo (lung) counting will be obtained in accordance to our Health Physics Procedure KM-NP-10-67.

8.0 Criticality Considerations (See calculations attached)

As described earlier, several criticality control procedures will be used including:

j a)

Prompt N.D. A. measurement of hardware, and cleaning waste as it is drummed through the new shipping container " Bag-Out" Box.

b)

One at-a-time use of geometrically safe bottles in the S.X. box for liquids collection and a safe array and spacing for storage of such

bottles, c)... A twolnch~ maxiinum liquid level for cleaning: solutions. in,the. bottom of the 'S.X; glo.vebox cdupled ~with a one' inch alarmc~

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The one-at-a-time movement of the five inch diameter columns as they are individually sectioned into smaller pieces, e)

Each shipping drum and box is limited so that its average plutgnium concentration is no more than five grams of plutonium per feet f)

Labelling and recordkeeping indicating quantities of plutonium in packages and containers with measured or analysed plutonium content.

'In addition to the above procedures, the following will be accomplished:

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The criticality detection and alarm system shall be re-activated and maintained.

b)

The emergency manual section on criticality accidents will be re-

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established, j

c)

The Kerr-McGee Nuclear Criticality Safety Specialist, Mr. G. M. France I

is based in the Oklahoma City office. Mr. France shall review and k

1 approve the proposed activities, make audits at least monthly, review and approve " SOL" limits and procedures concerning criticality control.

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The criticality section of the training program will be re-established and.a refresher course (including the above procedures) will be pre-sented for the appropriate employees.' Quarterly evacuation drills t

shall be re-established.

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9.0 Additional Security Measures In addition to the security measures authorized in our " Standby" license dated July 15, 1977, the following will.be accomplished:

a)

The ' sample." pass through window" locsted on the east exterior wall of laboratory room #140 will be completely covered with steel from the outside to prevent anyone from reaching through this window. The use of the SNM detector and alarm for this location may be discontinued.

This will be done before_ equipment removal from box 27A.

b)

When the NECO truck arrives, the guard checks the driver's credentials,

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requires him to sign "in" on the log, and performs his routine " frisk",

etc. After acceptable reception, the guard permits the truck to pass through the fence gate and park at the dock.

The driver then promptly exits the fence gate and returns to the guard, all while in view of the guard or an escort. The driver waits in the lunchroom or office area until his truck is loaded and sealed. After passing the guards i

exit check, the escorted driver returns to his truck through the j

w T.ence gategand; promptly;,ren! oves the. tr.uck f.r;om the'.facil.ity. site..,..

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j The NECO truck is' loaded by Cimarron Facility employees.

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loading, packages moving at any one time from room 121 to the truck will be limited to the space available in the airlock (room 120).

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First, the overhead door ("A" door) separating room 120 from 121 will be opened, packages moved into room 120 and then "A" door will be closed._ A H.P. technician will then survey all. persons moving the packages with a G.M. instrument and a metal detector before moving the packages from room 120.

Next, the overhead door ("B" door) between room 120 and the outside dock will be opened to allow the material to move to the truck.

The "B" door is then closed before the "A" door is again opened.

Person-nel re-enter room 120 using trie man door in the "B" door. During the truck loading, persons are not permitted to exit the fence gate.

1 The fence gate is controlled by the armed guard. The above procedure is repeated until the truck is loaded. Personnel return through the plant and guard station before leaving the Facility.

c)

No empty or partly filled drums (or other shipping containers) will be placed in room 121.

Shipping containers ready for shipment shall be tampersafe sealed.

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person must verify that the condition of the container matches the label description.

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The doors to the S.X. area will be tampersafed at the end.of each work day in this area..

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1 10.0 Accountability 10.1 - Introduction The Nuclear Materials Management Unit has been established at the-Cimarron Facility for.the purpose of developing, revising, implementing and enforcing all elements of the safeguards program.

The Plant Manager is responsible for the management of the facilities' activities including the elements of developing, revising, implementing and enforcing the Safeguards Program procedures.

A manual containing all current nuclear material control procedures shall be maintained by the Plant Manager.

The Health &' Safety Supervisor is responsible to the Plant Manager for the i

development of the Safeguards system. These duties include the establish-ment of a measurement control method for scales, analytical assays, and inventory. Statistical controls are to be established for these, consid-ering random bias and sampling error.

The responsibility also includes the implementation and reporting of scales, balances calibration and check weights. program and analytical analysis of the reference-samples, in

~ ddition to'n6rmaFanalytical' assays in' support' of.th'e Safegusrds pr6 gram.

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a The responsibility also includes the coordination of statistical and program elements within the Nuclear Materials Managment unit to assure the Manager that all program elements have been implemented and are rigidly enforced.

Administration & Accountability Clerk is responsible to the' Plant Manager for the development and implementation of the accounting, shipping and the records and report systems of the Safeguards programs.

Additional

-duties include the coordination of all elements within the Nuclear Materials Management unit to assure the Manager.that all program elements have been implemented-and are rigidly enforced.

10.2 MBA's Material Balance Areas (MBA) have been established by the Plant Manager at the Cimarron Plutonium Plant for the purpose of:

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' Establishing each MBA which shall be an identifiable physical area into and out of which movement of Special Nuclear Materials can be j

measured.

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Identifying and localizing Special Nuclear Materials (SNM) losses.

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Material Balance Areas are identified as follows:

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MBA-12 Vault Storage'(room 126) for plutonium bearing materials.

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NBA-50 Holdup plutonium and General Laboratory.

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MBA-121 Waste Shipment Storage (rcom 121).

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i The basis for establishing MBA's is that during the S.X, area disassembly

' plutonium standards and plutonium contaminated wastes are stored in the plant. Except for the Pu holdup in gloveboxes and process equipment, most SNM is stored in the vault and room 121.

Very few grams of Pu may be in the General Laboratory.

Plutonium stored in room 121 will consist only of material packaged and ready for shipment to burial.

10.2.2 Personnel The personnel as identified below are responsible for the control of SNM j

within his area and for the conduct and implementation of the Safeguards Program to include complete documentation of materials received into or removed from his MBA:

4 MBA-12 Vault Custodian MBA-50 Health & Safety Supervisor MBA-121 Administration &' Accountability Clerk i

Personnel responsible for the control of an MBA may authorize specific

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personnel to transfer SNM into or out of the MBA. Authorizations are to be, limited to' responsible. personnel in order, to achieve and document

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Instruction for the use i

of and proper completion requirements are identified in Facility Procedure Numbers KM-NP-15-16 and KM-NP-15-18.

10.2.4 Material Balance Ledgers The Material Balance Area Ledgers will be maintained and posted by the personnel responsible for the control of the MBA Areas.

Transfer documents as described in 10.2.3 will be utilized as the posting information.

These ledgers will be compared bi-monthly with the External Journals and Ledgers and with physical inventorica, 10.2.5 Inventories Inventories shall be conducted for the purpose of determining a material balance, loss or collection of other such information.

All material un-accounted for (MUF) will be credited to the Material. Balance Areas as i

~ms.adetermined.&An& nventory of;alhspecial: Muclear Material shall be. con-i

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,.g 10.3 Measur aments & Statistical Controls The program for compliance with this section is established by the Health

+ &c. Safety; Supervisor and reviewed by the. Plant Manager.

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The individual requirements for data collection, measurements and sampling requirements are outlined in appropriate safeguard procedures. The e

collection and processing of this data is the responsibility of the' Health & Safety Supervisor. Typical N.D. A. measurement procedures are illustrated in Appendix K of our application for the Standby license, a

dated August 7,1976.

This is supplemented with the use of procedure KM-NC-15-56 titled " Limit of Error Manual". ' Low-level liquid wastes are measured by N.D.A. or radioassay techniques as required by procedure 2

KM-NP-15-46. Thh procedure also covers' check weighing.

The interpretation, analysis and reporting of the measurement results to i

management is the responsibility of the Health & Safety Supervisor.

i physical inventories of the plutonium will be under the direction of the Health & Safety Supervisor. This individual is also responsible for the investigation and reporting to the Manager all shipper and receiver differences.

i j

The accumulation and reporting of the inventory data in compliance with 10 CFR 70.51 (3)(5) will be completed by the Health & Safety Supervisor.

The final reporting of the results to the Nuclear Regulatory Commission is'the Tesponsibility.of.the Plant Manager. 'The inventory report _is sub-S

~

i

.nitted to the Director, Regu'lation and Control, for review.

The report is forwarded to the Plant Manager for signature and distribution.

The reporting of material status conditions through the NRC/ERDA-742 will j

be handled by the Administration and Accountability Clerk.

Approval of these documents will be made by the Plant Manager.

\\

10.4 Management of Materials Control System 4

At least once each year, an internal review of the overall system of i

Special Nuclear Material Control will be conducted for corporate Management, and reported to the Plant Manager. The audit will cover accuracy, com-l pletness and adherence to accountability and safeguards procedures and existing regulatory requirements.

i An apparent loss of a discrete item or container of Special Nuclear Material which cannot be resolved by an immediate investigation shall be reported to the plant Manager, who shall promptly notify the Nuclear Regulatory Commission, Director of Inspection and Enforcement, Region III, Glen Ellyn, j

Illinois and shall conduct an investigation of the loss. The Plant Manager shall report the results of his investigation to the General Manager, Nuclear Manufacturing.

~

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r==--e-m g a:ep.

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g Although unlikely,' laboratory analytical procedures in support of the decom-missioning activities may be needed for the analysis of plutonium in waste l

liquids or solids.

In this event, trained and experienced radiochemists or technicians from the Kerr-McGee Technical Center will perform the 'ana-nlysisDin' the plutonium plant laboratory.

These persons shall be trained u :=1 l

I d

y V

r w

m

)

in the applicable aspects of the health and safety rules, security measures and accountability procedures.

.i 11.2 Maintenance Shop The glovebox in room 116 may be used for repair of tooling, etc., used during the S.X. area decommissioning.

In this event, air sampling and other health physics services will be appropriately conducted.

11.3 Building Ventilation During the S.X. decommissioning, two supply air and exhaust fans will be in operation; rather than one fan each as described for the standby con-dition of the total plant.

11.4 Outside Assistance a)

The Oklahoma State Department of Health (Radiological Health Section) i will be notified of the commencement of the S.X. area decommissioning.

LU ~' The Cimarron Facility Emergency' Manual wil'1 be "upda~te~d:.Its' Appendix A will additionally include phone numbers and names of Kerr-McGee employees at the Oklahoma City office, the Technical Center and the Sequoyah Facility who can render assistance in the case of emergency.

c)

Doctors and hospitals as listed in the emergency manual will be re-orientated or indoctrinated as to the emergency medical needs which might occur.

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CIMARR0N PLUT0NIUM FACILITY SX CAMPAIGN - CRITICALITY CONSIDERATIONS & CALCULATIONS 1.

Reference:

Paragraph 2.0 - Further Cleaning of the S.X. Area Box 27A - Limited to a single 5-inch diameter 2 or 4 liter poly bottle containing hydraulic pump oil, aqueous and organic rinse solutions.

Assume oil / aqueous - solvent mixture s 50 g per Pu/ liter - From ARH600 (Criticality Handbook, Vol. 1 B2 = s 0.02502 0 m 300g Per/ liter Am (nominal reflection) = 4.15 cm M2 = 30 i

2-liter bottle B2 = Geometric Buckling, Cylinder 9

2.4052

,2 U2 -

r = cylinder redius g..

'(r + A)2 ~k(h_+~A)Z,

' h =~ cylinder [heiijht,..

~

~ ~

A = extrapolation ~ distance 2.4052 y 2 B2 ~

9 (6.35+4]5.s2 4' (15.8 + 8.3)2

= 0.0525

+

0.0170 Bj = 0.0695 which is greater than B2 of 0.025 4

4-liter (2.405)2

+

,2 O2g (6.35+4.15)2 T31.6 + 8.3)2

= 0.0525

+

0.0062

.m.

.-..~

yn.n9.~.,.l@pp.-:qys,=.+.rhn=5h?f.05SGijsfgrejMQhang y off0 0257pygg;:jg;3.g7,.m =. 7 B

[;gg;;g;;;;.. ;

, 3. u.. _ pag - _

_ azu._ e _,;;,;;;

g

.7c, 4

..: e Both the 2t and 42 poly bottles are safe.

~

1 la. Duelop unit K-eff for the 41 bottle.

(nominal reflection) of 0.025 corresponds to a much more reactive system than Note!

B2 10 gPu/t.

1 + M2B2 or 1 + 30(0.02502)-

K-eff

=

in-1 + M2 2 1 + 30(0.0587)

B 9

0.634 1.7506

=

=

2.761 i

0.634 K-eff

=

13.333(K-eff) 0 allowed = 12.333 i

=d 21.3'33.

~ 1_3_.3'33(0.634) 5m.'.,,

_. I. _. '._

c_.. _ _

n = 3.88 Hence, 2 and 4 liter bottles are subcritical by geometry for all credible concentrations of plutonium nitrate.

Notel Battelle NW Labs calculated a K-eff for optimum Pu(0)(NO )4 ~

3 assuming 2.41 in a sphere.

Analysis Number Pu-G-2 Hence, K-eff(Ref1) = 0.777

.._:..u.c.m._.:... _s

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=5 N; kb$

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  • b h5*

~ ~.. -.

_.....,_.. _ _ _ _,, a m ;,_,c a.

l i

l 1

i 1

i 1b.

Array analysis of 10 poly bottles containing oil-aqueous-organic mixture in single array. Assume 4-liter bottles, s12 inches edge to edge - single array.

A X

C X = central unit Unit h(cm)

D(cm)

L(cm).

ni A

30.48 12.7 31.6 0.38

'C 30.48 12.7 31.6 0.38

.76 3.12 3.88 - 0.76 From la a =

=

LD Where n = h /L2 2

g+h m:

a+

. +a:

.+:+

The system is safe under the assumptions made.

ic.

Assume that a transfer cart is moved to within 24 inches of the poly bottle array.

The cart contains 2 poly bottles.

(4literseachof theabovemixture.)

Unit h(cm)

O(cm)

L(cm) ni Cart Bottle 1 68.07 12.7 31.6 0.33 Upper Shelf Cart Bottle 2 60.96 12.7 31.6 0.37

.70 Adding the amount of steradians from the bottles A & C

.76 1.46 3.88 - 1.46 = 2.42 Again from la n

=

..u.= :. - 2:=ahw: deb- =. =.

3.:.

=5:--

..;. &&. i.=th:::=:= e

'.._ i t.wu x-J m The system 3 sisa E dndeM theeassumptlonstmaderi}.m;

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T,~~'9.. 9.._:_~&-.. ?. ;T. 5q. __., k.;..qqs. p g,.

7

......... ~,.,

.7 s,

SQL for 4-liter bottles - Single Array Maintain 24" edge to edge spacing.

, = =. =:: : =:.==:

=.

.: = =.=,

, _ _ -. a;;.;.:::

o e

2.

SNM Material Transfer Carts, Nuclear Safety ' Analysis Pu-G-2 Battelle Pacific Northwest Laboratories provided an extensive criticality analysis for the general use of the transfer cart in the plutonium plant.

The degree of ;ubcriticality for the material and conditions assumed showed a K-eff F 0.747 for Pu02 powder unreflected and 0.945 with full water reflection.

12 SNM carts in a 4 x.3 array is considered to be the most reactive arrangement for. SNM carts possible anywhere in the plant.

The 42 Pu02 powder can is the most reactive of the fissile materials and was used in the solid angle neutron interaction calculation.

Due to the designed spacing of cart storage rings, the fissile material from SX clean out, and the previously described analysis--BNWL-Pu-G-2, there;should not be limited movement of carts containing SNM material in proximity of other SNM material.

Suggested SOL Sign.

r m. ma #,

m_

.g. g.

yg 7

1.

Cart must be loaded with only one type of material.

2..

The 2 or 4 liter bottles must be located in the two central location rings.

3.

Cart loaded with plastic bags containing scrap: Use the single parameter limits given.in TID-7016. A 200g total plutonium load verified with NDA measurements meets the criteria.

Place about 1/2 of the load on the bottom shelf.

4.

Space carts 2 ft (minimum) from other fissile material.

3.

SNM material may be stored in single arrays.

Because of maintenenace scheduling and/or instrument failure, any array formed without NDA measurements must be "so marked, dated and recorded in the Facility Manager's Log." -Array spacing is 24" edge to edge.

Arrays formed without NDA measurements are limited to three items of like kind.

4.

Scrap material "such as piping" must be taped and packaged in 5" bundles or less.

Maintain 2-foot spacing from other fissile materials.

E,o w...n5.:.2 Scrap;DrumsM2:.to;s4;11ter bottlesxcontaining P.lutonium wi1hbe;indivduaHy,.c...

I 12WiiWEMEcotinted in sinfNDA?e4 uijmelitEEThe'ba tti esuli_U2helcement ed 71 n to'15 U onidDIE:liz' NINNES$[]

y.%5fMM%@5EiEUiU16Blig@@@QJ{tyyjjjf]

At

.m ad.

=4 g

.ap

=

e+WP,4*

F 4

s4ri pu'b..eWD Wr

+

J

+ ' * * * *

, e

'+44

.K.

2::"% %

n

239Pu as (N0 0 - molar acids.

Concentrations of Assuming 30 wt.%

Pu greater than 150g Pu/t is $,ill subcritical in this geometry.

Assume 150g Pu/t From ARH600 A = 5.95 (Reflected)

Concrete - close fitting reflector on all sides.

B2 = 0.029 m

M2 = 28 K= = 1.785 Buckling (Bj) for the 42 bottle (Refl)

B2 = (2.405)2

,2 9

(6.35 + 5.95)2 + (31.6 + 2(5.95)2 e+_:

= 0,0382i.+,0.0052:.

__._a_.;.

_. ~ =m;w B2 = 0.0434 9

K-eff =

K=

1.785

= 0.806 1+M(Bj) 1 + 28 (0.0434) 2 The system is subcritical under the above assumptions.

With nearly 19 inches of concrete surrounding the 4 liter bottle, the system is essentially isolated from nuclear interaction.

A similar analysis was performed by BNWL based on the interaction of fissile material (250 grams of Pu/ liter) stored in 5" diameter tanks contained in concrete cells.

(Cimarron - Pu vault analysis.)

6.

Slab Geometry!

The 2 inch slab is adequately subcritical.

ARH600-at 109 Pu/ liter allows for much higher slab depth. Control of slab depth j

will be maintained by transferring liquid accumulations to 2 or 4 liter f%${?$h5&bh$$N?.'15bh$kihihi$$&&&by-;i.lM"*~[fli$$2QQ2=dQ Q

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