ML19296D977
| ML19296D977 | |
| Person / Time | |
|---|---|
| Site: | 07001193 |
| Issue date: | 01/08/1980 |
| From: | KERR-MCGEE NUCLEAR CORP. |
| To: | |
| Shared Package | |
| ML19296D976 | List: |
| References | |
| NUDOCS 8003140002 | |
| Download: ML19296D977 (15) | |
Text
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O SNM-1174 TERMINATION PLANS PARTS IV, V and VI January 8, 1980 800314 000A
I.
SNM-1174 TERMINATION PLAN - PART IV
.0 Introduction Part III of the termination plan concerns the dismantlement of glove boxes and equipment of the solvent extraction area located in rooms B-05 and 127 of the plutonium plant.
Part IV of the plan concerns the removal of all the remaining glove boxes except the liquid waste cementing box.
In addition, all laboratory slot boxes will be removed as well as all tanks, piping and glovebox ventilation systems and all equipment within these boxes and slothoods.
Two to five persons assigned to a supervisor will comprise a work ce(
There will eventually be three work crews, crew A, crew B ano crew C.
Normally, these crews will work the day shift, 5 days a week. There will be three health physics technicians and their supervisor attending the monitoring needs of the crews. Crew A has already been established and is working the solvent extraction area. The current (November 1979) staff of the Cimarron facility is 23 persons which provides the administration, maintenance, security and health physics coverage presently needed. The commencement of Part IV of the decommissioning plan will require the addition of nine more personnel including another health -% sics technician. The total on-site staff will include 32 persons listed as follows:
The Plant Manager The Administration and Accountability Clerk The Security Chief and three guards The Health Physics Supervisor and six H.P. technicians The crews A, B and C including 3 supervisors, maintenance and utility persons, and decommissioning operators.
It should be noted that from the above staff, evening shifts, night shifts and weekend coverage is provided.
There are three persons on-site during those periods; one guard, one utility person and one H.P. technician.
The utility person and the H.P. technician on these shifts will not normally perform January 8, 1980
dismantlement or decontamination work, however, they will perform some tasks in support of the deco =nissioning activities:
for example, filling breating air bottles, maintaining respirators, counting air samples, etc.
We anticipate that most of the personnel (except the guards) will have previous exployment experience at the Cimarron facility.
January 8, 1980 r
2.
Part IV Plan Table No. I shows the schedule for accomplishing parts III and IV of the Termination Plan, including the work crew assignments.
TABLE N0. 1 Task 1979 1980 1981 1982 4-March
+0ec.
& May 4-Nov.
4-Apr.
4-May +Sep t<Nt No.
+-
Nov.
1 Crew A 2
Crew P 3
Crew C 4
Crew A 5
Crew C 6
Crew A 7
crew r 7
crew B The tasks shown in Table No.1 are generally described as follows:
Task No. 1 Task No.1 involves the removal of glove boxes 27A and 27B from rooms B-05 and 127, identified as the solvent extraction equipment. This task has the N.R.C. approval as license amendment No. 3 dated March 9, 1979. Accomplishment of this task will complete part III of the termination plan.
January 8, 1980 9
Task No. 2 Reference is made to pages 9-4 and 9-7 of our application dateu August 7, 1976. These pages are floor plans of rooms B-02 and 128 showing equipment locations.
Task No. 2 involves the removal of all gloveboxes and ancillary equipment from rooms No.s B-02 and 128 excepting the liquid waste cementing glovebox and its equipment located in room 128.
The drum elevator (hoist) will remain in place.
Tanks No.s 183, 184 and 185 in room B-02 and two pumps servicing these tanks shall not be removed during task No. 2.
A power transformer in the S.W. corner of room 128 shall remain. An overhead ventilation duct crosses room 128 to the S.X. glovebox (Box 278). Most of this S.X. box duct will be preserved for possible use as an extra ventilation source if needed later. Room ventilation shall also be preserved throughout task No. 2.
With the above exceptions, all processing equipment, piping, etc.
(including the 40 wall storage tanks) shall be reduced in size where necessary, packaged, and transferred to a licensed disposal site. It is estimated that the packaged volume will be 6,537 cubic ft. and that it will contain 2.24 kilograms of plutonium.
Task No. 3 Task No. 3 concerns decommissioning work in rooms No.s 80-1 and 127. Pages 9-5 and 9-8 of our 8-7-76 application are floor plans of these rooms. All gloveboxes, 20 wall storage tanks, process piping and contaminated equipment will be packaged for off-site disposal.
The safe-spaced array of 4 inch tanks located at the west end of room 127 might remain intact in the event that temporary liquid storage capacity is needed during this task or later tasks.
Glovebox vent ducts iciil be removed but the room vent ducts will remain.
It is estimated uhat the packaged volume will be 3837 cubic feet, containing 4.80 kilograms of plutonium.
Task No. 4 The drawing found on page 9-6 of our 8-7-76 submittal shows rooms No.s 123 and 124 which have been called the dry processing area.
January 8,1980
Dismantlement and disposal of the gloveboxes and processing equipment in the dry process area, not including room 122, is the scope of Task No. 4.
Again, room ventilation will remain intact after task No. 4 is completed. There will be approximately 2,588 cubic feet of packaged material containing 2.02 kilograms of plutonium.
Task No. 5 A drawing identified as SGI is found in our application section titled " Standby Physical Security Plan for the Cimarron Plutonium Plant of Kerr-McGee Nuclear Corporation". Shown on drawing SG1 are room No.s 129, 130, 131, 132, 133, 134, 135, 136, 137, 138, 139, 140. 141, 142 and 143. The total area of these rooms are designated as the laboratory area. Only the few gloveboxes, a slothood and their vent ducts need to be removed to nearly return this area and most of its equipment to an uncontaminated status.
Task No. 5 involves the removal of the laboratory gloveboxes, slothood and their ductwork as well as any non-salvagable equipment within these enclosures. Task No. 5 also includes removal of the maintenance glovebox from room No. 116 (maintenance shop). A volume of 2,853 cubic feet of packaging is expected.
Previous NDA measurements show 18 grams of plutonium is contained in this material.
Task No. 6 During previous tasks, glovebox exhaust ventilation ducts were removed from between the boxes and the intermediate filter which services the box. The glovebox ductwork was blinded ahead of the intermediate filter housing. Task No. 6 involves removing the secondary (intermediate) filters and housings and the ductwork leading to the final filter bank in the air exhaust room. There are 15 intermediate filter housings.
These are located as follows:
January 8, 1980 -
Intermediate Filter Locations Room No.
Quantities Remarks B01 1
Cold Chemical Storage 2
These two filters are located on the vault roof. They service sys-tems originating in room B-02.
116 1
121 1
This box was used to ventilate the drier used to dry washed fuel p'9s.
123 1
124 1
127 1
128 2
One of these filters serviced the solvent extraction glovebox system an the other serves the gloveboxes in room 128.
129 1
132 1
133 1
135 1
143 1
Januray 8, 1980
It is estimated that task No. 6 will generate 6,480 cubic feet of packaged material for disposal. There is an estimated quantity of 70 grams of plutonium in this equipment according to previous non-destructive assay (NDA) measurements.
Task No. 7 Task No. 7 involves dismantlement and disposal of those portions of the final filter system which services the solvent extraction ventilation exhaust and all glovebox exhausts. The laboratory fume hood exhaust system and the room air exhaust systems for all rooms will be retained. Approximately 2,952 cubic feet of material will be generated for disposal during the activities of task No. 7.
Previous NDA measurements of this equipment showed no "above back-ground" levels for plutonium quantity assignment.
January 8,1980 II. SNM-1174 iERMINATION PLAN - PARTS V & VI 1.
Introduction _
Part V and Part VI of the termination plan was generally des-cribed in our letter of November 8,1977 to Mr. Richard Starostecki.
Parts V and VI are now combined and are designated as Task No.
Accomplishment of task No. 8 will complete the decommissioning 8.
activities.
2.
Task No. 8 Work crew A should begin Task No. 8 near the 1st of September 1982.
Work crews B and C will join in the task near the beginning of November 1982. The decommissioning should be completed by March 1983.
Task No. 8 involves the decontamination of all internal building surfaces and ventilation systems.
It also. includes the excavation of the outside liquid waste storage tanks, removal of piping to the now extinct evaporation pond and disposal of the cementing glovebox and its equipment from room 128. The drum elevator in room B-02 will be decontaminated or removed as well as tanks No. 183,184, and 185 and two pumps in room B-02.
The 4 inch dia. storage tanks possibly remaining in room 127 will also be removed. The estimated volume of waste requiring 3
disposal at a licensed disposal site is 3710 ft. The N.D.A.
counting previously conducted shows 72 grams of plutonium contained in this material.
III.
Further Discussion of Tasks No. 2 through No. 8 Monitoring, contamination controls, administrative controls, precautions and procedures will apply as described iin our letter of November 8,1977 " General Aspects of the Termination Plan" and car letter of October 11,1977 " Termination Plan Part I".
Tasks No.s 2 through No. 81c.volves 1) removing equipment from gloveboxes, 2) " fixing" the centamination on the interior surfaces of gloveboxes, then disassembling or cutting them into sizes suitable for packaging, 3) pipeline and conduit January 8,1980 disassembly, 4) storage tank removal, 5) glovebox filter and ductwork removal and finally, 6) decontamination or disposal of equipment external to the gloveboxes and decontamination of building surfaces. Non-de~ uctive analysis (flDA) will be performed for all contams ted material involved in these tasks to determine the quanthy of plutonium present.
Proper packaging will be pre ed for the contaminated waste to help assure safe delivery to a licensed disposal site.
After a room has been emptied of its gloveboxes and eo-ipment, it may be designated as a temporary storage area for packaged waste material awaiting shipment.
1.
Removing Equipment from Gloveboxes
" Bag-out" procedures are used to remove equipment from gloveboxes.
Equipment is removed whole unless it is too large or too heavy to be safely manipulated. Some equipment will need to be disassembled before bagging-out. Other items inside of glove-boxes such as piping, may need to be cut to remove it efficiently.
Care will be exercised that no electrical devices or conduits are energized when work begins to remove them.
Similarly, gas lines and liquid lines will be evaluated for hazardous contents and handled accordingly.
Some gloveboxes will need additional glove ports or bag-out ports installed on them to facilitate equipment removal. This procedure has been accomplished many times by our experienced personnel.
2.
Glovebox Removal After equipment is removed from the glovebox, damp wipes will be used to clean the box interior. Remaining contamination on the inner surfaces will be " fixed" using paint or other coatings.
The box will then be disassembled and packaged.
The disassembly and packaging work is done within a " greenhouse" enclosure.
Precautions are taken when using cutting torches or other open January 8,1980 8-
flames within plastic " greenhouse" enclosures to assure that flames or hot materials cannot ignite or penetrate the plastic enclosures. When dismantling those portions of a glovebox that can alter differential pressures in other portions of the ventilation systems, precautions will be taken promptly to adjust and restore differential pressures and ventilation flow in any remaining portion of the system.
3.
Pipeline and Conduit Disassembly Pipelines and electrical conduits which are external to the gloveboxes and which have been disconnected from the boxes are disjoined or cut to size for packaging. Bagging techniques are used. Long sections of pipe may be cut to shorter lengths within a special portable glovebox containing cutting tools.
These types of procedures are more thoroughly described in our letter of October 11, 1977.
4.
Storage Tank Removal There are 20 wall storage tanks in a wall common to rooms B-01 and 127. There are also 40 wall storage tanks in another wall which is common to rooms B-02 and 128. The top of these walls terminate about 3 feet below the ceilings of rooms 127 and 128 respectively. After removing the piping connected to the tanks, the tanks must be raised 1 - 2h feet into the free space beneath the ceiling. A piece of the pipe about 18 inches long will then be cut off. The pipe wi'l be raised and cut repeatedly until it is completely removea from the wall.
Jacks and come-along devices will be used to lift these wall tanks. Provisions will be made to provide effective ventilation controls and confinements to prevent the release of radioactive material to the general building environment.
The array of 4 inch diameter tanks located at the west end of room 127 will be removed. The " low level" liquid waste storage tanks No.s 183,184, and 185 in rec: B-02 and the outside underground liquid waste tanks may be removed after it has been determined that there is no longer a possible need for them. These large tanks may remain in place if they can be decontaminated.
January 8, 1980
_g_
5.
Glovebox Filter and Ductwork The glovebox air intake filters and the primary exhaust filters are removed during glovebox disassembly. The exhaust ductwork to the intermediate filter housing is then removed. The remaining task (Task No. 6) involves the removal of the secondary (inten'ediate) filters and housings as well as the ductwork between the intermediate filter housing and the final filter header in the air exhaust fan room. The final filter system servicing the gloveboxes is then removed.
" Greenhouse" procedures are in use during this type of work.
6.
Building and Remaining Equipment The final work consists of decontamination activities of building surfaces and equipment which had not been in gloveboxes.
This contamination is generally very low level. A few known locations have contamination " fixed" by paint.
Paint " stripper" is used to remove this contamination. A thorough contamination survey will be conducted. " Greenhouse" type operations may. be used when concrete surfaces need to be mechanically reduced to remove contamination. Cleaning liquids (mop water, etc.)
obtained from this decon. work is solidified with portland cement within a 55 gallon drum. When all such cleaning is done, the canenting glovebox and its equipment will then be dismantled and packaged.
At the conclusion of the decontamination efforts in the building, the room ventilation system, lighting, heat, water and natural gas, the air sampling vacuum pump and pipeline system will remain. The laboratory fume hood system shall also be intact as will several benches and tables. The large liquid storage tanks and certain other equipment successfully decontaminated may remain. The 1st-aid Emergency Building located near the plutonium fuels building will also be stbject to release from licensing.
January 8, 1980 IV. Other Safety Considerations Many safety considerations were discussed in the preceeding section.
Our application dated November 29,1978 "SNM Termination Plan Part III" describes several others which are of the type which will be continued in effect as necessary throughout the conduct of tasks No.s 2 through 8.
1.
Criticality Safety As in the S.X. system, decommissioning (Part III), liquids generated while cleaning glovebox interiors is given criticality consideration. Liquids collected as a result of glovebox clean out, process equipment, pipeline or tankage drainage will be placed in 5 inch diameter, 21 or 41, poly bottles.
Each bottle shall be NDA counted promptly before it is placed in a safe storage array to assure that it contains no more than 2.0 kgs. of plutonium. A maximum of two of the 2t or 42 liquid containers shall be permitted at the work station where the plutonium content of the containers with more than 35g of plutonium is to be subdivided. The work station shall be at least two feet from any other plutonium.
2.
Contamination Control A principal safety consideration during the dismantlement activities involves the monitoring and control of the potential spread of plutonium contamination. Several factors combine to minimize, and otherwise mitigate, the potential for uncontrolled contamination spread. These factors are described below:
During dismantlement of the internal glovebox equipment, which is expected to contain the most heavily contaminated material, the glovebox external structure will remain intact and a negative differential atmospheric pressure will be maintained from the outside to the inside of the glovebox.
In addition, the plutonium plant's building ventilation system will continue to function and operate as designed for normal plutonium fuel fabrication operations. When dismantlement of the glovebox external structure is in progress, special greenhouse enclosures will be devised and special procedures will be used to prevent the spread of contamination. These special procedures and
,g,
January 8, 1980
precautions are described in Section 3.2 of KMNC's application dated November 29, 1978.
In addition, in each room where dismantlement activities are performed, at least one constant air monitor with alarm (CAM) will be operating.
Also, at least 50% of personnel working in respirators are required to wear lapel air samplers. Monitoring for surface contamination will be accomplished in accordance with KMNC procedure KM-NP-10-66. Monitoring 'or nasal smears and bicassay sampling will be accomplished in accordance with KMC procedure KM-NP-10-67.
Finally, glove and bag changing will be accomplished in accordance with KMNC procedure KM-NP-31-6.
These procedures incorporate requirements for activities when the plutonium fuel fabrication plant was in full operation. They are appropriate and satisfactory for the purposes of dismantlement activities.
3.
Fire Protection When using small portable torches for specific cutting operations that cannot be accomplished ay other means, special precautions will be taken to insure fire protection. These include pre-planning and control using the Special Work Permit system described earlier. Secondly, portable fire extinguishers will be placed inside the tent or greenhouse enclosure for use by an operator. Because of potential problems that could arise with the use of a torch or open flame within the greenhouse enclosure, special precautions will be taken such that the flames or hot materials produced by cutting actions cannot ignite flammable materials in the greenhouse enclosure.
4.
Ventilation Control Dismantlement activities have the poter:tial to locally disperse plutonium contaminated material. Although this material is expected to be substantially in a dried solid form that is not readily dispersible, some of the cutting or other dismantling activities have the potential cause local spreading of plutonium-bearing material. As a result, and as is normal practice during plutonium fuel fabrication operations, a key method of preventing the spread of contamination is the use of a properly January 8, 1980 designed and balanced ventilation system. This principle of prevention of contamination spreading through ventilation control also applies during the dismantlement of Gloveboxes.
Included in this method of ventilation control is the fact that the building's ventilation system and ficus will be that designed for fuel fabrication operations. As described in Section 11.3 of the amendment application dated November 29, 1978, during the solvent extraction decommissioning activities, two building supply and exhaust fans will be in operation.
In addition, the exhaust stack air sampler and alarm system will be in constant use.
During some dismantlement activities associated with gloveboxes, the potential to alter building ventilation system flows and differectal pressures exists.
As a result, a provision is included which requries the monitoring for ventilation flow and di#ferential pressure imbalance and for corrective action to be taken promptly to restore proper ventilation flows and differential pressures.
5.
Environmental Considerations The decommissioning activity sequence will take place in such a fashion that provisions for high efficiency air effluent filtration is maintained for the plutonium plant throughout the entire activity. No liquid effluents other than sanitary discharges are released. As a result, any effect on the surrounding environment is insignificant.
In addition, careful packaging of the plutonium waste in approved containers with proper transport to an authorized disposal site will remove any future threat to the environment near this facility.
V.
Accountability and Safeguards Procedures as outlined in our application of November 29, 1978 are applicable. We request that License Amendment MPP-3 be revised to extend the conditions placed on gloveboxes 27A and 27B to encompass the total completion of the decommissioning (termination) plans of license No. SNM-1174.
January 8, 1980 3-15151