ML20090H849
| ML20090H849 | |
| Person / Time | |
|---|---|
| Site: | Barnwell File:Allied-General Nuclear Services icon.png |
| Issue date: | 10/14/1983 |
| From: | ALLIED GENERAL NUCLEAR SERVICES |
| To: | |
| Shared Package | |
| ML20090H837 | List: |
| References | |
| NUDOCS 8405220010 | |
| Download: ML20090H849 (30) | |
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ALLIED-GENERAL NUCLEAR SERVICES BARNWELL NUCLEAR FUEL PLANT DECOMMISSIONING PLAN l October 1983 i
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. o GLOSSARY AEC ...amic lnergy Commission AGNS - Allied-t sneral Nuclear Services AWR_ - AGNS Work Recues t=
BNFP' - Barnwell Nuclear Fuel Plant CFR - Code of Federal- Regulatio'ns CNSI - Chem-Nuclear Sys tems , Ind.
DOE - Department of Energy
'FAA - Federal Aeronautics Administration '
FRSS - Fuel Receiving and 'S torage S tation HCLA - Hot and Cold Laboratory Area
. HP - Health Physics HWP - Hazardous Work Penbit LTRC - Lower Three Runs Creek LWR - Light Water Reactor MTU - Metric Tons of Uranium NRC - Nuclear Regulatory Commission OSC: - Operational Safety Committee RWP - Radiation Work Permit R&D - Research and Development SCDHEC - South Circlina'Depctrteent of Health and Environmental Control SEC' - Safety and Environmental Control S RP - Savannah River Plant TBP - Tributyl Phosphate-TRU - Transurtnic UF 6 - Uranium Hexafluoride WTEG - Waste Tank Equipraent Gallery m
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. 1 TABLE OF CONTENTS PAGE GLOSSARY
1.0 INTRODUCTION
................................................ 1 1.1 Purpose........................................'......... 1 1.2 Ge ne ral B ac k gr ound . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.3 Re as on fo r S hut down . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 BNFP DE SC RIP TION AND HIS TORY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.1 S ite Loca t ion and Des crip t ion . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.2 Sep ara t ions Fac ili ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.3 Ur an ium He xa f luoride F ac ili ty . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2.4 Hot and Cold Laboratory Area ........................... 4 2.5 Other .................................................. 5 3.0 DECOMMISSIONING OBJECTIVES .................................. 9 4.0 REGULATORY REQUIREMENTS ..................................... 10 5.0 MANAGEMENT PLAN ............................................. 11 5.1 Manageme n t O rg a niz a t io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 5.2 Qua li ty As s uranc e and S a f e ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 5.3 Consultant .......................'...................... 11 6.0 DECOMMIS SIONING PLAN AND ANTICIPATED RESULTS . . . . . . . . . . . . . . . . 14 6.1 .
S ep a r a t io ns F ac i l i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 6.1.1 Process Systems ................................. 14 6.1.2 Proces s Building Cle anup . . . . . . . . . . . . . . . . . . . . . . . . 15 6.2 Uranium Hexa fluoride Facility . . . . . . . . . . . . . . . . . ; . . . . . . . . 15 1
6.2.1 Ge n e r a l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . :. . . . . . . . . 15 6.2.2 Carbon Steal Piping and Equipment ............... 15 6 . 3 . Ho t and C o l d Lab ora to ry ' Ar e a . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 I 6.3.1 Ge n e r a l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 l 6.3.2 Port able E quipment and S upplies . . . . . . . . . . . . . . . . . 16 6.3.3. Hoods and Glove Boxes ........................... 16 6.3.4 W a s t e S ys t em . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 17.
6.4 Other ..............,................................... 17 6 . 4.1 - Waste Tanks ..................................... 17 6.4.2 Support Buildings ............................... 18 111
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TABLE OF CONTENTS (CONTINUED)
PAGE 7.0 DISPOSITION OF SURPLUS EQUIPMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 7.1 Disposition of Equipment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 7.2 Radiological Controls .................................. 19 8.0 WA S TE D IS PO S AL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 8.1 Radio ac t ive Non-Trans uranic . . . . . . . . . . . . . . . . . . . . . . . . . . . e. A
- 8. 2 _ Radio ac t ive-Tr ans ur anic . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 8.3 No n-R ad i o a c t ive . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 9.0 ENVIRONMENTAL IMPACr OF DECOMMIS SIONING . . . . . . . . . . . . . . . . . . . . 22 10.0 FINAL STATUS AND CONTINUED SURVEILLANCE . . . . . . . . . . . . . . . . . . . . 23 11.0 DOCUMENTATION .............................................. 25 TABLES Table No. Title Table 7-1 HP Rele ase Code Cla s sific a tion . . . . . . . . . . . . . . . . . . . . . . 20 FIGURES Figure Na Title '
Figure 2-1 BNF P S i t e L o c a t io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 ,
- Figure 2-2 Aerial Photograph BNFP Site and Surrounding Areas . . . 7 Figure 2-3 Plot Plan of the Barnwell Plant . . . . . . . . . . . . . . . . . . . . . 8 Figure 5-1 AGNS Management Staff ............................... 12 Figure 5-2 Decommis sioning Project Organiz ation . . . . . . . . . . . . . . . . 13 1
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1.0 INTRODUCTIO_N.
't 1.1 Purpose This Plan has been prepared to describe fully the decommissioning of the Barnwell Nuclear Fuel Plant (BNFP), including non-radiological con-
! siderations and non-licens ed f acilities , in a single, c ompr ehe ns ive ,
document. Therefore, the procedures' and status described herein are not i necessarily intended to reflect license requirements. Proposed specific I license conditions will be submitted' as part of the BNFP license amend-ment applic at ion.
1.2 General Background The BNFP was designed and cons tructed, as a privately owned facility, to process light-water reactor fuel equivalent to 1500 metric tons of 4
uranium per year. A Construction Permit was applied for on November 6, 1968 and issued (as CPCSF-4) by the Atomic Energy Commission on December 18, 1970. Construction be gan in early 1971 and presently existing facilities were ess' ntially e completed by mid-1976.
These facilities provide for fuel receiving and storage, separation of
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the uranium, plutonium and fission products in the spent fuel, conver-i sion of uranyl nitrate solution to uranium hexafluoride (UF 6 ), storage of plutonium nitrate and liquid wastes and for laboratory analyses and research. As these facilities we.re completed, cold testing for operability was conducted using natural uranium as surrogate fuel. g no time has spent nuclear reactor fuel been present at the BNFP. During
, this period applications were made for other requisite Federal licenses and permits.
1.3 Reason for Shutdown l
i On December 23, 1977, responding to an abrupt reversal of long-s tanding governmental policy, the Nuclear Regulatory Commission terminated all licensing proceedings related to reprocessing and recycle of recovered products, leaving undisturbed, however, the BNFP Construction Permit.
Promptly thereafter, in early 1978, recognizing the BNFP as a national asset, the Congress authorized and provided funding for research and development programs at the BNFP in support of national policy. This R&D work, which continued through July 1983, involved use of all on-site facilities other than the Uranium Hexafluoride Conversion Facility which l
was deactivated and placed in standby stat'us.
In December 1982, the Congress passed a resolution which specifi.ed that "no Federal funding is provided for any activities at the Barnwell Plant l beyond July 31,.1983." Proceeding on that basis, activities leading to' ,
I an orderly shutdown of the BNFP by year-end 1983 were initiated in May.
l There is continuing indus try/ utility interes t in the possibility of l making a proposal to the Department of Energy for ' future operation of l-i . , . . . ... ... . . . _ . _ ..,..
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-the BNFP. If such proposal is made, it may be possible to modify the ongoing shutdown program. However, in the ab s enc e of such proposal, activities leading to shutdown in December 1983 continue. These activities include implementation of this Decommissioning Plan.
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2.0 BNFP DESCRIPTION AND HISTORY !
t 2.1 Site Location and Description The BNFP is located about 7 miles west of the City of Barnwell on a site of approximately 1706 acres of land of which approximately 200 acres have been cleared. This site is situated in a predominantly rural area in Barnwell County, South Carolina. The plant base line reference is positioned at the approximate Mercator coordinates of la titude 33*15 '0" N and longitude 81 '29 ' 20" W (South Carolina S tate Lambert coordinates Y:516,100 and X:1,850,300).
The BNFP site is bounded on the west and south by the DOE Savannah River Plant (SRP) reservation, on the east by the Chem-Nuclear S ys tems, Inc. )
(CNSI) site, and on the north by the Barnwell County Industrial Park.
The location of the BNFP site with respect to South Carolina and Georgia is shown in Figure 2-1. The site perimeter relative to surface streams, abutting properties , industrial plants, and other items of specific interest within a five-mile radius is shown in Figure 2-2.
The BNFP site is largely forest land, with a small number of abandoned farm fields undergoing secondary succession, and several Carolina Bays.
Fores tation consists of loblolly pine plantings, mixed pine fores ts, and mixed pine-hardwood (scrub oak) forests.
There are no natural streams on the BNFP site.
The plant site is wholly-owned private property. A right-of-way fo r Osborn Road, which is the principal acces s road to the site, has been granted to the State of South Carolina. An easement for the power transmission lines that supply the BNFP has been granted to South Carolina Electric and Gas Company. The railroad spur serving the Fuel' Receiving and Storage Station (FRSS) within the site boundary is wholly AGNS-owned.
A plot plan of the BNFP plant area showing significant fe atures is pre-sented as Figure 2-3. A chain-link exclusion fence has been ins talled around the plant area..
2.2 Separations Facility The Separations Facility was. designed to proces s 1,500 me tric tons of uranium (MTU) per year at a daily rate of 5 MTU/ day. The -lant was designed for processing fuel elements that prior to irradiation had a fissile material content of 'up to 5% U-235 or the equivalent for plutonium fuels.
The process systems in the 'BNFP for the recovery of special nuclear material are an adaptation of the Purex solvent extract ion proces s , fo r j which the technology and risks are well-defined. l l
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The Separations Facility includes five (5) contact maintenance cells, two (2) remote maintenance cells, tw o (2) plutonium nitrate storage
'celIs and associated equipment, e.g., pumps, ins trume r.c a t io n , and piping. Only liquid process equipment in the Sepa. ativas Facility has been exposed to solutions containing uranium (natural only). No plutonium has been used in any process area. Process support equipme nt ,
such as the shear and cranes , has not had direct contact with uranium.
The plutonium nitrate storage cells and auxiliary systems have not been in contact with uranium. Closed-loop cooling war.er and steam generating systems are clean; however, their status will be verified. The status of the Plant's ventilation systems will also receive cons ide r a tio n
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depending on areas it se rv ic ed , some of which have been exposed to natural uranium. Generally, residual in-cell. natural uranium contamina-tion levels were less than 1000 dpm/100 cm2 a anii 2000 dpm/100 cm2 gy smearable prior to the start of decommissioning. Proces s piping .and vessels that have contained solutions of natural uranium may have higher -
levels. Such levels in normal access areas, (e.g., operating stations, piping and ins trument galle ries , s tairwells and hallways), in general are less than 50 and 500 dpm/100 cm2 a and By smearable , respectively.
2.3 Uranium Hexafluoride Facility The UF6 facility contains equipment to convert uranyl nitrate to uranium hexafluoride. This equipment is housed in an eight-s tory me tal fr ame building. Some of the process-related equipment, such as piping, calciners, screw conveyors, bag houses,' and vessels, has been in direct contact with uranium, in mo s t cases in the fo rm of uranium oxide powde rs . Auxiliary systems and areas, 'such as compres sors , refrigera-tion, fluorine production and UF6 cylinder loading / unloading , have not been in direct contact with uranium. RIesidual uranium levels in normal access areas are comparable to those that exist in the Separations Plant.
2.4 Hot and Cold Laboratory Area The Hot and Cold Laboratory Area contcins a temporary lunchroom, a change and locker room, Health Physics support offices, and laboratories.
The Analytical Chemistry Laboratories consist of individual laboratories equipped to provide specific type s of analyses or . se rv ic e s . The laboratories include all facilities required for analyzing samples for purposes of process control, accountability and safeguards, product and raw material specifications , and process ins trumentation calibration.
The Analytical Chemistry Laboratories have been used for DOE-sponsored research and development work, support of plant cold testing, and analytical procedures development. Radioactive materials have been used in all of the laborato ries . Plutonium has been used in six labora-tories; thus, the hoods and glove boxes in these six lab ora t o r i e s contain residual TRU.
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i i The Engineering and Technical Laboratories consist of ar. Engineering i
Laboratory, Alpha Laboratory, Radiochemical Lab o r a to ry , and Cold l Chemical Laboratory.
j The Engineering Laboratory cons is ts of pilot plant scale eq uip me n t ,
e.g., stainless steel tanks up to 500 gallons capacity (15-20 ves sels ),
- pumps, heat exchangers , ins truments, three glass pulse columns, pulsers ,
laboratory. t i .
. The Alpha Laboratory contains three very large glove boxes and one i standard fumehood. One box (18 'L x .10 'M x 2.4 'D) contains solvent .
extraction pulse columns and ancillary equipment, such as glass vessels, !
'; pumps, stainless steel tubing, and valves. A second box (approximately 25 'N x 10 'L x 5 'D) is used for waste solution handling. This box contains a vacuum pump, stainless steel tank, glass mixing vessel, and several 26-liter polyethylene bottles for storage of waste. The third glove box is used for analytical tes ts. All three glove boxes will '
contain residual plutonium.
1 The Radiochemical and Cold Chemical Laboratories are standard chemical laboratories containing fume hoods, normal bench tops, and sinks, and i are equipped with standard chemical labware. These laboratories have been used for work with natural and/or depleted uranium and by product tracer level radionuclides. No plutonium has been used in the Radio-i chemical and Cold Chemical Laboratories.
2.5 Other I
The Fuel Receiving and Storage Station (FRSS) contains a cask testing l and decontamination pit, two (2) cask unloading pools, a fuel storage l
pool, and associated pool water cooling and tr e a tme n t equipme nt and .
handling cranes. The FRSS has not been exposed to radioactive i materials.
The Waste Tank Equipment Gallery (WTEG) houses the pumps, piping, and equipment for maintaining and sampling the three (3) underground liquid j
waste storage tanks. Some transfer and sampling lines have contained
, uranium solutions , but the general area is clean. Two of the three j .
underground storage tanks have also contained uranium-bearing solutions.
4 Support facilities, such as the utility area, administration buildings, j shops, and warehouses have never been exposed to radioactive materials.
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T@ORAPH APERTURE SCALE 1" = 7 0 0 0* l L R@UNDING AREAS U, DATE OF PHOTOGRAPHY : 10/14/1980 SOUTH CAROLINA 8405220010-:01
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PLOT PLAN OF THE BARNWELL PLANT FIGURE 2-3 l !
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3.0 DECOMMISSIONING OBJECTIVES The objective of the BNFP Decommissioning Plan is to place the BNFP facilities and the site in such a condition that a minimal level of radiological controls and security will be required following shutdown.
The Plan is consistent with preserving the option of reprocessing at the BNFP in the near term future. However, should a decision be made later that the reprocessing option no longer needs to be preserved, then the plan provides that the future level of ef fort necessary to place the f acilities in an " unrestricted use" status also should be minimal. To 3 accomplish the Plan's objectives, source, special nuclear, and by product materials will be removed from the site. Low levels of .
residual natural uranium will remain on the interior surfaces of process piping and vessels. In addition, some residual plutonium contamination will remain on the interior surfaces of glove boxes. The TRU glove boxes will be isolated from ventilation systems and securely sealed.
The exterior surfaces of equipment and structures will be cleaned to the "unres tricted use" levels set forth in NRC Regulatory Guide 1.86.
Selected equipment outside of process cells will be salvaged and sold.
All waste will be disposed of in accordance with existing regulations.
AGNS will submit to the SCDHEC an ap p lic a t io n to amend its existing s tate radioactive material license to a " possession only" licens e . The facilities will be closed and all access points secured. Continued surveillance will be provided as de s c rib ed in Section 10.0 of this plan.
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4.0 REGULATORY REOUIREMENTS Allied-General Nuclear Services (AGNS) has been licensed by the State of South Carolina to pos ses s and use radioactive materials. The State regulations governing the use of radioactive materials are published in
" Rules and Regulations for Radiation Control, Regulation No. EC-1." The shutdown and decommissioning of the BNFP will be conducted under these regulations and in conformance with existing AGNS procedures which are incorporated by reference in the S tate license. Although the State regulations do not specifically address de c ommi s s io n ing , Section RHA 2.19 states that the " Department may terminate a specific license l upon request submitted by the licensee to the Department in writing." It is intended that this decommissioning plan and the supporting docu-mentation which will be generated during the course of decommissioning will support an application to amend AGNS' current State license to be a
" posses sion only" licensee.
A second set of applicable regulatory requirements is associated with the AGNS Construction Permit granted under 10 CFR Part 50. 10 CFR 50, paragraph 50.82 states that "a licensee must submit decommissioning plans to the NRC." However as with State Regulations, no specific guidance is provided. The NRC recently revised 10 CFR Parts 30, 40, and 70 for the purpose of establishing procedures for termination of licenses. Although these revisions address the ques tion of acceptable levels of residual radioective materials, no specific limits were established. Regulatory Guide 1.86, " Termination of Operating 1.icense for Nuclear Reactors," dated June 1974, included by reference in numerous NRC-issued licenses as guidelines for release of facilities 'for unrestricted use, will be so used during the decommissioning activities.
All other applicable State and Federal regulations governing packaging, transportation, and disposal of radioactive and hazardous materials, shutdown of sanitary waste treatment facilities , inert industrial waste landfills, etc., also will be followed. .
l
i 5.0 MANAGEMENT PLAN 5.1 Management organization The AGNS preseni, management organization is depicted in Figure 5-1.
Dr. J. A. Buckham, President, has appointed J. H. Ellis, Director, Operations, to be Chairman of the BNFP Shutdown Steering Committee. The Committee has the responsibility for detailed planning, scheduling, and conduct of the plant shutdown and decommissioning program. Other committee members are:
J. L. Aughtman - Manager, Procurement and Material Control l* J. H. Mestepey - Manager, Plant Engineering and Maintenance J. J. Jernigan - Controller M. Hawkins - Nanager, Safety and Environmental Control 1
i The functional decommissioning project organization is shown in Fig-ure 5-2.
5.2 Quality Assurance and Safety l
Quality assurance considerations will be in conformance with the BNFP Quality Assurance Program as set forth in AGNS Policy and Procedure Q-11. The program will be utilized to monitor and provide documented evidence of activities during the period of decommissioning.
The AGNS Operational Safety Committee (OSC) will remain functional dur-ing the decommissioning period'. The OSC provides a management oversight function to assure that activities conducted at the BNFP are carried out in a manner consistent with the safety policies of AGNS and in con-formance with all spplicable regulations.
5.3 Consultant AGNS has contracted with Rockwell International of Canoga Park, Cali-fornia as a consultant to provide an independent review of the BNFP decommissioning program. This action was taken to provide ad de d impartial and objective assurance that the decommissioning program is properly planned, documented and performed. Rockwell has conducted an initial review, resulting in a number of recommendations all of which have been incorporated in this decommissioning plan. Rockwell will also perform an independent radiological survey to ve rify the final radio-logical status of the facilities. This consultant is to prepare reports addressing the adequacy of the decommissioning plan and procedures, as well as perform periodic reviews during the course of decommissioning.
A final report summarizing the results of the decommissioning program will be prepared. This final report will be available for review by appropriate regulatory agencies as will other supporting documentation.
11 -
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+As part of the shutdown plan these employees have been terminated and the positions are now vacant.
e ACMS MANAGEMENT STAFF i
l FIGURE 5-1
s Prograss Manager *
- .g John H. Ellis Alternate
! Monte Hawkins AGNS Operational ~ ~ ~ ~ ~ - ~ ~ - - - - - - - -
Safety Cosemittee George T. Stribling.
Chajrman Quality Assurance Shutdown and Control - .... . .......
. Steering M. L. Rogell- Comunittee
, < Manager ,
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Separations facility UF. Facility Safety & l.nvirosamental Lab. Decesselssioning Waste & Muclear Material
.-- Decoussissioning Decesselssioning Control George A. Huff.' Processing Disposal ~
W James H. Mestepey,* Monte Hawkins.* Manager . Ken E. Plumeser.
Ken E..Plusiner.
a c--rl=a m e saanerlatendent Manager Analvtical Services Superintendent. Separations
~
l i 1 i Equipment Identification Budget & Cost Equipment itemnval Records Documentation
& Disposition Jerrel J. Jernigan.* James H. Mestepey. Georgia F. Fields, gggt, g g,,,,. Cor. troller - Manager ^ Manager y,, Plant Eng. & Maint. Office Services Procurement b terial l Contrwi L 'f f
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DECOMMISSIONING PROJECT ORGANIZATION FIGURE 5-2
6.0 DECOMMISSIONING PLAN AND ANTICIPATED RESULTS Existing AGNS procedures will be followed during decommissioning opera-tions. A Hazardous Work Permit, Radiation Work Permit, AGNS Work Request and/or Work Instruction will be issued by AGNS to cover items of work in order to provide written ins tructions , to assure compliance with existing procedures and regulations, and to document that the work was done.
Disposal of non-TRU Radwas te , TRU waste, non-rad waste, and non-rad hazardous waste will be governed by existing AGNS procedures.
6.1 Separations Facility 6.1.1 Process Systems Proces s solutions will be removed from process vessels and piping.
Unused TBP and diluent will be removed from their respective feed tanks.
Solvent with uranium contamination will be cleaned with sodium car-bonate. Process solutions will then be packaged for of f-site disposal or sale. Approximately 14.5 MTU of DOE-owned natural uranium, in the form of uranyl nitrate solution, will be shipped
In order to remove residual quantities of uranium and reduce residual internal levels in the Separations process equipment and piping , nitric acid and water flushes will be performed. Internal smear surveys will be taken from selected vessels and piping sections prior to performing an initial acid flush. Solution samples will be taken before and after
" flushing" so that the ef fectiveness of this flushing can be determined.
Additional (repeat) internal smear surveys will also be taken. Where i indicated, vessels will also be flushed with sodium carbonate solutions to remove organic residues.
Data collected from this initial flush will be used to de't e rmine if. an additional acid flush is required on all or part of the process. Waste generated from these acid flushes will be collected in a waste tank.
i Following these acid flushes, a water flush will be performed and pro-cess vessels and piping .will be filled to overflow. A final dilute acid flush will then be performed to enhance clean-up and to assure passi-vation of the internal surfaces of the piping and ve s s e ls . All flush solutions will be collected and prepared for of f-site disposal.
Records will be maintained to document the history of clean-up of major vessels and process systems (internal residual levels, type and number of flushes, etc.).
- Shipment was completed on September 26, 1983.
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It is expected that the above cleanup and flushing program will result in residual uranium levels on the interior surf aces of process piping and ves sels of le s s than 1000 dpm/100 cm2 sme arable natural uranium '
alpha.' The results of the flush solution samples and smear surveys of the interior surfaces of process systems will be analyzed to verify this expected result.
6.1.2 Process Building Cleanup All areas of the process building (contact cells, remote cells, gal-1eries, stations, and areas) will be cleaned to levels as low as practicable . Direct radiation levels in the buildings will not exceed background. Final radiological surveys will be performed.
To the extent practicable, all wood, paper, flammable liquids, and other combustibles will be removed from the process building.
Cell ventilation lines will. be surveyed by Health Physics (HP), and closed off. Ventilation and of f gas filters will be lef t in place.
After clean-up is complete, all water will be shut of f and all lines drained. All electrical service will be de-energized and the buildings secured.
6.2 Uranium Hexafluoride Facility 6.2.1 General The same general procedures will be followed for cleanup of the UF6 Pro-cess system and building as are described for the Separations Facility.
6.2.2 Carbon Steel Pipins and Equipment Some sys tems in the UF 6 Facility have been in contact with natural uranium powder. Because they are constructed of carbon steel, these systems cannot be flushed with nitric acid. These sys tems will be identified, opened, and vacuum cleaned. They .will then be physically removed from the facility. Piping will be discarded as non-TRU waste.
Where practicable , equipment such as conveyors , blowers , valves , etc.,
will be trans ferred to Allied Corporation's Metropolis , Illinois Facility. These items will require HP approval . prior to disposal or shipment.
6.3 Mot and Cold Iaboratory Area 6.3.1 General The laboratory area of the BNFP consists of analytical chemis try laboratories, an engineering laboratory and an alpha- laboratory. The analytical chemistry laboratories are equipped with hoods, glove boxes,
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work tables, and the necessary analytical chemistry equipment to perform sample analyses for process control, accountability and safeguards, product and raw material analyses. The engineering and alpha labora-tories contain pilot plant scaled equipment and have been used for process development work.
l The general plan for decommissioning the laboratory areas is to remove all radioactive sources, contaminated equipment and any other radio-active materials. Fixed work table s , hoods, and glove boxes will be left in place. Floors, ceiling, counter tops, and if pos sible , the interior of hoods will be teleaned to AGNS Zone II limits which are 50 dpm a /100 c.2 and 500 dpa sy/100 cm2 , smearable. The interior I surf ace of the glove boxes :which have not contained Pu will also be '
cleaned to Zone II limits. .
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The laboratory area also contains administrative of fices for laboratory personnel, a temporary lunchroom, and Health Physics support offices.
All of these areas will be cleaned to Zone II limits. It is expected that as a result of this decommissioning ef fort , the laboratory area, except for the interior surf aces of TRU glove boxes and hoods, will not have residual levels greater than Zone II levels on any accessible surfaces. .
l 6.3.2 Portable Equipment and Supplies
. r Portable equipment will be cleaned and placed in storage outside of the laboratory area for future sale or disposal. If the equipment cannot be readily cleaned, it will be discarded as waste. Compa tib le laboratory ,
chemicals will be discarded to the Separations Plant Waste Treatment j
Systems. Other chemicals will be packaged for disposal at an approved
. chemical disposal site.
- All cabinets and drawers will be emptied and the contents removed fros l the laboratory for sale or subsequent disposal. The interior surfaces
! of cabinets and drawers will be cleaned to Zone 11 limits. All portable l equipment will be removed from hoods and glove boxes. !
6.3.3 Hoods and Glove Boxes ,
All accessible exterior surfaces of the hoods will be cleaned to Zone 11 timits. The interior surfaces of hoods will be cleaned to a level that is considered to be as low as practicable.
All drain lines from hoods , non-TRU glove boxes , and sinks will be !
flushed with nitric acid and water. The flush solutions will be treated in the Separations Facility Waste Systens. Flush solutLons fron TRU glove boxes will be collected and treated as TRU waste.
Af ter cleaning, the glove boxes and hoods, which had contained TRU
. material, will be isolated from' the ventilation system and other l utilities. The gloves will be lef t in place in the glove boxes and a l gasketed cover plate will' be placed over the glove port. Since there
1 l
will be residual plutonium remaining in some of the glove boxes, a periodic surveillance program, as described in Section 10, will be performed to assure that the integrity of the boxes is maintained.
There are three large non-standard glove boxes in the alpha laboratory which have been exposed to plutonium. As much equipment as practicable will be removed from these boxes via existing bag-out ports. These boxes will be cleaned to a level that is considered to be as low as practicable, sealed and isolated as described above. As with the analytical laboratories, periodic surveillance will be performed.
6.3.4 Waste System Af ter clean-up of the laboratories is completed, all drain lines and tanks in the laboratory waste system will be flushed with nitric acid and water. It is expected that the interior surfaces of the pipes and vessels in this system will contain less than 1,000 dpm/100 cm 2 natural l uranium alpha. No plutonium-bearing solution has ever contacted the laboratory waste system.
All waste disposal operations required as a result of laboratory decom-missioning will be performed in accordance with existing AGNS procedures and applicable state and Federal regulations.
6.4 Other 6.4.1 Waste Tanks l
l There are two High-Level and one Intermediate-Level stainless steel l vaste tanks. Each tank has a nominal capacity of 300,000 gallons and is located inside a concrete vault which is lined with stainless steel.
One High-Level tank and the Intermediate-Level Was te Tank were used to collect wastes generated during the DOE ~ sponsored demonstration runs of the Separations Facility. These solutions have been removed and solidified. However, a waxy film containing a small amount of uranium adhered to some of the cooling coils in the High-Level Waste Tank. The '
l Intermediate-Level Waste Tank has been cleaned, and it will be surveyed by HP. The second High-Level tank has not been used.
l The Intermediate-Level Waste Tank will be used to collect the nitric acid flush solutions used in cleaning the Separations Facility. The used High-Level Waste Tank will collect the water flushes which follow the acid flush.
l The water flush solution will provide sufficient volume to submerge the coils and sodium hydroxide solution will be added to dissolve the waxy flim on them. This solution will then be used to neutralize the acid in the intermediate-level tank and the combined solutions will be concen-trated and prepared for disposal at an authorized burial site.
17
i The two tanks will then be flushed and final surveys will be taken. The !
unused High-Level Waste Tank will also be inspected and surveyed. All utilities will then be shut of f, and the vaults will be closed.
6.4.2 Support Buildings There are a number of support buildings such as' warehouses , machine ,
vehicle maintenance, and ins trument-electrical shops at the BNFP. All of these support facilities are clean. Portable equipment, flammable j liquids, and to the extent prac t ic ab le , combustible material will be removed for disposal or possible sale. Power will be shut down, and the buildings will be locked.
It is possible that the administration buildings will be used for records storage and will be occupied by records pe rs onnel for the inunediate future. In addition, portable equipment will probably be stored in the warehouse, i
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a 7.0 DISPOSITION OF SURPi.US EOUIPMENT A system has been established for controlling the distribution of sur-plus materials. All items of equipment or lots of similar items will be assigned a unique identification number. All pe rtinent data will be keyed to this number and maintained in a computerized data management system. The data collected will include, among other things, a descrip-i tion of the item, its value, location, to whom it was donated or sold, j and Health Physics survey anql release data.
7.1 Disposition of Equipmen't i Portable. equipment (i.e. , readily disconnected by unplugging or unbolt-
! ing) is located in the Separations, Laboratory, and UF6 facilities as
! well as administrative and support areas. This equipment include s such
, things as of fice furniture, laboratory ins truments, welding machines ,
l medical and safety equipment, and small tools. This eq uipme nt will be cle aned , tagged, surveyed by Health Physics, and moved to a designated
- holding area. Movement of this equipment will facilitate subsequent
, eleanup of the - building.
- Some of this equipment, such as saf e ty and medical equipment , may be donated to area hospitals, schools, fire departments, and rescue squads; limited quantities of office furniture and other selected items will be
{ sold to employees. Other selected equipment also will be sold. All i
equipment that is released from the site will be cleared by the Safety and Environmental Control Department (SEC) in compliance with existing ACNS procedures.
7.2 Radiological Controls The SEC Department will determine whether an item can be released fr om the site on an " unconditional use" basis or whether it must be treated
, as a " restricted use" item. " Restricted use" items will be released only to organizations or persons authorized to receive radioactive materials, such as other licensees or the Department of Energy.
Table 7-1 describes the criteria to be used to determine the Health
- Physics Release Code classification for the release of material from the j BNFP.
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TABLE 7-1 HP RELEASE CODE CLASSIFICATION ,
Type of Resid- HP Release Limits (b) ual Material Code Classification Definition Alpha (c) Beta / Gamma unconditional 2 2 Smearable (a) A use of items 1100dpm/100cm 1100dpm/100cm res tricted B use of items >100dpm/100cm 2 >100dpm/100cm 2 unconditional 2
Fixed i use of items 1100dpm/100cm 10.1mR/hr I
res tricted 2 use of items >100dpm/100cm 2 >0.1 mR/hr (a) No covering or coating materials shall be applied to items for the purpose of reducing removable residual levels.
(b) Except as noted (see Note No. c), the limits shown shall pertain only to natural uranium. ,
(c) For items removed from plutonium handling areas in the HCLA, the unconditional use' limit for smearable alpha shall be 110dpm/100cm2, A code letter and number designating fixed and smearable classifications shall be assigned to each item.
The restrictions associated with Health Physics Release Codes shall be applied independently and the most res trictive limits shall de termine the subject item's disposition. For example, items classified with a '.' Health Physics Release Code of
' Al'" are defined as unconditional use items. Items cla s s ified as "A2," "B 1," or "B2" are defined as being res tricte'd use items. Only authorized parties, e.g.,
radioactive material licensees, shall be eligible to take pos ses sion of res tricted.
use items.
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O 8.0 WASTE DISPOSAL A number of types of waste will result from the shutdown and decommis- ,
sioning of the BNFP. All vaste disposal operations will be in com- l pliance with applicable S tate and Federal regulations .
8.1 Radioactive Non-Transuranic The waste which will be generated in this category will include such
. things as non-salvageable uranium-bearing equipment, including some pipes and vessels from the UF6 Facility; " job control" was te resulting from decommissioning activities; non-salvageable laboratory glassware which may have been in contact with uranium; and solidified aqueous waste resulting from process equipment clean-up. The principal radio-active material in these wastes is natural uranium. The waste will be packaged for disposal in accordance with existing regulations. It will then be transported to a licensed commercial site for disposal.
8.2 Radioactive-Transuranic During the performance of research and de ve lopme nt programs for the Department of Energy, it was necessary to use limited quantities of plutonium. Because the plutonium was used in support of Department of Energy programs, it has been determined that all transuranic was tes resulting from decommissioning activities can be accepted by the Department of Energy's Savannah River Operations Of fice for interim storage. In addition, plutonium and other transuranic waste laboratory standards, sources, and stock material will be trans fe rred to the Department of Energy.
8.3 Non-Radioactive Non-radioactive wastes will include such items as pape r , wood , sc rap met al, plas tics , and general trash resulting from c le anu p . AGNS is currently licensed by the state to operate an inert industrial waste landfill on the BNFP site. Materials such as those described will be placed in that land fill. The landfiil will be stabilized and shut down in accordance with state regulations. Af ter the landfill is shut down, AGNS will obtain the services of a commercial waste contractor to accommodate the small volume of waste that will remain.
AGNS has on hand a number of chemicals used in support of laboratory operations and as stock for process solutions. There nonradioactive chemicals will be donated, sold, or disposed of as chemical was te at a licensed disposal site. Any other chemicals or hazardous nonradioactive materials will also be disposed of only at an authorized disposal site.
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9.0 ENVIRONMENTAL IMPACT OF DECOMMISSIONING .
The shutdown and decommissioning of the BNFP will not have a significant environmental impact beyond the socio-economic impact on employees and the community associated with loss of employment.
All flammable liquids, chemicals, radioactive, and other hazardous materials will be removed from the site for sale or for disposal at an authorized facility. Any environmental impact associated with such disposal will have been evaluated and considered during lic ens ing activities for the disposal facilities, j The radiation exposure of personnel during decommissioning will .be l negligible since the principal radioactive material which mus t be l removed from the site, natural uranium, will be handled in pipes, tanks,-
l and similar essentially closed systems. Where it is necessary to work with plutonium, protective measures will be taken in accordance with existing AGNS procedures which have been proven ef fective. No exposures to the general public will result from decommissioning.
The outfall from Beacon pond will be closed of f and liquid discharge i
into the pond and thence Lower Three Runs Creek (LTRC) will be termi- ,
nated. Since the pond's discharge cons,titutes only a small fraction of the total flow of LTRC, cessation of discharge will have minimal, if .
any, impace.
An Environmental Consultant retained by AGNS has recently inspected the site to determine if eros ion would be a problem should the site be ,
abandoned. His conclusion was that the surf ace features of the site have stabilized and that ecosion will not be a problem.
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L 10.0 FINAL STATUS AND CONTIFUED SURVEII.I.ANCE Upon completion of the decommin aianing progr am, the BNF P s i t e and facilities will be in a condition such that only minimal periodic surveillanco will be required.
Except for previously discussed residual stounts, all radioactive raterial will have been removed from the sita. All normal ac ces s areas will have been cleaned to Zocs 11 timite and entrance may be made wearing street clothing only. Same neural uranium will be present on the internal surf aces of pro: usa pipes and ve s sels. However, it is anticipated that lovels of residunt material will be le s s chan the limits set forth in Regulatory Guide 1.86 for " Unrestricted" use. While glove boxes thich previously contained plutonium will still have resid-ual quantities of plutonium on their interior surteces, the external surfat as will be less than Zone II limits. Hoois, laboratory work benchen, ficore, ceilings, and walls .in the laboratory area will also be less than Zone II limits.
The doors to latoratorias and en*xis vill be securely locked. Ven-tilation dampers to cells and laboratories will be closed. Glove boxes which have contained plutoniu a' vill be isolated from the ventilation sys tem. All combustibles , flammable liquids, po rtable equipment, and furniture will be reaived from the laboratories and process buildings.
l Electrical power and ccher utilities will be shut down. All entrance l
points to the pro.ess b didirgs will be sicurely locked.
Support buildings r.vch as utility areas, trainin;; center and warehouses will be emptied of their contents. Entrances will then be locked.
i However, it is possible that nue equipment may be s to r ed in existing wareheuses on alta.
, Two of three lerns waste tanks at .the CNFP have been contained with natural uranium. These t anks will be cleannd to a level that is considered to be as low as practicable. It is expected that the residual level in these tanks will be less than the levels specified in Regulatory Guide 1.86, for "Unrestriceed" use.
Although the amount of radioactive : mater.a1 remaining on site will be extremely small a*! will be presont only an low-level surface reeidues, a periodic survalliance program will be lapleme nted . Security inspec-tion of the process areas will be perf armed quarterly. The security inspector will look for obvi.ous dar2 age to buildings or evidence of attempts to enter the faellity. . Site boundary fen:es will be inspected for evidence of entry and the site will 1e obs :rved for erosion damage.
l While thu meteorological tower remains in p: tee, t.be FAA varning Ild hts l will be checked daily for oportition.
1 Semi-annual radiological surveys and safety and fira protection ins pec-tlone will be performed. Thin will consise of walk-chtough inspeeeions
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of the facility to detect fire or safety problems. Smear surveys will I be conducted in the Separations Facility, the laboratory areas , and the UF6 Facility. In the laboratory areas, smears will be taken around' -
glove ports to assure that any residual material remains confined. ,
Glove ports will be visually inspected to insure that the integrity of (
3 the box is maintained. l j l i
As a part of preparing for operation of the BNFP, an extensive radio- I logical environmental survey was performed by a consulting team now [
, headed by Dr. John M. Palms of smory University in Atlanta, Georgia. '
l Although AGN8' contractual relationship 'with these consultants has been
- terminated, a new contract will be written to provide for a final
! environmental survey of' the BNFP. However, because only minimal levels !
j of radioactive materials will remain at the BNFP, it is not considered !
necessary to perform periodic environment:1 surveys such as soll, sir, j and water sampling. F
- AGNS will contract with a qualified organisation to perform the sur-l veillance functions. An individual within one of the parent companies i will be assigned responsibilities for assuring that the surveillance !
program is properly conducted. !
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%- l 11.0 ' DOCUMENTATION s
All activities associated with the decommissioning of the BNFP will be performed under exis ting', AGNS procedures. These procedures will be supplemented with written work ins truct ions as necessary. Copies of procedures , work ins tructions , radiologic al survey ' data, and property disposition records will be retained as supporting documentation.
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