ML20024D490
| ML20024D490 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 07/31/1983 |
| From: | Link B, Miller R UNITED NUCLEAR CORP. (SUBS. OF UNC, INC.) |
| To: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| CON-FIN-B-7568 NUREG-CR-3336, NUDOCS 8308050105 | |
| Download: ML20024D490 (48) | |
Text
.
NUREGICR-3336 Evaluation of Nuclear Facility l Decommissioning Projects Summary Report Ames Laboratory Research Reactor i
Prepared by B. W. Link, R. L Miller UNC Nuclear Industries Prcpared for U.S. Nuclear Regulatory Ccmmission 5
hDR DOC 000 6 W PDR
. NOTICE This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability of re-sponsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that !ts use by such third party would not infringe privately owned rights.
Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:
- 1. The NRC Public Document Room,1717 H Street, N.W,.
- Washington, DC 20555.
- 2. The N RC/GPO Sales Program, U.S. Nuclear Regulatory Commission, Washington, DC 20555
- 3. The Natioria! Technical Information Service, Springfield, VA 22161 Althc, ugh the listing that follows represents the majority of documents cited in NRC publications, it is not intended to be exhaustive.
Referenced documents available for inspection and copying for a fee from the NRC Public Docu-ment Room include NRC correspondence and ir.ternal NRC memoranda: NRC Office of inspection and Enforcement bulletins, circulars, information notices, inspection and investigation notices;.
Licensee Event Reports; vendor reports and correspondence; Commission papers; and applicant and licensee documents and correspondence.
The following documents in the NUREG series are available for purchase from the NRC/GPO Sales Program: formal NRC staff and contractor reports, NRC-sponsored conference proceedings, and N RC booklets and brochures. Also available are Regulatory Guides, NRC regulations in the Code of
- i. Federal Regulations, and Nuclear Regulatory Commission issuances.
Documents available from the National Technical Information Service include NUREG series reports and technical reports prepared by other federal agencies and reports prepart.d by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.
Documents available from public and special technical libraries include all open literature items, such as books, journal and periodical articles, and transactions. Federal Register notices, federal and state legislation, and congressional reports can usually be cbtained from these libraries.
Documents such as theses, dissertations, foreign reports and translations, ar.d non-NRC conference prcceedings are available for purchase trom the organization sponsoring the publication cited.
Single copies of NRC draft reports are available free upon written request to the Division of Tech-nical Information and Document Control, U.S. Nuclear Regulatory Commission, Washington, DC 20555.
Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Marylard, and are available there for reference use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards Institute.1430 Broadway, New York, NY 10018.
GPO Printed copy price:
l
NUREGICR-3336 ,
1D l
l Evaluation of Nuclear Facility ;
Decommissioning Projects !
)
i Summary Report Ames Laboratory Research Reactor Minuscript Completed: May 1983 Date Puuished: July 1983 Prepared by B. W. Link, R. L Miller UNC Nuclear Industries m iss n g P ograms Department Prapared for Division of Engineering Technology Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission
'N:shington, D.C. 20556 NRC FIN B7568
EVALUATION OF NUCLEAR FACILITY DECOMMISSIONING PROECTS
~
SUMMARY
REPORT.
AMES LABORATORY RESEARCH REACTOR Reviewed By DOE-RL:
D.~
DWhite, Director, Surplus Facilities -
2dn Date-
- f. Management Program Office Approved By UNC:
( esk/we<<- b ( b T. E..Dabrowski, Director, Decommissioning '
Date Programs Department Approved By NRC:
,- ------/f8 ._ t //t/93
' D. W. Reisc~nweaver, NRC Program Manager ' /Date
)
ABSTRACT This document summarizes the available information concerning the-decommissioning of the Ames Laboratory Research Reactor (ALRR), a five-megawatt heavy water moderated and cooled research reactor. The data were placed in a computerized information retrieval / manipulation j system which permits its future utilization for purposes of comparative analysis. This information is presented both in detail in its computer output form and also as a manually assembled summarization which highlights the more important aspects of _the decommissioning program. Some comparative information with reference to generic decommissioning data extracted from NUREG/CR 1756,
" Technology, Safety and Costs of Decommissioning Nuclear Research and Test Reactors," is included. l l
i 1
iii
CONTENTS '
Page
1.0 INTRODUCTION
1 1.1 Acronyms & Definitions 2 2.0 FACILITY SUMPMRY REPORT 4 2.1 Facility Description 4 2.2 Summary of Costs and Radioactive kaste 4 2.3 Comparisons of Cost Items 5 2.3.1 Dollar Costs 5 2.3.2 Man-Rem Costs 5
3.0 DESCRIPTION
OF COMPUTER REPORTS 6 3.1 General Information 6 3.2 Decommissioning Code Table /Index 6 3.3 Significant Event Report 7 3.4 Radionuclide Inventory ~ 7 3.5 Project Cost / Exposure Report 7 3.6 Dose Rate and Contamination Report 7 3.7 Project Labor Report 7 3.8 ALARA Report 7 3.9 Shipment Report 8 3.10 Disposal Costr 8 3.11 Surveillance Report 8 3.12 Public Dose Rate 8 4.0 COST ADJUSTMENTS 9 5.0 FINAL SITE CONDITION 11 5.1 Criteria 11 5.2 Final Site Condition 12 v
~ . - . - . . . . . - - - . .. -. -
a CONTENTS - continued i
'Page 1-5.2.1 Site, Other Structures and Reactor' Building 12 Other than Reactor Room 5.2.2 Reactor Room and Basement 13' 15
6.0 CONCLUSION
S AND LESSONS LEARNED
.16 7.0 COMPUTER REPORTS 17
)~ General Information' Decommissioning. Code Table Inder 22 24 Significant Event Radionuclide Inventory 25 <
26 Project Cost / Exposure i
28 Dose Rate and Contamination 30 Project Labor 32 ALARA
- 33 Shipment 37 Disposal Costs 39 Surveillance 40 i Public Dose Rate vi d
' 7 . .
, +
A
,, 1.0 INfROCUCTION This document-summarizes the available information concerning the decommissioning of the Anes Laboratory Research Reactor (ALRR) in the DE00N mode, as defined in Section 1.1. Although the removal 'and disposal of the reactor and all reactor-associated equipment and material was completed, the existance of very low levels of residual radioactivity precludp.<i the facility's release for " unrestricted use". LFurther infonnation on final . site conditions is presented in Section 5.0.-
z
~
3_ .
The decision to shut dodn' and decommission the ALRR, made jointly by the Department of Energy and the Ames Laboratory, was brought about by continuing reductions inl funding for basic nuclear research. Because the space utilized by the reactor and its associated equipment was considered desira51e for future Laboratory activities, tae DECON decormiii,sioning mode was chosen in ortler to clear the space in question' for " unrestricted use".
The prompt institution of the' decommissioning program was determined to be necessary for several reasons; among them, a knowledgeable staff of reactor employees was available and could be maintained, and the inflationary escalation of-costs could conceivably be minimized.
The services of a nuclear consultant firm were utilized for preparation of the necessary documentation, and in the pre-decommissioning cost estimates. The original sum budgeted for the decommissioning program was 4.5 million dollars. The decommissioning schedul6 called for completion of the physical work in 3 years and of post-decommissioning documentation in an additional six months. The actual work was completed nine months later than the original schedule and the large majority of required documentation completed at approximately the same time.
The decommissioning data were assembled in a form that permitted its input into a computerized data-handling system. The computer program used results in a flexible data accumulation, manipulation and retrieval system which can provide such benefits as:
e Greater- accuracy of cost, labor and radiation exposure estimates e Increased perception concerning ALARA responsiveness e Guidance in time schedule projections e Predictability of radiation and contamination levels
.z .- . . . . . -
- s
~
~
P' o Identification of. special areas of' difficulty in the decommissioning process LAs' thd accumulation of. data from actual decommissioning projects mounts, -the value of.the program as a decommissioning; aid is:
enhanced. Some comparative information with reference to reference 4
researth and test reactors is. included'in Section 2.0.
1.1 Acronyns - Abbreviations - Definitions Definitions of Decommissioning Alternatives i
DECON -to immediately remove all radioactive material to permit unrestricted release of the property. .
SAFSTOR - to fix;and maintain property so _that risk to safety is acceptable for period of storage followed by decontamination and/or
+
decay to Jan unrestricted level.
- ENTOMB - to encase and maintain property in a strong and structurally
,, '. long-lived: material __ (e.g., concrete) to assure retention until e, radioactivity' decays to an unrestricted level.
. ' Acronyms - Abbreviations l A/C Activated or Contaminated AEC - Atomic Energy Commission
! ALARA As' Low As Reasonably Achievable 71 Alum Aluminum Metal
!- ANL Argonne . National Laboratory
- BARN Barnwell, S. Carolina (waste disposal site) n BIO Biological
? Ci ~
- Curie
~ '
CS Carbon Steel Cu Ft Cubic Feet DDS ' Decommissioning Data System DNA Data Not Available .
p;' . 00E Department of Energy -
DOS RED FCT Dose Reduction Factor DPM Disintegrations per ' Minute H VAC Heating, Ventilation, Air Conditioning HX Heat Exchanger
- -c 'LSA Low Specific Activity MAPPER ~
Maintain, Prepare, and Produce Executive Reports
. MW ' ~ Fbgawatt
- mwd Megawatt Days i
.s-ta' I_
. ~. _. __.a_._ - - . . , . _ _ . - - _ . . _ _ _ . - . _ . _ - , . _ . . . _ , - - _ _ _ _ _
+
MWdt- . Megawatt Days Thennal MWt - Megawatt Thermal N/A - Not Applicable . .
NRC U.S. Nuclear Regulatory Comission OSU Oregon State University RICH Richland U.S.' Ecology Disposal Site RHO Hanford DOE Disposal Site (Operated by Rockwell Hanford)- .
- Specification Number
' ~
SPEC NO-SS ' Stainless Steel
- SYS/ COW System Component' TRIP LEN Trip Length
. TYP Type .
UNC - UNC Nuclear. Industries,' Operations Division i
d*
i ih
,.- .i p
!' 1 t-
, , . , - - - - . . . . . - _ . . - ..- - - _ , - - - . . . . . , . - , . , . _ . . . , _ , _ . _ . . ~ , --..--,._,__,,.._.._,,,.,.,--.,J.- , r-.-,
i 2.0 FACILITY
SUMMARY
REPORT This section contains a manually summarized duplication of the computer-output information presented in Section 7.0, and comparative infomation with reference to generic decommissioning data extracted from NUREG/CR 1756, " Technology, Safety and Costs of Decommissioning Nuclear Research and Test Reactors."
The purpose for this section is two-fold: (1) to provide the reader with a condensed overview of the decommissioning of a SMWt D20 research reactor, similar to several U.S reactors which.will, of course, eventually be decomissioned, and (2) to present a brief comparison of major facets of the above decommissioning project with those of the generic decommissioning of a reference 1 MWt research reactor (RRR) and of a reference 60 MWt Test Reactor (RTR).
Cost infomation for RRR and RTR is assumed to be in 1981 dollars, while comparative ALRR infonnation is assumed to be in approximate 1980 dollars. As ALRR cost items became due, they were paid on approximately the completion dates of the specific cost items being ch arged.
2.1 Facility Description Name: ALRR RRR RTR Anes Laboratory Research Reference Research Reference Test Reactor Reactor Reactor Location: Anes, IA Corvallis, OR Sandusky, OH Owner: Department of Energy Oregon St. University NASA Operator: Anes Laboratory OSU NASA Reactor Type: Research (D2 0) TRIGA (Pool-Type) Test, (Hp0)
Operating Lifetime: 12 yrs 40 yr. (5% operating) 40 yr.
Decommissionina Mode: DECON DECON DECDN Power Rating: 5 MWt _ 1 MWt (Steady State) '60 MWt Lifetime Power: 15200 MWdt 740 MWdt 98000 MWdt Reason for Decommissioning: Reduced funding End-of-Life End-of-Life j 2.2 Summary of Costs and Radioactive Waste ALRR RRR RTR Total Decommissioning Cost, Dollars: 4,335,000 850,000 15,600,000 Personnel Exposure, Manrem: 69.4 18.3 322 ALRR RRR RTR Radwaste Volume, Co. Ft.: 40,830 5650 174,200 Radionuclide Inventory, Radwaste,. Curies: 6832 1500 369,000 2.3 Comparisons of Cost Items 2.3.1 Dollar Costs The following listed items are compared to total dollar costs for the decomissioning project.
ALRR RRR RTR No. 07-'7i0. of $ No. of No. of $ No. of No. of $
Item (thit) Units Per Unit Units Per Unit Units Per Unit Radionuclide Inventory (C1.) 6832 634.43 1500 56.67 369000 42.28 Radwaste (Cu. Ft.) 40830 106.18 5650 15.04 174200 89.55 Lifetime Pwr.
Output (MWdt) 15200 285.16 740 114.86 98000 159.18 Spending Rate (Mon) 45 96320 8.5 10000 25 624000 2.3.2 Man-Rem Costs The following listed items are compared to the total personnel exposure to radiation during the decommissioning program.
ALRR RRR RTR No. of No. of No. of No. of Units Per No. of Units Per No. of Units per Item (Unit) thits Man rem Units Manrem Units Manrem I
- Radionuclide Inventory (C1. ) 98.44 81.97 1145.96 6832 1500 369000 Radwaste Volume (Cu. Ft.) 40830 588.33 5650 308.74 174200 540.99 Decommissioning Costs (5) 4335000 62460 850000 46450 15600000 48450
3.0 DESCRIPTION
OF COMPUTER REPORTS The reports described below are the basic reports used in the DDS pro gram. The Gescriptions, as presented, are intentionally idealized. *t should be understood that all functional facets of the reports will not always be utilized, simply because the documentation of decommissionire information will vary from project to project. In addition to the basic reports, MAPPER provides the ability to produce supplementary reports by manipulating the data available in the basic report s.
3.1 General Information This report is a free format input report designed to accommodate descriptive data of any kind. Entries may be given any title and related to any f acility system by a system component number. Data are entered in any fonnat on any subject. The report should be used to record information that does not fit into any of the report types organized by column. This includes facility location, description, owners, operators, builders. Summary data may also be included where it is not readily derivable from other reports or for convenient reference.
3.2 Decommissioning Code Table /Index This report contains a list of unit items, including facility.
buildings, systems and system components, and budgetary items, with a corresponding identification number for each unit. The identification system is used throughout DDS to relate data to specifically identified units.
This basic report type may be expanded to include tables or indices of other kinds related to facility decommissioning. Candidate tables are labor category wage rates, shipping company rates, shipping company name codes, disposal site name codes and rates, or archived file tape names.
One of the basic values of this report is the fact that, by utilizing an index which can ultimately be made common to all reactor facilities included in the program, the report can become the intercomparison base for the DDS. The full utilization of this base will not be possible until a certain minimum number of facilities as yet unspecified, are included in the DDS.
3.3 Significant Event Report This report is used to record the facility's operating history, which
, in some cases could impact facility decommissioning. It contains dates, system / component numbers, and event descriptions. Noteworthy events such as construction completion, startup, shutdowns, significant incidents, and accidents are recorded in this report.
3.4 Radionuclide Inventory An inventory of radionuclides present in each f acility system will be made prior to the start of decommissioning. The amount of each radionuclide or its concentration, the measurement date, and a description of each system's material composition will be recorded.
It will be noted whether a radionuclide present in a system is the result of neutron activation or contamination.
3.5 Project Cost / Exposure Report Costs, schedules, man-hours, man-rem, both estimated and actual, are Ifsted for each activity specification number. These costs may be broken out on lines having a subactivity specification number. This report is the main respository of cost and exposure infomation for a decommissioning project.
3.6 Dose Rate and Contamination Report Oose -ates at locations throughout each facility are recorded prior to decommissioning. Locations relative to a reference map, elevation, system / component number, and type of measurement are recorded for each meas urement. Both upper and lower limits of dose rates or contamination levels (in disintegrations per minute) are listed.
3.7 Project Labor Report Decommissioning labor costs, exposure, and man-weeks for each activity specification are recorded at a to-be-detemined frequency. This
) supplements the project cost / exposure report by providing data on how
- f. . costs and exposures accumulate over the course of a decommissioning project.
3.8 ALARA Report The ALARA report contains records of ALARA efforts by activity specification number. The affected facility system, date, cost items, exposure information, and a description of the ALARA effort are listed. This report can be used to calculate by activity l
specification number or for all activities the total estimated man-rem saved as well as total ccst incurred through the implementation of the AL ARA effort.
3.9 Shipment Report Volunes, weights, and other physical data are recorded by waste type for material produced by each activity specification. These data are listed for each shipnent of material from the decommissioning site.
Trip lengths and vehicle dose rates are recorded in order to calculate public exposure.
3.10 Disposal Costs The costs associated with each waste disposal shipment are recorded in the Disposal Costs Report. Costs are divided into transportation, burial, and container categories. Costs for each container type on the shipment are also listed.
3.11 Surveillance Report The surveillance report is used to record annual costs and exposures associated with long term surveillance of a decommissioned facility.
Under normal conditions a surveillance report would not be required for a facility decommissioned under Mode DE00N.
3.12 Public Dose Report -
The exposure of the public to radiation which results from the decommissioning of nuclear facilities is one' criterion which is to be considered during the pre-decommissioning evaluation phase. This report presents an estimate of such exposure information, based on extrapolations of measurement data and numerous assumptions, including both routine and accident conditions.
l
'T
-~ +r- - ,,.. - ,- - ,
4.0 COST ADJUSTMENTS All cost infonnation included in this document is presented in actual dollars as the charges were paid through the decommissioning program.
For adjusting costs listed in the computer reports to year of interest, use the inflation rate table below.
florealized Cost Escalation Table Annual inflation Rate
- Year 1970 1971 1972 1973 1974 9 1975 1976 1977 1978 1979 1980 1981 1982 0.029 1966 0.029 1967 0.042 1968 0.054 1969 0.059 1970 1.000 0.043 1971 1.043 1.000 0.033 1972 1.076 1.033 1.000 0.062 1973 1.138 1.095 1.062 1.000 0.110 1974 1.248 1.295 1.172 1.110 1.000 0.091 1975 1.339 1.296 1.263 1.201 1.091 1.000 0.058 1976 1.397 1.354 1.321 1.259 1.149 1.058 1.000.
0.065 1977 1.462 1.419 1.386 1.324 1.214 1.123 1.065 1.000 0.077 1978 1.539 1.496 1.463 1.401 1.291 1.200 1.142 1.077 1.000 0.113 1979 1.652 1.609 1.576- 1.514 1.404 1.313 1.255 1.190 1.113 1.000 0.135 1980 1.787 1.744 1.711 1.649 1.539 1.448 1.390 1.325 1.248 1.135 1.000 0.089 1981 1.876 1.833 1.800 1.738 1.628 1.537 1.479 1.414 1.337 1.224 1.089 1.000 0.060** 1982 1.936 1.893 1.860 1.798 1.688 1.597 1.539 1.474 1.397 1.284 1.149 1.060 1.000 l
Exampl e: A cost paid in 1971 dollars would increase to a cost of 1.893
! times the original, if paid in 1982 dollars.
- Sourt e: Statistical abstract of the United States,1981 Consumer Price Index.
- 1982 data are interim estimated.
l l
In planning for large decommissioning projects which cover long time spans or are scheduled to start at some time in the future, cost estimates should consider the " worth" of current money and then adjust cost estimates to reflect this consideration. This exercise, referred to as a " time value cost analysis", considers the year of. expenditure, interim surveillance and maintenance costs, major non-routine maintenance costs, and inflation rates. " Worth" of current money is usually based upon an average yield on stable, non-speculative investments such as long and short-tenn treasury bills. A " time value cost analysis" results in a percentage value, referred to as the discount rate, which is used to discount the cost of a future project to the current " worth" of money. This discount rate includes consideration of financial uncertainties, such as p overruns, recovery costs for major accidents, etc. {oject cost Example - A discount rate of two percent yields the following table:
Discount Discount Ye ar Factor Year Factor 1 0.9804 6 0.8880 2 0.9612 7 0.8706 3 0.9423 8 0.8 513 4 0.9238 9 0.8535 5 0.9057 10 0.8204 If project is estimated to cost $10,000 during a time period six years from today, the amount of money presently' required to be invested is
($10,000) (0.8880) or $8,800.
Detailed discussions and suggested assumptions may be found in the following references:
- 1. Methodology for Establishing Decommissioning Priorities U.S. Department of Energy, Richland Operations Office, RLO/SFM-82-7, June,1982.
- 2. The Rate of Discount for Evaluating Public Projects Mikesell, R. F.,1977 American Enterprise Institute for Public Policy Research, Washington, D.C.
Navigating through the Interest Rate Morass: Some Basic 6
3.
Principles Santoni, G. J., and C. C. Stone 1981 Federal Reserve Bank of St. Louis Review, March,1981
i 5.0 FINAL SITE CONDITION 5.1 Criteria l The original goal for decomissioning the ALRR as stated in the Environmental Impact Assessment was to place the building and site in condition for unrestricted use by removing the reactor-related radioactivity. The radiochemistry laboratories in a laboratory wing, the laboratory part of a Warehouse / Laboratory Building, and the Waste l Disposal Building were excluded from the goal of unrestricted use since it was considered that they would be in continued use involving radioactive materials. However, removal of reactor-related radioactivity from these areas was included in the decommissioning pl a n.
The exact values of residual levels of radioactivity acceptable for unrestricted use were not well-defined and appeared to ur.dergo change during the course of decomissioning. Guidelines used were those of 00E Order 5480.1, Chapter XI, Table II (also in 10-CFR-20, Appendix B), and the unrestricted use levels of NRC Regulatory Guide 1.86. The fonner are maximum values averaged over a year for the concentrations of radioactive isotopes in water and air releasable to the general public. The relationship between allowable residual radioactivity in I soil and concrete and these values is not at all clear. The criteria l originally suggested were that concentrations of radioactivity in l water, soil and concrete of 10% of the Table II value for water could i be allowed to remain. This was to be defined on a weight basis, i.e.,
concentrations in uCi/g of the material in place of uCi/ml of water used in Table II.
. In informal discussion with CH, it was indicated that levels in the range'of 1-3% of the Table II value should be the goal rather than 10%
in guiding the removal of soil in areas which contained low levels of contamination.
The discovery of widespread low-level diffusion of tritiated water into the concrete of the reactor room floors and walls made it obvious that the criterion of 1-3% of the Table II value could not be met for tritium in this part 'of the building. An ANL-based Radiological Survey Group
- stated in their report, " Interim Overview / Certification Activities Report for the Ames Laboratory Research Reactor Facility, Ames, Iowa" of February 11, 1981 that, "It is also quite evident, from l
" Authorized to perform in behalf of the Department of Energy in matters concerning radiological safety.
l t
the airborne tritium levels encountered, that the release of this structure for unrestricted use is not possible at this time or in the near future." This conclusion was endorsed by CH and agreed to by the Ames Laboratory and has been used as the basis for decontamination of the reactor room. However, this decision does not imply that the room cannot be used. Another conclusion by the Survey Groep was that it appears possible "to essentially allow uncontrolled access" to the room as long as Health Physics surveillance of airborne tritium is maintained.
Exemptions from strict adherence to the unrestricted criteria for removal of radioisotopes other than tritium were granted for several pipe lines buried in concrete. These aspects of the problem are discussed in the next section.
5.2 Final Site Condition The reactor and its associated systems, components and wastes were removed, and major decontamination was completed. Only the tasks of final detailed survey remain to be completed, and will be dccumented in the form of interim and final addenda to the final decommissioning report referenced in the General Information Report of Section 7.0. ,
5.2.1 Site, Other Structures and Reactor Building Outside the Reactor Room In August and September 1981, soil samples were taken at two depths from 65 sites around the reactor building using a grid based on quadrant / radial segment areas centered on the reactor, including area inside and outside of the reactor exclusion fence. Samples were also taken from five control sites. To this date all control site samples and seven of the reactor site samples have been analyzed by gamma spec troscopy. All samples contain 137C s, but with no significant difference between reactor site and control samples. Additional samples have been prepared for gamma analysis and sufficient samples will be analyzed to provide adequate documentation.
Traces of radioactivity dating to pre-reactor days remain in a controlled waste holding area on the site which has been used by the Laboratory since 1950. Most of the radioactive material stored in this area was removed, and much of it included with deconmissioning waste shipments. Survey results showed small areas of slightly contaminated soil, with uranium and thorium the major components.
The laboratory half of the Warehouse / Laboratory Building was not cleared of radioactivity because work with radioactive materials is expected to continue in these laboratories. However, no radioactivity
produced from or related to the ALRR remains. At present some neutron diffraction equipment.which was slightly activated at the face of the-reactor is stored in the warehouse half of this building. This equipment.is considered by the experimenter to be too valuable to -
consign to waste and continues to be of potential usefulness in the continuing program in neutron scattering conducted by Ames Laboratory scientists _at the Oak Ridge Reactor. This equipment is catalogued and will be kept on the record as. radioactive as long as it shows radiation levels-above backgrou'nd.
The Radioactive Waste Disposal Building will be maintained for handling, packaging and temporarily storing radioactive waste. Since shipments of. waste in -less than truck load quantities presents problems, storage may last for more than a year..
The Laboratory Wing of the Reactor. Building includes several laboratories in which radioactive material from the ALRR was handled-and used. It was earlier considered that these laboratories would continue to be utilized for radiochemical research, but programs which do not involve radioactivity were installed af ter decommissioning was completed, and the laboratories were decontaminated. The hood exhausts in' the laboratories : included horizontal runs of . square ducts made of an asbestos composition. Since the ducts were slightly radioactive, they were removed, crushed, boxed and included in last waste shipments. The vertical runs of the hood exhausts to the roof, the exhaust fans and the fume hoods were surveyed for removable and fixed contamination and were decontaminated where necessary. One hood was decontaminated, removed and stored for future use within the Laboratory. The laboratories were decontaminated and surveyed; the final conditions exceed the criteria for unrestricted use of NRC Regulatory Guide 1.86, ".Temination of Operating Licenses for Nuclear Reactors" as well as the ALARA principle.
The Staging Area.section of the Reactor Building were cleared and surveyed. :The accessible floors and walls were determined to be free of removable contamination.
7 5.2.2. Reactor Room and Basement As stated above, it is not possible to release the Reactor Room for unrestricted use at this time because of the tritium present as tritiated water of hydration in the concrete. Since this action pemits the use of the room as laboratory space, the removal of other radioisotopes which might further restrict the use of the room remained the objective with the unrestricted use criteria as the basis.
This objective has been achieved in all but a few inaccessible locations in buried drain lines. Exemption from strict application of the removal criteria for radioisotopes other than tritium was made on the basis of inaccessibility and.the very small amounts of radioactivity. The walls'and floor of the reactor room and basement were washed down and surveyed for both removable and fixed contamination. Removable activity met the unrestricted use criteria in all areas. In small areas scattered over the reactor room floor, the residual fixed activity level was above these criteria. A survey by the Radiological Survey Group showed a number cf these areas, and others were found in a thorough survey by the Laboratory Health Physics Group. Since further scrubbing did not remove all of the radioactivity, various abrasive and chipping devices were used to remove a surf ace layer of concrete from 1/8 to 1/2 inch deep in these areas. The only reactor-related radioactivities identified in samples of the surface concrete by gamma spectroscopy were 13 7Cs and 60Co. Removal of a single thin layer of concrete usually reduced the contamination to below unrestricted use criteria. If the activity still exceeded these levels, the process was repeated. The ceiling, walls and floor areas of the main floor of the reactor room were brought to levels below the unrestricted use level of NRC Regulatory Guide 'l.86 for all radioisotopes other than tritium.
On completion of this survey and decontamination effort, and of similar work in the reactor basement, staging area and other possibly contaminated areas, documentation will be presented in addenda to the final decommissioning report.
1
6.0 CONCLUSION
S' AND LESSONS LEARNED
- Decommissioning of the Anes Laboratory Research Reactor was accomplished within the original budget authorization of $4.5M. It is interesting that the cost of construction for the original building, reactor and site work in the 1961-64 period was very close to the cost of decommissioning the reactor and its systems but leaving .the -
building intact in 1978-81. Because of escalation, these costs cannot be compared directly. In 1961 dollars, the cost of decommissioning would be in the range of $1.5 to $2.M.
A delay of approximately seven months occurred in one task as a result of contractor's problems and an unforeseen error in as-built drawi ngs. Change in DOE policy on waste disposal caused a delay of about one month. With these exceptions, the original schedule was followed fairly closely. Completion was six to nine months later than scheduled, but preparation of the final report was not delayed as much.
The decision to proceed with decommissioning immediately after shutdown seems to have been correct. Although this action resulted in funding on an annual rather than a continuing basis, the original staff was intact to begin the work, and it otherwise would have been necessary to bring in more contract workers with much less knowledge of the system to be removed, in all likelihood at a greater cost.
Also, the rate of inflation during the years of decommissioning has beeri usually high. Although this was not predictable, if the work had been postponed, the total cost would have been considerably greater.
The use of annually appropriated rather than line item funds which could be carried into subsequent fiscal years did create problems, particularly because of the delay in completion of one contract and the mandatory postponement of following work. The time available between the decision to shut down the reactor and the scheduled start of decommissioning was not sufficient to obtain funding as a line item.
The matter of the type of subcontracts to be used was discussed in
, planning the decommissioning. As is customary in the DOE, contracts were awarded on a fixed-bid basis, but some consideration was given to the use of cost-plus-fixed-fee contracts. In this project, the cost for subcontract work was unquestionably less with the fixed bid k procedure. In two of the contracts, the low bid may have led to a substantial loss by the contractor. Soliciting bidders on a cost-plus
- The information presented in this section was taken from the final ALRR decommissioning report referenced on page 17 under " References".
basis would have cost more, but could have provided personnel with more experience leading to more prompt completion of the work.
Wether greater prior experience is required and whether completion on schedule is worth the extra costs are debatable questions which depend on other circumstances.
It was suggested by subcontractors that they would rather see the complete work as a single package. It might be advantageous to include all of those tasks for which contractors were hired, e.g.,
core tank and themal shield removal and pedestal demolition, in a single package to enhance continuity. However, time would still be required to prepare the bid specifications and it is doubtful if any savings in time or money would be realized. Several vendors would have welcomed the opportunity to provide managerial and/or engineering services for the complete . task. Such contracts were not considered and it seems doubtful if the work would have proceeded any more smoothly or at a comparable cost under such- an arrangement.
In future decommissioning projects it is suggested that the bid specifications be expanded to include more information on radiation levels and radioactivity content in order to assist the vendors in planning and preparing cost proposals. A major problem in providing this infomation is the potential exposure of personnel in obtaining it. The cost and time for the preparation of specifications would also be increased.
7.0 COMPUTER REPORTS The following section comprises the basic computerized data which was taken from available documentation, stored reactor records and on-site interviews with Anes Laboratory employees associated with the decommissioning program.
WP#1195F l
~
PAGE NO.' i
.ALRR-DffnN UNE EffnMMIRRfnufMR DATA RYRTFM nr kr t al TkFnamaffng,gEgnRT 79P11ga ,___ __m.__..
8 .SYS/ COMP.
.8 SYSTEM / COMPONENT , . NUMBER . ENTRY TITLE-tossemessassesse.sene.semessee.eemesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeen.
DESCRIPTION OPERATING HISTORY maer. at ne traerne m Igg _,, risonmov i o re. __ ___ _ ,_,. .,
. LOCATIONI AMEse IOWA SHUTDOWN DATEI. DECEMBER 1977
. OWNERI DOE MEGAWATT DAYSI 1.52E4
. OPERATORI AMES LABORATORY MAJOR SHUTDOWNSI '3 MONTHS, MAJOR VALVE REPAIRS
. ARCH'ITECT/ ENGINEER l BURNS 1 ROE DECOMMISSIONING MODEI DECON
. BUILDERT MAXON CONSTRUCTION , _ _ _ _ . . . . _ _ _ . . . . _ .,1.
. DESIGNERI AMF ATOMICS
.+++++++++++++++++++4+++++++++++++++++++++++++++++++++4+++++++++++++++++++++++++
REFERENCES REPORTS l
. ALRR FINAL HAZA_RR_SILMMARY REPORT , _ _ _ _ . , . _ _ _ _
. FINAL REPORTe DECOMMISSIONING OF THE AMES LABORATORY RESEARCH REACTORe
. IS-4789e UC 78A
. PAPERSI
. I. PLANS AND PROGRESS IN DECOMMISSIONING A RESEARCH REACTOR, A F VOIGio
. ET_AL._IAEA, YJ ULNAt_19Z' e PP2 237-23a . ._ _
. 2. DECOMMISSIONING OF THE AMES LAB 0kATORY RESEARCH REACTORe. _ _ . . . . . . . . _ _ _B W L INK.
. A F VOIGTe INTERNATIONAL DECOMMISSIONING SYMPOSIUMe SEATTLEe 1982,
, . PAGES IV-19 THROUGH IV-38
-a .+++++++++'+4+++++++++++++++++++t+++++++++++++++++++++++++++++++++4++++++++++++++
%J . DOCUMENTS PREPARED
~ ~ ~ ' "'
. CATEGORY TITLE
. DECOMMISSIONING ALTERNATIVES ' DECOMMISSIONING ALTERNATIVES FOR THE AMES .
. LABORATORY RESEARCH REACTOR *e CH ERDAeJULYe'77
. ADDENDUM TO THE ABOVE, AUG/'77
~
. ENVIRONMENTAL IMPACT ' ENVIRONMENTAL IMPACT AS$'ESSMEET FOR DECOM-
. MISS10NING THE AMES LABORATORY RESEARCH REACTOR
. REACTOR'e REACTOR DIVISION, AMES LABORATORY.
. ORIGINAL SUBMISSION JULY 1977. REVISED
. NOV.'77 p
. PROPOSED SCHEDULES ' DECOMMISSIONING ALTERNATIVES' ALRR STAFF
. JULYe'77 AND NOV.'77
' DECOMMISSIONING STEPS' ALRR STAFFe MAP'78
__ 'DECOMMIS$JQNINRJQEN F(M AININQ' ALRR ST AF F
. MARCH '80 SHIPPING GUIDE 'kADI0 ACTIVE MATERIAL SHIPPING GUIDE's
. PREPARED BY CONSULTANT FIRMe JULYe'78
- w. . m+e ..m ,
__ .. - _ - -e m o _ _
4 _ . ..- . .,
.ALRR-p{ CON UNC DECOMMISSIONING DATA SYSTEM GENERAL INFORMATION REPORY 72CLjQ4 _ _ _ . _ _ _ .
4 . SYS/ COMP.
s SYSTEM / COMPONENT . NUMBER . ENTRY TITLE g...............................................................................
. DECOMMISSIONING PLANS ' PLAN FOR DISM4NTLING THE AMES LABORATORY
, RESEARCH REACTOR' REACTOR DIVISION. AMES
. LABORATORY
. PART At ' PLACING THE REACTOR IN STAND-BY
. STATUS *e NOV'77
. PART Bt ' DISPOSAL OF REMOVABLE PARTS'e
. AUG*78 PART Cl ' RE MO.VJ Nfr_JIAClGR. IN_TIRN ALS TMIURC ' _, ._ . , ___.._ . _ . . _ .. _ .
. SECTION II FY79 PORTIONe NOV'78 SECTION 23 FYB0 PORTIONe AUG'79 "
. PART D1 ' REMOVAL OF REMAINING RADIDACTIVITV'e
. MARCH'81 AL OPERATING LIMITS'AND POLICY IN ABOVE DECOMPISSIONING PLANS ALSO -
- ADJUSTMENT OF ALRR OPERATING POLICY'e MAR'81
.' OPERATING POLICY *e MAY'81 t BID SPECIFICATIONS, PREPARED BY CONSULTANT FIRM, REVISED BY ALRR STAFF,
. REVISED AND APPROVED BY CHICAGO OPERATIONS OFFICEe DOE i
I . ' REMOVAL AND DISPOSAL OF THE ALRR TOP PLUG
- 1 -s . . DEC'78
' REMOVAL AND DISPOSAL OF THE ALRR D20 TANK *
~
00 . '
I FEB'79 . . _ . . . _ , . __ __._,._ ., _
. ' REMOVAL AND DISPOSAL OF THE ALRR THERMAL t . SHIELD'e APRIL *79
. ' REMOVAL AND DISPOSAL OF THE ALRR THERMAL
. SHIELD TANK AND CONCRETE REACTOR PEDESTAL'e
. AUd'79
. . QUARTERLY FROGRESS REPORTS ISSUED FROM JAN'78 THROUGH SEPT'81 .
.++++++++++++++++++++++++t+++++++++++++++++++4++++++++++++++++++++++44++++++++++
. DECOMMISSIONING INFORMATION
. PERSONNEL 9ADIATION EXPOSURE
. NUMBER OF PERSONNEL MONITOREDi 92
. AVERAGE DOSE IN MANREM8 0.754
. TOTAL MANREM USED1 69.4
. DOSE TO PUBLIC IN MANREMI DNA
.+++++++++++++++++++++++++++++++++++++++++++++4+++++++++++++++++++++++++++++++++.
-A h -e
- . _ _ . _ _ . _ . _ _ _ . . . . _ _ . _ _______ __ - .. e- _ _ s_ m _
FAGE NO. 3 . .
.ALRR-DECON UNC DECOMMISSIONING.. DATA . . . , SYSTEM GENERAL INFORMATION REFORT 72C1104 s .SYS/ COMP.
4 SYSTEM /COMFONENT . NUMBER . ENTRY TITLE 4=assamassosssenesses.asseemas.sassnessnessi .sseammasesseesssssssssssssssssse.
. NOTE CONCERNING F OLLOWING COST _ INFORMATION-
. IN ORDER TO MAhE AFFROX! MATE COST COMPARISON $e ALER COST DATA MAY BE ASSUMED
. TO BE IN 1980 DOLLARS. AS COST ITEMS BECAME DUE. THEY WERE PAID ON AFFROX-
. IMATELY THE FINISH DATE OF THE SPECIFIC COST ITEMS BEING CHARGED.
.+++++++++++++++++++++4+++++++++++++++++++++++++++++++++++4++++++++++++4++++++++
DECOMMISSIONING COST
SUMMARY
ITEM COSiet SUMSe+
. A. A0 MINISTRATION \ DOCUMENTATION 6.36ES I) ADMINISTRATIONe DOCUMENTATION, SUPERVISION 5.103E5
. 2s SECURITY 1.257E5 B. OFEkATIDNS AMES LABORATORY 2.2793E6 Il REACTOR OPEAATIONSI SALARIES. BENEFITS ETC. 7.364E5
- 2) F JRCHASED SUF PLIES & SEkV!CES 4.555E5 3's IN-HOUSE SERVICES 3.827E5
. 4) HEALTH PHtSICS 6.727E5
. 5) COUNTING F0JIPMENT 3.2E4 C. OFFkATIONS. SUBCONTRACT 04 5.929E5 5.929E5 l
d D. WASTE DISPOSAL 6.015E5 UD In F AthAGINGe AME S L ABORATORY 3 12E4
. 2) PACkA0!NG. SUBCONTRACTOR 5.05E4
. 3) CASK RENie UASlE SHI F P !dG e AMES LABORATORY 1.62RE5
. 4s CASK RENT. WASTE SHIFFING. SUBCONTRACTOR I.875ES
. 5) DISPOSAL. AMES LABORATORY 9.63E4
- 6) DISFOSAL. SUBCONTRACTOR 7.37E4 E. S!1E RESTOFATION 2.253E5 2.253E5
. DECOMMISSIONING COST TOTAL 4.335E6
. LABOR RATES (+/HR) DNA
. WASTE DISFOSAL RATES
. BURI AL COSTS FER CU FTI 4.29 CASK RENTAL RATESI DNA
. TRANSFORTATION RATES! DNA SURCHARbESI DNA A
PAGE NO. 4
.ALRR-DECON UNC DECOMMISSIONING DATA SYSTEM GENERAL INFORMATION REPQR] ,,12[1].94 _
s .SYS/ CORP.
8 SYSTEM / COMPONENT NUMDER . ENTRY T s .................................................ITLE.........................
. OTHER COSTS (TOTAL THRU DECOMMISSIONING PERIOD) ,__, ,,,,,
. UTILITIESt 4 186E5
. MISC. SUPPLIES AND
. SERVICEst 6.342E5
. NUCLEAR inset H/A
. LICENSE FEES! N/A
. FINAL SITE SURVEV8 SEE SPECIAL SECTION AT END OF THIS REPORT
. TAXESI N/A
. REAL ESTATE SALE VALUE! P/A
. MATERIAL DISPOSAL INFORMATION
. RADIDACTIVE WASTE . SALVAGE DISPOSAL
. NUMDER OF SHIPMENTSt 83 NUMDER OF SHIPMENTSI 27
. TOTAL VOLUMEt 40830 CU. FT. TOTAL VOLUMEt 4400 CU.FT.
. TOTAL MASS 1350 TONS TOTAL WEIGHT! I4.9 TONS
. NUMBER OF CONTAINERSS 933 SPENT FUEL, CURIES! 3.12E5
. TOTAL RADWASTE D20 AND CONTAMINATED
. INVENTORYe CURIES! 6832 EQUIPMENTeCURIESI I.2E4
. TRANSPORT COSTS 8 637400 hO C3 . FINAL SITE CONDITIONSe
SUMMARY
I ____ .,
. DASIS FOR CRITERIAt DOE ORDER 5480.le CNAPTER XIe TABLE II
. NRC REGULATORY GUIDE I.84
. UNOFFICIAL LIMITS ENDORSED DV DDE-CH
. CRITERIA
SUMMARY
t UNRESTRICTED RELEASE UNATTAINABLE ' MONITORED USE'
. CRITERIA UTILIZED
~~' ~ ~ ~ ~ ~ ~~~ ~
~~
. INSTRUMENTS USED8 TECH. ASSOC. PUG IE ORNL CP-5
. EPERLINE PAC 40 VICTOREEN 470A
. NMC SMEAR COUNTERS VICTORLEN THYAC III
. TELETECTOR R METERS TRACOR NORTHERN GE LI DETECTOR SURVEV RESULT
SUMMARY
8 FINAL SURVEY INCOMPLETE-WILL DE PUBLISHED AT A _ _ _ , , _ . , _ , _
. LATER TIME
+ - - = * ' * - -
,,. . - , _ w-Amerh* -e
- - - . f __
FAGE NO. 5
.ALFR-DECON UNC DE LOMMISS10NING DAT A Sf STEM GENERAL INFORMATION REPORT 72C1104 4 .SYS/ COMP.
s Sf5(iM/COMFOhENT . NUMPER , ENikV TITLE 4=======-s===========.========. =======================.=======================e.
.COMF AE ISON ITEMS TOTAL COST OF DECOMMISSIONINGI 4.3344E6 DECOMMISSIONING COST
= COST / UNIT NO. OF UN!!S IIFM NO. OF UNITS COMPARISDN COSTS CURIES 6832 634.43 DOLLARS / CURIE
. FAD WASTE (CU FT) 40830 106.18 DOLLARS /CU FT SPENDING RATE (MONTHSn 45 96320 DOLLARS / MONTH PnWtR RATING .MWE) N/A N/A DOLLARS /MWE
. LIFETIME (MWDin I.52E4 285.16 DOLLARS /MWDT TOTAL MANREM USEDI 69.4
. NO. OF UNITS e . ---------------------------- = UtiiTS/MANGEM N . TOTAL MANREM a
I ITEM NO 0F UNITS COMPARISON
. RADIONUCLIDE INVENTORY 6832 98.44 CURIES /MANREM (CURIES)
. RAD WASTE (CU FT) 40830 588.33 CU.FT./MANREM
. TOTAL COST (6) 4.3344E6 62455 DOLLARS /MANKEM
. LIFETINE MEGAWAIT DAYS 1.52E4 219 MWDT/MANREM 4 THEGMAL (MWDT)
. F 0WE R R ATING t MWE) N/A N/A MWE/MANf.EM
. COST CONDITIONS ALL COSTS ARE AS CHAEGEDs mND WERE PAID AS THET WERE FRESENTED THROUGM
. THE AFPROXIMATE FOUR YEAR DECOMMISSIONING PERIOD.
. _. ~ . ;- - -.n... . ~ . ~ , . - . . - . -
. . . . ~ . _. .
f i
j '
PAGE NO. 1
.ALRR-DECON U.N.C. DECOMMISSIONING DATA SYSTEM - DECOMM CODE TABLE /INDEX 7231102 , . _
4 FACILITY .SYS/ COMP.
{ 4- SYSTEM / COMPONENT , . NUMBER . . .
, 01 . A.. PLACEMENT OF REACTOR IN STANDBY STATUS 4 01.01 A-1 DISPOSE OF FUEL 01.02__ A-2 DISPOSE OF D20 ,_, ,
01.03 A-3 DISPOSE OF THERMAL SHIELD WATER
, 01.04 A DISPOSE OF PLUG COOLING WATER
.01.05 A-5 REMOVE EXPERIMENTAL EQUIPMENT
} 01.06 A-6 DISPOSE OF RADI0 ACTIVE PARTS (PRIOR USE)
- 01.07 A-7 REACTOR FACILITT SURVEILLANCE (PRE-FUEL DISPOSAL)
OJ20_8 A-8 EFFLUENT AND ENVIRONM(NTAL MONI[QRINQ_ _,_ , _ _ , _ _ , __
01 09 A-9 REPORT bRITING 01 10 A-10 FABRICATE DISMANTLING TOOLS 01.11 A-11 REMOVE COOLING TOWER 01.12 A-12 CONSULTANT SERVICES ,
01 13 A-13 REMOVE WATER TOWER +
j 01.14 A-14 ADD REACTOR ROOM ACCESS DOOR 02 'd . DISPOSAL OF REMOVABLE PARTS
' 02 01 B-1 DISASSEMBLY AND DISPOSAL OF CONTRLL RODS 02.02 3-2 REMOVAL AND DISPOSAL OF CURRENT REACTOR PLUGS ,
- e AND E0u!PMENT . _ . _ , _ _ _ . , , , , . . , _ , _ . ,
02.03 B-3 REMOVAL AND DISPOSAL OF TOP PLUG (REACTOR i $ TANK PLUG) ,
! 02.04 3-4 DISMANTLEMENT OF GONTROL ROOM ELECTRONICS 1 $ AND CONSOLE REACTOR FACILITY SURVEILLANCE (FUEL REMOVED) +
[a pg 02.05 02.08 B-5 B-A EFFLUENT AND ENVIRONMENTAL MONITORING j
i 1 8 (EXTENSION OF A-8) l 02.09 B-7 REPORT WRITING (EXTENSION OF A-9) i 03 C REMOVAL OF REACTOR INTERNAL STRUCTURES C-1 l
_ _0 L.,01 REMOVAL OF ELECTR.JS_A W EAR F ROM _R EE T OR , _ _ _._ _ , _ , . . . _
- 4 BASEMENT 93.02 C-2 REMOVAL 8 DISPGSAL OF D20 PURIFICTION
- EQUIPMENT
! ~03.03 C-3 CLEAN OUT PUMP ROOM AND REACTOR BASEMENTe INC.
! e PRIMARY COOLING SYSTEM. PLUO COOLING SYSTEMe .
e TMERMAL SHIELD SYSTER. HCLIUM SYSTEM EMERGENCY '- ~~~~ '- f 4 C00ETNG SYSTEMe IRRADIATED AIR SYSTEM, SAMPLE 8 TRANSFER (RABBIT) SYSTEMe SECONDARY COOLING g
e SYSTEM.
i 03.04 C-4 REMOVE AND DISPOSE OF CORE TANK
} 03.05 C-5 SEAL THERMAL SHIELD TANK TO CONTAIN SHIELDING
' ~ ~ ' ^~^
03.06 C-6 OVEe SiGRENT AND DISPOSt~iiF7HIRMA S'HlEED~~~ '
l 8 _ . STEEL 2
03.07 C-7 REMOVE THERMAL COLUMN GRAPHITE 8 WATER CANS 4 03.08 C-8 DISPOSE OF REMOVABLE PARTS OF TMERMAL SHIELD I
- TANK U
1
+
4 1
. _ . + - - _ _
_ 4 - e.., .am . . - . ..u # ,- 6-.
< %.a u ,mw , +. _ . _, _ 4 # _. . .* .+. . , w.% ~ . .
J 4
l .
_ _ . _p .7_____
.&lER.BrfnN H.M_r_ DrrnamTctinMfun DATA EvtTru . hrenum rnnr Taki r /T Mhr Y TSaltn9
- e FACILITY .SYS/ COMP.
- STSTEM/CORPONLNT NUMBER . _
a e...................................................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................................................
3 03.09 C-9 . REACTOR FACILITY _ SURVEILLANCE (SAME AE 3-5)
. 03.10 .C a EFFLUENT renMYruuavinM AND ENVIRDNMENTAL nr parurnut Pennes 1 MONITO. RING d- 03.11 C-11 REPORT NRITING AND GENERAL SUPERVISION 8 __m ..._(CONTINUATION OF. PREVIOUS PROGRAM)
, 04 D REACTOR DISMANTLEMENT AND FACILITY REPAIR f oat 91. D-1 REMOVE ALVMINUM SHEETINE_EROM REASISS_t1RESIAL ,. ,,,,,.
l 04.02 D-2 REMOVE REACTOR PEDESTAL 04.03 D-3 , REMOVE UN-NEEDED REACTOR EXHAUST SYSTEM
, 04 04 D-4 REMOVE REACTOR EXNAUST STACK
, 04.05 D-5 REPLACE REACTOR ROOM FLOOR, FILL IN AND .
- COVER POOL 7 oq.0a D.a nrunur Nov rrit 1 04.07 D-7 REMOVE NOT WASTE TANK AND LINES f 04.09 D-8 DECONTAMINATE AND DISPOSE OF MISCELLAMEDUS
- -a STORAGE AND TRANSFER CASKS
} '04.09 D-9 DECONTAMINATE AND DISPOSE OF REMAINING RESIDUE 1 04 10 D-10 . ENVIRONMENTAL MONITORING AND HEALTH PHYSICS j $ COVERAGE (EXTENRIQg_DF C-10) ,, ,,_;, ,
4 04.11- D-11 REACTOR FACILITY SURVEILLANCE (EXTENSION OF E-93
, 04 12 D-12 REPORT WRITING (EXTENSION OF C-11) j g 04.13 D-13 DECOMMISSION REACTOR DRAIN LINES
'l- nO 04.14 D-14 DECOMMISSION STORAGE POOL 00 04.15 D-15 REMOVE AND DISPOSE OF ACDUSTIC CEILING MATERIAL s
?
6 M'm. N N l T
e -
4 wem . ~-
_. . , . . . _ . . . _ - - _ . . ~ -
- i i
4
.an an nrens iuse arrnmutantnerun nata cyntru . ctr.mtrvraur rurur ar*DRI 7 7mi t OL _ . .. .. ,
SEVENT .SYS/ COMP.
8 DATE .NUMDER .. SIGNIFICANT EVENT DESCRIPTION 1 *======.========.==============================================================.
, 61 FACILITY CONSTRUCTION STARTED
. . _ . . ~ . . . - - . - . . .
650101 FACILITY CONSTRUCTION COMPLETED 450217 ~ ~~' INITIAL CRITICALITY 1 650712 INITIAL FULL POWER
~~ ~ ~ ~
660615 INSTITUTION OF ROUTINE OPERATION 3 741201 SNUTDOWN FOR MAJOR UALVE REPAIR OPERATIONS 750301 RE-INSTITUTED ROUTINE OPERATION 770501 REPAIRED MAJOR COOLANT LEAK RESULTING IN OROSS TRITIUM e CONTAMINATION OF INTERNAL REACTOR PEDESTAL 90LUME 770601 INSTITUTED PRE-DECOMMISSIONING EFFORT INCLUDING DOCUMENTATION .
8 REQUIRED BY DOE, AND ENGINEERING AND COST ESTIMATES
- ~
771231 FINAL REACTOR $NUTDOWN AND INSTITUTION OF D'EC OMMI SS'I d5ING
- PROJECT 011001 COMPLETED DECOMMISSIONING PROJECT k.
s . . . . - _ - . . . .
k
~ ~ . ,
6 t
t . . .
4 I
i l
i i
f.
~._-.__--_-___.____-__ - -.
4 PAGE NO. 1
.ALRR*DECON DECOMMISSIONING DATA SYSTEM - RADIONUCLIDE INVENTORY Hille , _ _ _ _ .
8 . .A.MEASUR.<-------RADIONUCLIDE------->.
._ ,8SYS(COMP,_ _ ._ _ _ . _ , . . _ . . . . _....... ,s/.EMENT . . . . . _ .. CURIES. DPM/ e e NUMDER . SOURCE MATERIAL DESCRIPTION .C. DATE . NAME . CURIES .Fie03 300CM2.
.g........,............................. ..............................................................................e3........ ...
02.01 CONTROL RODS A DNA CO 60 750 DNA DNA __ _ _ , _ _
02 02 COLLIMATERS. PLUGS. MISC. METAL A CO 60 24.9
__ 02 02_ _ PLUGSe SHUTTERSe STORAGE. LINERS, ,_A.. CO 60 0.01393 MISC. PEACTOR SYSTEMS EQUIPMENT EU 152 0.0003
'CS 137 0.00023 ZN 65 0.00014 02.03 GUIDE TUDE ASSEMBLY A CO 60 14 286 (SUPPORTED FUEL ELEMENTS AND CON-TROL RODS) _
..02.03 TOP PLUGe 2 SECTIONS _ _ _ A CO 60 0.029 03.03 RAbt!T TUDES DEAM TUBES, EXPER. A CD 60 33.1 FACIL.
i 03.04 ALUMINUM CORE TANK 4 CO 60 450 _ _ , ,
ZN 65 50 03.06 THERMAL SHIELD STAINLESS STEEL A FE 55 3573 AND ASSOC. RESIDUE CO 60 1862 NI 43 267 CD 109 11 AG 110 35 , _ _ , , , _ , , ,
04.02 REACTOR PEDESTAL CONCRETE C CO 60 145 198 I ~
AND ASSOC. RESIDUE H 3 64.0 1 04.06 HOT CELL DEMOLITION RESIDUE A FE 55 10.1 h3 1 CO 60 SOURCE CO 60 21.7 U
TH 232 0.0026 NI 63 09 1 04.09 NEUTRON GENERATOR EQU1P.. C CD 60 .06 CS 137 0.07 2N 65 0.03 H3 10 0
' 04 14 STORAGE' POOL DECOMM.' RESIDUE C CD 60 0.107 CS 137 0.027 _ . _ _ _ _ __ , ,
04.15 ACOUSTTC MATERIAL, 60K LDS. C CD 60 0.0002 d
(REMOVED FROM REACTOR CEILING)
REMAINING MISC. RADIONUCLIDE ^ 'A CO 40' 146.44
' " ~ ~ ' ~ ' INVENTORY" '
FE 55 52.30
. ZN 65 10.46 86+++++++++++++++++++++++++++++++++++++++++++++++++++++++++4++++4++++++++++++ . . _ , _
- . RAD 10NUCL 1DE INVEN T0RY T0iALS
( .
. FE 55 3449.76 CD 109 11.0
. CO 60 2734.094 H 3 74.0 _ _ . , _ _ _ _ _ _
. NI 63 267.9 CS 137 0.097
. ZN e5 60.49 TH 232 0.0026 i . AG 110 35.0 EU 152 0.0003 1
- S. - ~ - - . - - - - -~ - . .
l i
6 4
0
r
" '*' ~ ~ ~ ' -
~ PAGE NO. 1 .
.ALRR-DECON UNC DECOMMISSIONING DATA SYSTEM - PROJECT COST / EXPOSURE 7411132 s . . .C.SCHED .SCHED .ESTIM. .ESTIM. ACTUAL. ACTUAL.ACTUL. . ACTUL -
l 8 ACTIVITY. COST ITEM / .SYS/ COMP.A. START .COMPL . MAN .ESTIMTD. MAN .. START .COMPL . MAN . ACTUAL . MAN, .
$ SPEC NO . ACTIVITY . NUMBER .T.DATE .DATE . HOURS. COST $ . REM . DATE .DATE . HOURS. COST 6 . REM .
g.............................................................................................................
NOTE NOTE NOTE NOTE:
i 1 -- 3... 2 . _.3 . . _ . .
s++++++++++++++++++++++++++++++++++++++++++++++++++ete++++++++++++++++++++++++++++++++++++++++++++++++++++++++
01.01 DISPOSE OF FUEL D 780730 37.5E3 0 665 780630 43.3E3
, 01.02 DISPOSE OF COOLANTS D 780530 17.4E3 0.485 780530 35.1E3-01.03 INCLUDED IN A-2 DATA 01.04 INCLUDED IN A-2 DATA 01,.05, REMOVE AND RELOCATE D 780530 83.5E3 0 275 780630 _220,. 6E 3 , . . _
- EXPERIMENTS 01.06 DISPOSE GF ACTIVE D 781130 501.6E3 1?.5 790930 476.9E3 s PARTS 8 4ASTE 02.01 INCLUDED WITH 01.06 02.02 INCLUDED WITH 01.06 01.07 SECURITY D 194.9E3 .
,125.7E3__ _
i' 01.08 HEALTH PHYSICS D 596.5E3 NOTE 704.7E3 4 s SERVICES, EQUIP. . 4 01.09 REPORTS 1 .D 494.2E3 510.3E3 s SUPERVISION
. 01.10 FABRICATE SPECIAL D 60.0E3 11.1E3
~~~~s TOOLS 01.11 REMOVE COGElNG TOWER D 780930 19.2E3 790630 17.9E3 01.13 REMOVE WATER TOWER D 80 780930 48.6E3 g 01.14 ADD REACTOR ROOM D 790630 34.2E3 PO s ACCESS DOOR Ch 01.12 CONSULTANT D 90.7E3 46.2E3 8 _ _ . . _ . . _ _ . . ..
02.03 REMOVE TOP PLUG D 790330 211.7E3 2.92 790525 790630 85.5E3 0.021 1 $ ASSEMBLY 02.04 REMOVE ELECTRICAL D 781230 22.2E3 0.17 780530 225.8E3' s SYSTEMS
__ ___ 9h0.1 IN.CWpH.WJJH 02.04 .
02.05 RESTORE POOL D _ _ . _ _ . . . . _ . . .0.38' 45.0E3
- VISIBILITY 03.02 REMOVE D20 CLOSET D 790830 27.5E3 0 27 800730 23.5E3 03.03 CLEAN 0UT REACTOR D 790830 326.0E3 0.48 .
. 190830 _,__,. 228.6E3 4 R00M. PUMP ROOM.
I 4 BASEMENT 03.04 REMOVE CORE TANK D 790830 34944 82.4E3 1 004 790830 2246 87.4E3 0.75
.i 03.05 SEAL THERMAL SHIELD D 790130 11.8E3 4.9 790630 16.7E3 4 TANK 03.06 REMOVE CUTE SHIP D .1942J1 12900J ) . 3E 3. .J 0 rf e 80_0101J00830_10_499.22),6E 3 7.13 s THERM. SHIELD STEEL 03.07 REMOVE THERM. COLUMN D 790530 10 DNA 1.75 790525 GRAPHITE. 1ST HALF 03.07 REMOVE THERM. COLUMN D 791230 121.6E3 3.8 800330 22 5E3 1.4
- GRAPHITE 2ND HALF t
4
~ _. --
, . - . . _. . . 4 PAGE NO. 2
.anan-orrnu une nrrnmatccinutun nata evefru - panirrY rnefervenener saattss
- . . .C.SCHED .SCHED .ESTIM.. .ESTIM. ACTUAL. ACTUAL.ACTUL. .ACTUL 4 ACTIVITY. COST ITEM / . .
SYS/CCMP.A. START .COMPL . MAN .ESTIMTD. MAN . START *COMPL . MAN . ACTUAL . MAN .
eSPEC NO . ACTIVITY . NUMDER .T.DATE .DATE . HOURS. COST e . REM , DATE .DATE . HOURS .REN .
emessemos.esesseseommesseemese.mosassee...sommes.easses,eesse,eensees,meses,emesse,messee.messe. COST ,se $... .....
03.08 REMOVE PEDESTAL, e THERMAL SHIELD TANK D 800730 3806 015.0E3 14.84 800728 801130 2766 544.0E3 11.77
~
04.01 INCLUDED I'N'03.08 04.02 INCLUDED IN 03.00 04.03 REMOVE EXHAUST D 801230 64.0E3 0.28 810430 55.8E3
$ SYSTEMS STACA 04.05 REPLACE FLOOR D 800930 2333 20.0E3 0.94 810630 1664 75.8E3 0.80 04.06 REMOVE HOT _ CELL 8 0 811230 85.5E3 0.28 800430- 118.5E3 e STORAGE EUNRER 04.07 REMOVE HDTWASTE D 801230 33.5E3 0.58 810930 77.0E3
$ TANK & LINES 04.08 DISPOSE OF STORAGE D 801230 32.0E3 800330 __312 EE3.
- CASRS I 04.09 DISPOSE OF RESIDUE D 801230 9.611 810930 04 13 DECOMMISSION REACTOR D 0.38 810430 11.9E3
$ DRAIN LINES 4! 04.14 DECOMMISSION STORAGE D 2.10 801110 810630 40.2E3
- POOL .
i 04.15 REMOVE & DISPOSE OF D 810330 1414 105.1E3 0.68
., . ACOUSTIC MATERIAL e .++++++44++++++++++444444++++4444444444444++444444++44++++++44++444++++++++++++4 4
P4
'4 . NOTE 1- THE TOTAL TO BE OBTAINED FRUM THIS COLUMN IS THE MEASURED PERSONNEL I FYPntiler TOTAL FOR THF FMTfRF nrrnunf ttinuf un pen tret. FETIMAY1gg_QF . , _ .
. REACTOR EMPLOYEE EXPOSURE INFORMATION FOR INDIVIDUAL COST ITEMS WASe
. HOWEVER. NECESSANY IN. ORDER TO OBTAIN THAT TOTAL.
. NOTE 2- INFORMATION INCLUDED HERE REPRESENTS TOTALS FOR LISTED COST ITEMS,
. INCLUDING SALARIES, SUPPLIES AND OUTSIDE SERVICES. CONTRACTSe
. PACKA0!NGe SHIPPING AND DISPOSAL.
. NOTE 3- ACTU_4L MAN-HOUR AND MAN-REM DATA SNOWN HERE INCLUDE ONLY CQNTRAqlp_R __ _ .
. INFORMATION FOR THE PERIOD OF TIME ENCOMPASSED BY THEIR CONTRACTS.
.NDTE 4- kADIATION EXPOSURES INCURRED DV HEALTH PHYSICS EMPLOYEES ARE NOT
. SHOWN HEREe BUT INCLUDED IN EXPOSURE INFORMATION PRESENTED FOR ACTUAL
. INDIVIDUAL COST ITEMS.
e.. .o
- ---y ow w + ew..eeea--e % s>
- 'ehe w em e. wemw
. ,m. _ _ __ . . . . .. .. . . _ . . _ .. _..m ...__m _. . _ _ .
FAGE NO. 1
.ALRR-DECON U.N.C. DECONNICEIGNING BATA CTETFN - hntf R&TF 77G111A , _ _ ,
j 8 . . . . . . . . DPM . DPM .MEASUR. .
, 8 ' MAP . .ELEV . MAP .STS/CDMP. . R/HR . R/HR .100CM2 100CM2.EMENT . .
l 8 . REFERENCE . DUILDING . FEET .COORD. NUMBER .TVP.LONEP . UPPER . LONER .UPPIR , DATE . COMMENT .
g..................................................................................................................................,
< N/A REACTOR N/A N/A 01.06 CON -10.01 1200 DNA HORIZ. TANGENTIAL FACILITV PLUG e IN.
I a ava . enmasam =cartreymn.11PERIhENT
- 01.06 CON 0.3 HORII. TANGENTIAL FACILITT PLUGe 4 IN.
e DI An. REACTOR F ACE NO. 3 (REMOVED E ARLT) x 01.06 CON 7.0 75.0 DRUMS OF FUEL ELEMENT CUTOFFS (UNFUELED ENDS) 01 06 CON 0.35 VERTICAL THIMDLE V-3e DLDe 01.06 CON 2.0 GRAPHITE CAN FROM INNER END OF H-5 PLUG 01.06 CON 90.0 HORII. DEAN PLUE_H-5.7 5.IM. DIAM. (ORIGINAL) 01.06 CON 70.0 HORIZ. SEAM PLUG H-6 11 IN. DIAM (&R/HR 8 9 3') %MCLUDES FINAL FISSION PRODUCT 4 GENERATOR (FPG) HARDWARE 01.06 CON .50.0 500 HORIZ. BLAM PLUG H-6 11 IN DIAM. (ORIGINAL) l e INCLUDES SECOND FPG HARDNARE l 01.04 CON 31.0 ,____,,
MORIZ._gran Plug H-1 11_I4. DIAM. (ORIGINAL)
I 01.06 CON 10.0 VERTICAL PLUG 4THIMDLE V-Se (ORIGINAL) 02.01 CON 0.1 1 4E4 PLUOS AND SLEEVES, CONTROL RCD 02.01 CON 2.5 7.0 DRIVE SHAFTSe CONTROL ROD j 02 01 CON 110.0 CONTROL ROD DRIVE PIECESe (CUT 0FFS) 1 42.01 CON 7.0E3 CONTROL ROD. ORIGINAL DESIGN, USED 6 YEARS ,
~.JEliQl CQN 124EL .. ____
CONTROL ROR, RE-DESIGN .IN USE AT SHUTDOWN >
1 I 02.02 CON 1.0E3 NORIZ. DEAM PLUG H-7 4 IN. DIAN. INCLUDES ORIGINAL FPG HARDNARE (01* ) - (150R/HR 9 3')
8 i e 02.02 CON 17.3 HORIZ. DEAM PLUG H-9 4 IM. DIAM. (0.2 *R/HR DJ e 9 6') .
i 00 02.02 CON 100.0 2 0E5 HORIZ. DEAM PLUG H-9 6 IN. DIAM. (DEAM
- I g ._
CntLINATDR) -, . . _
i 02.02 CON 100.0 HORIZ. DEAM PLUG H-10 6 IN. DIAM. (DEAM 8 COLLIMATOR) l HORIZ. TANGENTIAL FACILITT PLUG, 4 IN.
02 02 CON 350.0 s SIAM. REACTOR FACE NO. 9 (10 R/HR. 9 3')
02 02 CON 20.0 NORIZ. TANGENTIAL FACILITY PLUG 6 IN. DIAM.
_1 ._._, _ _ REACIDfLfACL_NL 3.(0.25 R/HE G 3')
VERTICAL PLUG V-3 02.02 CON 0.5
'02.02 CON 2.5 VERTICAL PLUG V-5 i
02.02 CON 50.0 HORIZ. TANGENTIAL FACILITY PLUGe 6 IN.
4 DIAM. REACTOR FACE NO. 3 (1 4 R/HR. 9 3')
02 02 CON 15.0 NORIZ. LINEPe H-2 6 IN. DIAM. (0.7 R/HR -
8 , _ . # I*1 .
02 02 CON 45.0 HORIZ. LINERe H-4 4 _-INC. DIAM. 40.7 R/HR 4 .
9 3')
02 02 CON 50.0 NORIZ. LINERe H-5 7.5 IN. DIAN. (1.5 R/HR. ,
e 9 3*)
.l 02.02 CON e5 0 HORIZ. LINER, H-6 11 IN. DIAM. (2 R/NR.
$ t.3') - ..
MORIZ. LINER H-7 4 _.IM._ DIpM.~_(0.75 R/NR.
02 02 CON 50 0 9 3') .
s~ ~ ~~
~~~~02 02 CON 50.0 HORIZ. LINER H-S 4 IN. DIAM. (0.75 R/HR s , _,
O 3')
~
f a
4 i
e 4
PAGE NO. 2
.ALRR-DECOM U.N.C. DECOMMISSIONING DATA SYSTEM - BOEL_ FATE 72G1114 e
. . . . . . . . DP4 . DPM . MEA?uR. .
e, MAP __ .. .. _.ELEVi. MAP .ST5/ COMP. ,_R/HR ,. R/HR;.300CM2 800CM2.EMENT_3__ .
8 REFERENCE
. DUILDING . FEET .COORD. NUMBER .TTP. LOW .UFPER . LOWER . UPPER . DATE . _____ _ _ _ _ _ COMMENT _ _ _
s.......................................................ER ... .................................. ..............e........e........ ....
02.02 CON 45.0 HORIZ. LINER H-T 4 IM. DIAM. 41.5 R/HR.
e 9 3') '
,02.02 CON 50 0 HOR;2. LINER H-10 A Im. DIAM. (1.0 R/dR.
8 9 3*)
02'02
~
. CON 70.0 '~'-'HORIZ." yANGENTIAL LINERe 4 IN. DIAP.
8 ._ __ _ . . . _
(2.0R/NR 9 3') . . _ . .
.02.02 .. CON 25.0 HCRIZ. TANGENTIAL LIhERe a IN. D I 8.M .
e f3.0R R/NA. e 3*)
42.07 CON 70 0 huaIZ. DEAM PLUG H-2 IN DIAM. 415 R'/HR O'3E )
- 8 . - - - 2... _ . - . .
_ _ _ ._tBEAM COLLIMATPR).
02.02 CON 500.0 Ho#II. DEAM PLUG H-3 & IN DIAM. (7. R/HR.
8 t 3*) .(DEAM COLLIMATOR) 02.02 COM 50.0 e _ _ . _p3 Hou!.Z.
) DEAM PLUG H-4 4 IN DIAM. (1.0R/HR 02.02 CON 1.0E3 MORI2. DEAM PLUG H-5 7.5 IN. DIAM. (Al 2*)
- STAINLESS STEEL CONSTRUCTION ,
02.02 CON 7.0 35.0 YERTICAL LINER PIECES (CUTOFF) 02.02 CON 0.1 ~ HORIZON T AL PLUGSe _ THERKAL COLUMN, INNER EMDS 02.02 CCN 0.25 VERTICAL THIMSLESe SEVERAL 02.02 CON 11.C UERTICAL THIMDLE, V-5
" " ~ ~ ~ ~ ^"
02.0; CON 11.0 VERTICAL LINER. V-3 02.02 CON 20.4 VERTICAL LINER. V-5 g 02.02 CON 10.0 VERTICAL LINERe b-0 hO 02.02 CON 0.6 1.0 FUEL ELEMENT HOLD-DOWN PLUGS M3 02.03 CON 0.015 1.0 3000 SHIELD PL'J6 OVER CMRE T AKhe LO'e th SURF ACE OF I s LOWER SECTION _iQ113_R/HR 9 l'l , ,, ,
02.03 CON 200.0 300.0 GUIPE TUDE ASSEMBLY (SUPPORTS F.E.'% $
02.04 CON . 05 . _ ,, FISSION CHAMSER__ __
03.03 CON ._1000. PNEUMATIC SAMPLE TRANSFER DLOWER 03.03 CON _.0.01, PIPINGe, PRIMARY C00LANTe REM. FROM PUMP RM.
CEILING e 03.03 GEN 0.85 P9MP ROOM DELOW CCRt, SHINE THR'J PENEIRAt!0NS 03.03 COM 50 0 PMEUMATIC &&MPLE SVGTEM LINER h-1, 1 IN.
8 03.03 DIAM. (2 R/HR 9 3')
~" ~ ~ ~ ~
~ 03.03 ^ CON 150.0 PNEUMATIC SAMPLE SYSTEM LINCR. R-3, 1 IM.
s_ , __
DIAM. 45.0 R/HR. 38) 03.03 CON 45.0 PNEUMATIC SAMPLE SYSTEM LINEk R-4e 2 IN.
- DIAM. 40.S R/NR. 9 3')
03.04 CON 153.0 CORE TAmhe OUTSIDE SURFACE
. _.03.04_. CON 1.5E3 .. CORE TANK. VOLUME CENTER, Iff-PLACL e TAKEN THRU
- e. PLUG-
__ ._ _. ..._03.04 ___ CON 15.0 . _ _ .LARGE_ DIAMETER ALOMINCM CORE TANK SUPPORT RING 03.04 100.0 THERM. SHIELD ST AINLESS STEEL A*SEMBLY
$ (14 IN. FROM CONTACT)(40R/HR 9 4.5 FT) 03.04 450.0 THERM. SHIELD STAINLESS STEEL CUT PIECE.
TAKEN FROM MOST ACTIVE SECTION 03.07 ' CON 0.025 1.3 GRAPHITE STRINGERS FROM THERMAL COLUMN
- 1 4 ,'
O
.-/ x '
ss" i
s
+
s FAGE NO. 1
.ALEk-DECON U.N.C. DECOMMISSICNING' DATA iVSTEM - FROJECT LABOR 74F1132
+ACTIVITf. ! '. MAN .LADOR . MAN .
eSFEC NO DATE . t 06TEGOEY . WE E F.S . COST s. REM .
+....... ......s.... 4 ADnf .............................................................................................................
. " F E0 JECT LABOE COSTS REFAESEN' ONLY SERVICES OF REACTOR EMFLOYEES. ALL
. OTHER LAPOR COSTS WIRC INCLUDED IN SLDCONTEACTS AND IN Sf4VIET CNARGES 61 OTHrE AMES LAPORATCRY OR00*S.
.++++t++++++++++t+t+++64++++++ti++++++++++++++++++++++++++++++++++++++5+++++++++
01.01 Dh4 DISF0$E OF FutL DNA 1.3E4 DNA e 01. s .' DISPOSE OF FR1 MARY 2.0E4
+ COOLANT (D20) 01.03 DISTOSE OF THERMAL SHIELD NOTE-1 a COOLANT (H2O) 01.04 DISPOSE OF FLUG COOLANT NOTE-1 4 (H2O) 01.C5 ELMUVE EkFER. EQUIP. 5.7E4 01.06 DISFOSE OF ACTIVE PARTS 2.01E5 02.01 EONTPOL ROD DISPOSAL NOTE-2 02.02 FLUG & MISC. DISPOSAL NOTE-2 01.07 hECUkITY 1.09E5 01.06 HEALTH PHYSICS. 5.57E5
+ MONITORING 01.09 RE F ORTS & SUPV. 3.81E5 c t . t t, FA6RICATE TOOLS 1.5EI 02.03 FEMUVE TOP FLUG ASSR. 2 6E4 02.04 REMOVE ELEC. SYS. 3.0E4 g 03.01 CONTINUATION OF ABOVE NOTE-3 00 02.0L EESTOGE FOOL CLARITY 2.39E4 C3 03.02 REMOVE D20 CLOSET 1.15E4 I 03.03 CLEAN OUT REACTOE ROOM, 1.57E5 34.09 fuMF kOOMe BASEMENT NOTE-4 03.04 REMOVE CORE TANE 1.0E4 v3.95 SE AL ThEEM. SH. TANK 1 17E4 01.e4 DISPOSE OF THERMAL 1.15E4 a SHIELD FLATES(SS) u3.07 REMOVE THERM. COLUMN 7.5E3 4 bkAPHITE 03.08 DISF OSE OF EEMOVABLE 1 8E4 a FARTS OF THERMAL 4 SHIELD T ANA 04.01 EEMOVE FEDESTAL SAIN NOTE-5 04.02 EEMOVE PEDESTAL NOTE-5 04 03 REMOVE /DECON EXHAUST 3.48E4 4 SYSTEM 04.0L EEFLACE/kEFAIR FLOOE 1 00E4 04.06 EEMOVE NOT CELL AND 4.00E4 a OUTSIDE S10kAGE BUNKER 04.07 REMOVE UNDERGROUND HOT 2.50E4 a WASTE TANF $ LINES 04.00 blSFDSE OF MISCELL. 2.0E4 SHIELDED CASKS 04.13 DLCOMMISSION EMBEDDED 5.0E3 e HOT LINES
d i
4
! J PAGE NO. 2
. ALF:R- DE CON U.N.C. DECOMMISSIDNING DATA SYSTEM - FEDJECT LABOR 74F1132-sACTIVITt. . . . MAN .LA90R . MAN .
sSF EC NO DATE LABOR CATEGORY .WEFk$ . COST 4. REM .
s enas e see. ess o a . ease s sene mosema ssesse==== eeemme sease e.eeme.n eesesseenmassenemonessessesseessesemessenessee mesessenesessessessess .
04.14 DECOMMISSION STORAGE FOOL 2.0E4 04.15 EEMOVE' ACQUSTIC MATERIAL 2.0E4
.+++++4+++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++
,N01E 1- LABOR COSTS INCLUDED IN 01.02
.NOIL 2- LABOR COSTS INCLUDED IN 01.06
. NOTE 3- L ABOR COSTS INCLUDED IN 02.04
.Ndli 4- LAROR COSTS INCLUDED IN 03.03
.N0fE 5- LABOR CDSTS INCLUDED IN 03 08 66sestesseesssesseeste8446sesesssestatsteestteesssettessettessesess***s*444440st I
00 a
i
PAGE NO. 1
.AlDD-DFfnM tl.M.P. LFPnMMTCCYMMTMM BATA SYCTrM - AI AD A DrpnDT TSrttin ,,, ,,,,, ,
8 . . . MAN- . . . DOS.
____3 ACTIVITY.STS/CDMP. ___._ ALAR A._ REM 4INIT I AL. F INAL . RED. .. -_ . . . .
eSPEC NO . NUMBER . DATE . ALARA COST ITEM . COST $. SAVED. MR/HR . MR/NR .FCT. ALARA EFFORT DESCRIPTION
. ___, g e a s s e s s e , s.s e s s e m agene.nes,seeeeeeeeeeeeeeeeeen,es.sese,sesse ,sessee.neamese,see,sessenesseeeeeeeeeeeeeeeeeeeeeeeeeeeeeeesomeonessee, M/A N/A DNA CRANE MODIFICATION BMA DMA DNA BMA BMA PDaur FFMMAMT NODIFfFD TD FYTFMD PDAME ,_,
a TRAVEL FOR FIXED OPERATOR LOCATION CONTAMINATION USED WATER SPRAY TO CONTROL AIRBORNE
$_ ._.__C O N T R OL_ _ _ _ _ _ _ _ . , __ _ . . . . CONTAMINA!!0N DURING REACTOR EDUIPMENT s MANIPULATION
~ ~
CONTAMINATION APPLIED LINSEED OIL SPRAY TO REMOTELY
_ __ 8 _ . . _ _ . . _ . _ . , , _ . ~ CONTROL _ __ _. - _ FIX CONTAMINATION ON ACTIVATED EQUIPMENT a - TO BE MANIPULATED RADIATION EXPOSURE MODIFIED EXISTING 2 INCN LEAD SHADOW e CONTRot SHfrtDS IN CONJUNCTION WITH LEAD ELASS .
s WINDOWS TO PROVIDE SHIELDED ENCLOSURES FOR HI-RAD OPERATIONS CCTV UTILIZED CLOSED CIRCUIT TELEVISION FOR NI-RAD MANIPULATIONSe E.G., INSERTION OF 4
8 LOADED LINERS INTO CASK _
FLEX DUCT . _ _ _ . ,
UTILIZED HI-VELOCITY FILTERED VENTILATION I _ _ _ _*..________ . . _ VENTILATION SYSTEM FOR CUTTING AND WELDING ACTIVATED /
00 e - "' ~
CONTAM. MATERIAL, APPLIED DIRECTLY TO O s WORK WITH FLEX-DUCT UNDEAWATER UTILIZED NYDRAULICALLY DRIVEN CUTTING"
_ $. _ _ . _ . _ _ _ . CUTIING _ ___ _ __. EDUIPMENT FOR. UNDERWATER CUTTING OF ACTIVATED MATERIAL
~ - ~ ~ '
FORK L'IFf" FABRICATED BOOM EXTENSION FOR REMOTE
- MODIFICATION MAgIPULATION _ . . _ ,
RADIATION UTILIZED LEAD SHOT SAOS FOR HOT-SPOT
- EXPOSURE CONTACL SNIELDINS WHERE REMOTE MANIPULATION WAS NOT FEASIBLE TRUCK ENTRY TO PROVIDED REACTOR ROOM ENTRY FOR RLMQJJ __
- REACTOR ROOM CRANE USAGE IN LOADING HI-LEVEL WASTE
_____8 ____ ... DIRECILT.INTO TRUCK-MOUNTED CASKS 4
-w.v---., sms.4_e ,e, ,u- s e --me .
__ _.. w ,
. _ , o _ . . _ . ee e
@ w M.
~1'
~ '
PAIE NO.
.6LRR.BFrnM tl.M.C. MrrnMMftRfnM1MR h&Ta CVSTrn CMTDMrMT DFDnDT Tart 19A 8 . TRIP . . . . .T. . DOT .<-- WASTE --->.
4 SHIP . SHIP..LEN. .MR/HR .MR/HR .MR/HR . RADIONUCLIDE.. ACTIVITY. . WASTE. .Y. PHYS . . CHEMICAL . SHIP .CUSIC .. . . * .
s DATE .NUM . MILES.CONTCT.6 FEET. CAD g........................................................................................ORM
. NAME . CURIES.. SPEC NO .DESCRPTION.P. FORM . F . CLASS. FEET . POUNDS.
. COMMENT! THE DOCUMENTATION STATES THAT . WITH THE EXCEPTION OF ACTIVATED CARBON
.Sirrt ITEMS. CD A0 19 THr naraTLY PartnMikadT RantnWiset inr VM at t w&RTr. ~ ~
. FISSION PRODUCT CONTAMINATION WAS VIRTUALLY NONEXISTANT.
.4++++++++++++++++++++++++++++++++++++++++++t+++++++++++++++++++++t+++++++++++++
780807 1 1100 DNA DNA DNA CO 60 3.42 01.06 SHIELDED A LSA _ 90.00 10402 DRUMS 780814 2 1100 DNA.. ..DNA. ..DNA . CO 60 . 6 520 01.06. SHIELDED ..A-
..LSA_.90.00 8496 s DRUMS 780814 3 1100 DNA .DNA DNA CO 60 0.0146 01.06 DRUMSS A LSA 424.67 27958.
s SHIELD, s PIECES 780816 4 1100 DNA DNA DNA CO 40 250.0 01.06 CONTROL A LSA 15.00 200
- a ROD e pirrrt
~
780821 5 1100 DNA DNA DNA CO 60 .003 02.01 DRUMSS A LSA 424.67 41120 s ' SHIELD s PIECES 780825 6 1100 DNA DNA DNA CO 60 .022 01.06 DRUMSS A _ LSA 15.00 36120 s SHIELD e
PILCES _ . . .
780906 7 1100 DNA DNA DNA CO 60 500.0 02.01 CONT,ROL A B 15 00 375 s ROD , ,
g a PIECES 00 781211 9 1100 DNA DNA DNA CO 60 .011 01.06 DRUMS 4 C LSA 576.00 24900 00 s .
BOXES I
7ggggg 9 1100 LNA DNA DNA to Ao 10.11e 61.ca 'Launt 1M A LCa 90.00 9630__ ,
a CASK 790413 10 1100 DNA , ..DNA .DNA CO 40 6 374 01.04 90XES & ._ __. LSA _ 816.00 24950 s SHIELDED . A '
s DOXES 790601 11 1100 6.0 3.0 .03 CD 60 14.286 02.03 GUIDE TUDE A LSA 77.90 '400 s (SSEMBLY.
s .
(CASK) 790605 12 1100 40.0 0.3 .03 CO 60 0.005 02.03 TOP PLUO A LSA 251.00 56000 s .
SECTION 790608 13 1100 50.0 7.0 0.03 CO 60 0.024 02.03 TOP PLUO A LSA 177.00 55000 s SECTIOk 790710 14 1100 100.0 10.0 0.9 CO 60 32.5247 CONCRETE C LSA ;118 t22_39400 4 SPLYWD s 30XES
. CO 60 0.040 s790723 15 1100 40.0 5.0 0.02 BOXES (9) C 8790810 16 1100 40.0 5.5 0.50 CO 60 500.000- CORE TANK A 790917 17 1500 100.0 13.0 0.13 CD 40 0.26488 DRUMS, C LSA 861.50 38601 s -BOYER C 790921 18 1100 15.0 10 0 0.07 CO 40 33.100 CASH 5 (2) A LSA 25.10 800222 19 1100 _ 07 ._0.03 _.0.03_ _CO.60_ 0.002 . _ . PLYWOOD C ,_ LSA. 846.00 39200 4 DOXES 69) 800321 20 1100 1.10 0.07 0.03 CO 60 0.003 PLYWOOD C LSA 1161.0 30000 4 DOXES 49)
I , _ - . .
4 4
d
.ALRR-DECON U.N.C. DECOMMISSIONING DATA SYSTEM - SHIPMENT REPORT 74C1124 ~
e TRIP . . . . .T. . DOT .<-- WASTE ---F
$ SHIP . SHIP .LEN .MR/HR eMR/HR .MR/HR , RADIONUCLIDE^. ACTIVITY. WASTE ~
.Y. PMTS . CHEMICAL . SHIP . CUBIC . .
't DATE .NUM '. MILES.CONTCf.4 FEET. CAD .' NAME .CUPIES . SPEC NO .DESCRPTION.P2 FORM .~ FORM . CLASS. FEET .' POUNDS.
s................................................................................................................... ..............,
800501 21 '1100 '35.00' 5.00'~0'.13 CO '60 961.000 03.06 ~~ CASK ~ A LSA 124.00 9241 e (METAL) .
" ~ ~ ~ ~ ~ ~
800505 22 1100 110.00 9.00 0.02 CO 40 10.641 90XES 47) C LSA 1064.0 31317
$ DRUMS (24) 800510 23 1100 35.00 7.00 0.05 CO 60 795.950 03.06 CASK A LSA 126.00 9400
.800604 24 ._1100__5 00 Q.30 _,0 93..CO 60. 0.015 _
TANK $s 4 _
LSA 1126.1 38386 8 BOXESe a DRUMS ,
800707 25 1100 100 00 2.00 0.03 CO 40 2237.00 03 06 CASK A LSA 126.00 10500 8 . . _ __
STAINLESS e STEEL 800716 26 1100 13.00 2 00 0.06 CO 60 899.00 03.06 CASK- A _ LSA 124.00 4500 4 STAINLESS s STEEL C ~~
800730 27 1100 40.00 DNA 0.06 FE 55 0.001 90XES 1 4 DRUM 3 . .
800008 28 1100 7.000 0.4 0.03 CO 60 100.0 03 06 CASK. A LSA. 124.00 10e00 STAINLESS STEEL 800923 29 1500 1.00 0.4 0.04 C0 60 0 3003 TANK file A LSA 784.00 2490_Q_
e BOXES (4) a 800923 30 1500 100.00 7.0 0.04 CD 60 0.016 BOXES (11) A LSA 1047.5 34375 8 801003 31 1500 DNA DNA DNA CO 60 50.000 CASK A LSA 103.00 4750 00 810119 32 1500 35.00 3.0 0.03 CO 60 0.162 DRUMS, A LSA 763.00 35592
]
4h
- DOXES I
810323 33 1500 31.00 4.0 0.15 CD 60 0.134 BOME1(10) A LSA 952.00 3q450 ,,
810323 34 1500 0.04 0 04 0.04 CO 60 0.0001 BOXES 410) A LSA 1300.0 17100 810323 35 1500 _0.04 0.04 _ 0.04 CO 60 0.0001 90XES(10) A LSA , ,1300.0 10600-810604 34 1500 25.00 0.75 0.05 CD 60 32.747 CASK (14 A LSA 200.00 12000 DRUMS) 810611 37 1500 ~ 45.00 .9.00 0.04 CO 60 0.768 - DOXEC (9) C LSA 857.00 27000 RESIF _ . ,
o COLUt:N(1)
DRUMS (18) , C LSA 1079.0 33055 810910 38 1500 5.00 0.17 0.04 . CO 60 .017.
s DOMES (9) 810918 39 1500 C0 60 0.149' DRUMS (24) .C LSA 940.0 32050 BOXE3(59 TANK. RES. . _ _ . . _ _ _ ,
COLUMN . .
' C0 40 ' 0.240 RUSDLE. C SOLID ,ELEM/0X. LSA 320 38224
~ 200818 101 '1500 '0.05~~0.04 ' - - 0.04 ~
O.1058 'REBAR.TUDE
' H '3 C SOLID ELEM/0X_ LSA 320 36312 800820 102 1500 0.05 0.03 -0.03 'MCO '360 0.149 0.0656'
-RUSDLE 800820 103' 1500 0.08 0.05 0.03 CO 60 0.233 RUSSLE. C SOLID ELEM/0X LSA 320 39980, ,_
H 3 0.1027 RE9*R C SOL.ID. ELEM/0X - - -LSA- 320 42502 800822 104 1500 0.09 0.05 0.03 CO 60 0.256 . . - - -.____.RUSILEe-
_C. SOLID ELEM/0X LSA 320 43600 800825.105 1500 0.08. 0.15 0.0a CO 60._0.276 _ RUBBLEe.
H 3 0.1217 REBAR e
1 v
._ . .. .a. ... _ _ _ _ . . _ .. . _ . - .
.ALRR-DECON U.N.C. DECnMMfEEinMfMG DATA EYRTEM - KWTPMfMT DFPnRT 7AP199A -...._.
8 TRIP . . . . .T. . DOT .<-- NASTE -~~)
. 8,. SHIP . SHIP .LEN _ MR/HR...MR/HR MR/HR . RADIDMUCLIDE .ACTIUITT. WAS T E ... .Y. PHYS . CHEMICAL . SHIP . CUBIC . .
- DATE . MUM . MILES.CONTCT.6 FEET. CAD . NAME . CURIES . SPEC NO .DESCRPTION.P. FORM . FORM . CLASS. FEET . POUNDS.
9888888.T****.*****_s**.**""."*****."****".******a*******."***=***.**********.# ******.**********.*****.******.8=*****.**************.
800825 106 1500 0.15 0.08 0.04 CO 60 RutDLEe C SOLID ELEM/01 LSA .320 38499 u i 0.233, n ios erman , , ,
800828 107 1500 0.15 0.05 0.03 CO 60 0.263 RUBBLEe C SOLID ELEM/0X LSA 320 43622
.N_3 .0 1159 REDAR
_ _ . . _ . .800829 108_ . _1500 0.70_ _ _ _ _ _0.12.-.0.04 CD 60 0.231 RUBBLE, C SOLIDELEM/0X . . . . . _ LSA 480 43196
_.._H 3 .0.1018 REDAR .- .. .
800904 109 1500- 0.20 0.05 __0.03 CO 60 0.248 RUBBLE, C SOLID ELEM/0X__ LSA 320 41402 H 3 0.1093 artAR ,_
800905 110 1500 0.05 0.04 0.04 CD 60 0.265 RUBBLE, C SOLID ELEM/0X LSA 352 43670
_ _ ._ .H 3. 0.1168 REBAR _. .. .
_800905 111 1500 . 0.05 . 0.03. . . . 0.03 CO 60 0 257 RUBBLE, C SOLID ELEM/0X . LSA . 352 41559 H 3. 0 1133 REDAR .
800906 112 1500 0.06 0.04 0.04 CD 60 0.207 RUBBLEe C SOLID ELEM/0X. . . . . LSA. 384 42588 H 3 0.6917 mraan , ,
800906 113 1500 0.06 0.04 0.05 CO 60 0.240 RUDDLEe C SOLID ELEM/0X
- LSA 320 39662
_ .H 3 0.1058 REBAR 800911 114 1500 0.15 0 07 . 0.04 CG 60 0.234 RUDDLEe C SOLID ELEM/0X LSA 448 43026
_ H 3 0.1031 REDAR 800916 115 1500 0.14 .0.04.. . _0.04 CO 60 0.265 RUBBL(e C SOLID ELEM/0X__ LSA 320 42?96 i
H 3 0.1168 REB &R 4
800916 116 1500 0.80 0.07 0.04 CO 60 0 247 RUDDLEe C SOLID ELEM/0X LSA 480 41029 H 3 0.1089 REBAR 800916 117 1500 0.15 0.05 0.03 CO 60 0.259 RUBBLEe C SOLID ELEM/0X .LSA._ _ 322 43004
[g H 3 0.1142 REDAR on 800918 118 1500 1.30 0.07 0.03 CO 60 0.195 RUDDLEe C SOLIU ELEM/0X LSA 494 41976 g H 3 0.0860 REBAR. ___
s . AtuM.
.800920 119. 1500. 22200.._4.00 0.00. .C0 40. 9.946 . RUDDLE, . C SOLID ELEM/0X _ LSA _576 .43491
. H 3 4.384 REDAR 800924 120 1500 .32 00 5 50 0.05 CO 60. 8 191 . RUDDLEe. C SOLID ELEM/0X LSA 352 42724 H 3 3.6104 REDAR 800925 121 1500 30.00 9.00 0.07 co ao a.119 mummar. c not to rtrM/or tsA A72 4 q gig . ___ ,, ,
H 3 3.5707 REDAR, 8 _ ALUM.
800925 122 1500 35.00 5.00 ...0.07 . CO 60 4.365 RUBBLEe C SOLID ELEM/0X LSA 608 42440
_.H 3 1.924 REDAR.
~~,-. ._ _
AtuM.
800926 123 1500 1.30 0.20 0.03 CD 60 0.112 RUBBLE, C SOLID ELEM/0X LSA 528 41g_2 (___ . _ , , ,
H 3 0.0494 REDAR,
~ ~ ~ ~4 ^ ALUM.
80092f t24 '~15'00~10.66i.90
~
0.03 ~C0 A0 0.113 RUBBLEe C SOLID 'ELEM/0X 'LSA 560 39173
_H._3.__0.0498 _, REDARe
. . . . 8 _.
ALUM.
800927 125 1500 0.08 0.03 0.03 CD eo 0.028 RUBBLEe C SOLID ELEM/0X LSA 56) 39218 _ .__.
H 3 0.0123 REDAR, 8 _ _ . . ALUM. . .
801002 126 _1500 27.00 4.50 0.15_ _CO _ _60. _ 10.600_ RutDLEe C SOLID _.
. . ELEM/0X . _ _ .LSA_ . . . 384 44244
. . __H _ 3. 4.6722 REDAR j _ _
PAGE NO. 4
.ALRR-DECON U.N.C. DECOMMISSIONING DATA SYS*EM - SHIPMENT REPORT 74C1124 a TRIP . . . . .T. . DOT .<-- WASTE ---i' 8 SHIP . SHIP ,LEN ,MR/HR .MR/HR .MR/HR , RADIONUCLIDE.. ACTIVITY, WASTE .Y. PHTS . CHEMICAL . SHIP . CUBIC .- .
- DATE' NUM . MILES.CONTCT.6 FEET. CAB . NAME . CURIE 1 SPEC . NO .DESCRPTION.P. FORM . FORM . CLASS. FEET . POUNDS,
- s ee m see .mossa .sosse,.sem en e.se em a_e.samese e essee , somosen.some ssee , memamenes s m.ne e sse , see...smes , ma sse.sesse e ,essamme. nee ssemameseee ,
801003 127 1500 15.00 3.00 0.30 CO 60 13.500 RUBBLE, C SOLID ELEM/0X LSA 320 43472 H 3 5.9505 REBARe 8 ALUM.
801003 128 1500 _30.00_ 3.00 0.07 _C0 60 4.220 RUBBLEe C SOLID ELEM/0X LSA 400 35496 H 3 1.8601 REBARe ALUM.
801006 129 1500 . _ _28.00 4.50 0.17 . CO 60 12.940 RUBBLEe C SOLID L.ELEM/0X LSA 496 43778 H 3 5.7037 R[ PAR. _ _ _ ,
8 ALUM.
801006 130 1500 17 00 _3.00 0.08 .-CO 60 11 110 RUBBLE, C SOLID .ELEM/0X LSA 512 41866 H 3 4.897 RE B AR-e 4 ALUM.
801007 131 1500 21 00 5.00 0.04 CO 60 11 400 RUBBLE, C SOLID ELEM/0X LSA 572 43302 H 3 5.0249 REBAR, 4 ALUM.
801000 132 1500 20.00 5.00 0.09 CO 60 13.500 RUBBLE, C SOLID' ELEM/0X LSA 560 43754 H 3 5.9505 .REBAR.
- ALUM.
801013 133 1500 30.00 5.00 0.08 CO 60 14.300 RUBBLE. C SOLID ELEM/0X LSA 496 43504 H 3 6.3031 REBARe
- ALUM.
801013 134 1500 5.00 0.60 0 12 CO 60 11.400 RUBBLEe C SOLID ELEM/0X LSA 496 42443 I H 3 5.0249 REBARe Ld 8 ALUM.
Cn 801014 135 1500 4.00 0.25 0.03 CD 60 0.240 RUBBLE, C SOLID ELEM/0X LSA 416 40260
' H 3 0.1058 RJ)_AR 801017 136 1500 0.30 0.09 - 0.03 CO 40 0.259 RUBBLEe C SOLID ELEM/0X LSA 512 42976
~ H 3 .. O.1142' REBAR 801020 137 1500 ~7.00 '~0.15' '0.03 CD'600.268 RUBBLE, C SOLID ELEN/0X LSA 544 44126 s H 3 0.1181 REBAR 801025 138 1500 3.50 0.40 0.03 CO 60 1.746 RUBBLE, C SOLID ELEM/0X LSA 576 44702 H 3 0.7696 REBARe
& ALUM.
801028 139 1500 15.00 1.00 .0.03 CO 60 0.271 RUBBLE, C SOLID- ELEM/0X LSA 528 44875 H 3 0.1195 REBAR 6 .
ALUM.
801030 140 1500 75.00 7.00 -'0.04 CO 60 1.591 RUBBLE, C SOLID 'ELEM/0X LSA 592 43420 H 3- 0.7013 REBAR, _ . . _
$ ALUM.
801031_141, ,1500 1.00 0.09 0.03 CO 60 NEG RUBBLEe C SOLID ELEM/0X LSA ~548 42066 H 3 NEG REBAR.
- ALUM.
801110 142 1500 '80.00 ~ 8.50'~ 0.20~ CO 40 1.891 RUBBLEe C SOLID ~ELEM/0X LSA 432 38482.
H 3 0.8335 ALUM.
801111 143 1500 32.00 7.00 0.13 CD 60 0.232 RUBBLEe C SOLID ELEM/bX LSA 560 37404____
H 3 0.1023 REBAR.
~ 4. ALUM.
801111 144 1500 '75.00~ ~ ~8.00~ - " ~0.14~- CO 60 0.559
~
RUBBLEeRE- C SOLID ELEM/0X LSA ; 424 40624 N 3 0.2464 BAR, ALUM.
9 ww twme e
. , , ~ ~ . . . ~ . - -
,- .- , -, - - . , w - - , ,,
7 FAGE NO. 1 . .. .
.ALRP-DECON U.N.C. DECOMMISSIONING DATA SYSTEM - DIEPOSAL COSTS- 74D1126 4
- SHIP . SHIP . .<----------- BURIAL CNARGES $ -------->.<----- TRANSPORTATION CHARGES $ ---->.<------- CONTAINER CHAR 0ES's ---- -->:
DISP'. .
. . SHIPPING . . NO . CONT . CONT .
4 DATE .NUM
. SITE . BASIC . CURIE .SP/HND.0THER . TOTAL . COMPANY .SASIC . PERMIT.0THER . TOTAL . CONTAINER TYP . CONT. COST . RENT 4.............................................................................................................E ......................
4- 780807 1 BARN 705.50 705.50 TRISTATE 2200 2200 SHIELDED DRUMS IN 12' 33 1860 4 CASK 780814 2 BARN 705.50 705.50 TRISTATE 2200 2700 SHIELDED DRUMS IN 12 33. 1860 t 4 CASK 780814 3 BARN 2028.3 2028.3 TRISTATE 2193.3 2193.3 DRUMS - 84' 231
, 780816 4 BARN 2000.0 2000.0 TRISTATE 2590.0 2590.0 CASK LINER 1 867.5 780821 5 BARN 2028.3 2028.3 TRISTATE 2193.3 2193.3 CONCRE1E-STEEL (19)
{ 780825 6 BARN 2028.3 2028.3 TRISTATE 2193.3 2193,3 CONCRETE-STEEL (21) 3 390 BOXES (3) 780906 7 BARN 2000.0 2000.0 TRISTATE' 2590.0 2590.0 CASK LINER- 't 867.5.
781211 8 BARN 2200.0 2200.0 TF1 STATE 2590.0 2590.0 DRUMS (31) BOXES (6) 37. 865.2 1 781218 9 BARN 2000.0 2000.0 1AISTATE 2590.0' 2590.0 DRUMS IN CASK 12 .33 2874.
i 7b0413 to BARN 3100.0 3100.0 TRISTATE- '3080.0 3080.0 BOXES 10 1300
< 790601 11 BARN 2500.0 2500.0 TRISTATE 2842.0 2842.0 CASK LINER 1 3158.
790605 12 BARN 4000.0 4000.0 TRISTATE 6100.0 6100.0 FOLY FILM i
7V0608 13 BARN 4000.0 4000.0 TRISTATE 6100.0 6100.0 POLY FILM 190710 14 BARN 2842.5 2842.5 TRISTATE 3711.0 - 3711.0 BOXES 9- 1170-l 790/23 lb BARN 2042.5 2842.5 TRISTATE 3711.0 3711.0 BOXES- ,
10 1300 190810 16 BARN 2500.0 2500.0 TRISTATE 2510.0 2510.0 CASK LINER 1 3158 190917 17 ALLH 3250.0 3250.0 TRISTATE 3842.0 3642.0 DRUMS (85) BOXES (7) 92 1144.
, 190921 18 BARN 2510.0 2510.0 TRISTATE 6510.0 3842.0 CASK LINER (2) 2 . 2468
}r y 800222 19 BARN 7427.0 7427.0. TRISTATE' 2071.0 2071.0 BOXES 9
1170
%q 800321 20 BARN 7427.0 7427.0 TRISTATE' 2070.0 2070.0 BOXES 9- 1870 e 8005v1 21 BARN 2040 6 2040.6 SUPERIOR 2807.0 2007.0 CASK LINER 1 800505 22 BARN 8666.0 8666.0 TRISTATE 2077.0 2077.0 BOXES (7) DRUMS (24). 41 1005.
. 800510 23 BARN 2040.6 2040.6. TRISTATE <2807.0 2007.0 CASK LINER . 1 .
0 800604 24 BARN - 8666.0 8666.0 TRISTATE 2077.0 2077.0 PACKAGES (9) DRUMS (10) 10 27.5 -
800707 25 BARN 2040.6 2040.6 Tk! STATE 2807.0 2007.0 CASK LINER 1 800716 26 BARN 2040.6 2040.6 TRISTATE 2807.0 2807.0 CASK LINER 1 800730 27 BARN 5744.0 5744.0 TRISTATE 2073.0 .2073.0 BOXES 4 520 800608 28 BARN 2040.6 2040.6 TRISTATE 2807.0 2007.0 CASK LINER 1 800923 29 RHO 3129.0 3129.0 TRISTATE 2731.0 2731.0 BOXES . 9 1170.
800973 30 RHO 3129.0 3129 0 TRISTATE 2732.0 2731.0 BOXESe TANKe SEALED 6 780.0 i 801003 31' RHO 2406.0 2406.0 TRISTATE 2686.0 '2686.0 CASK LINER 1 24614' 810119 32 RHG 3300.0 3300.0 TRISTATE' 2686.0 2686.0 DRUMS (36) BOXES (2) 38 359.0 810323 33 RHO 3724.0 3724.0 TRISTATE 2804.0 2004.0 BOXES to 1300.
810373 34 kHO 3724.0 3724.0 TRISTATE -2804.0 2004.0 BOXES 10 1300.
810323 35 RHO 3724.0 3724.0 TRISTATE 2004.0 2004.0 BOXES' 'to 1300.
810605 36 RHO - 680.0 680.0 . TRISTATE 2844.0 2844.0 LINER . 1 14305 810618 37 RHO 3018.0 3018.0 TRISTATE -2844.0 2844.0 DOXESe RESIN COLE 9 1170.
e . SEALED 810911 38 RHO ,3776.0 3776.0 TRISTATE 2820.0- 2820.0 BOXES (9) DRUMS (18) 27 1220.
810918 39 RHG 3290.0 3290.0 TRISTATE. 2820.0 2820. BOXES (5) DRUMS (24) 29 716.0 800818 NOTE - RHO 44300. 44300. 1.47E5 1.47E5 BOXES 418 54340
. NOTE- A TOTAL OF 44 SHIPMENTS. NO'S. 101 THRU 144
.++t++++++++++++++++++++++++++++++++++4+++++++++++++++++++++++++++++++t+++++++++
4 i
i l
.i 1
PAGE NO. 2
.ALMk-DECON U.N.C. DECOMMIS$10NING DATA SYSTEM - DISPOSAL COSTS 74DI!26
- . .<----------- BURIAL CHARGES 4 -------->.<----- TRANSPORTATION CHARGES $ ---->.<------- CONTAINER CHARGES 6 -------> '
4 SHIP . SHIP .DISF . . SHIPPING . . . NO . CONT . CONT .
8.DATE .NUM . SITE . BASIC . CURIE .SP/HND.0THER . TOTAL . COMPANY . BASIC .PER-IIT.0THER .TCTAL . CONTAIMER TYPE .CCHT.CDST . RENT .
s ......................................................................................a=== .......................................
. WASTE DISPOSAL COSTSS
. BURIAL EHARGES $169574
.* TRANSPORT CHARGES 259055
.0CCNIAINER COSTS 74047
.* CASK RENTAL 54832
. ST0TAL 6557508
.s WASTE DISPOSAL CHARGES FOR TWO MAJOR CONTRACTS WERE INCLUDED AS PART OF THE
. CONTRACT COST, AND f' .D NOT BE EXTRACTED FOR INCLUSION HERE.
t 00 00 I
c- .- . . . . .., , , . +.. c i
~ PAGE^bOI ~ I
.ALRR-DECOM U.N.C. DECOMMISSIONING DATA - SURVEILLANCE REPORT 74E1130
e .S. . .<------ ANNUAL --===>. .
. ..e .,_DEC0% ./.EXPENDITUR,. . nNAN _.MAM ._. .. COST a ' . ..
eVEAR. MODE .M. ITEM .FREQ. REM . HOURS . S . EXPENDITURE ITEM DESCRIPTION .
8 "
- i $ = ? ? it." e i= ? ? " *.* * "" ? ? " " 1" e. ? " * " ? m 1* * = * . " = ? "? ? * * " " = " m * = = = = = = " * * * = "" * = * * * = * = * * * * * * * = * *
. THE COST OF CURVEILLANCE ACTIVITIES REQUIRED SPECIFICALLY DECAUSE OF THE ,
. PAST EXISTANCE OF THE REACIOR IS ABSORDED IN THE COST OF OTHER SURVEILLANCE i .
ACTIVITIES REGUIRED DY THE_ CONTINUING UTILIZATION OF RADIDACTIVE MATERIALS j . IN LABORATORIES AT THE FACILIIY.
~
~~~$MAINTENANbfCOSTSARC~OKEklSt'hBSORDi~DT~SECURITYACTIVITIESINAREASWHICH ~
3
. WERE ORIGINALLY WERE REACTOR-ASSOCIATED ARE NO LONGER NECESSARY DECAUSE THOSE i
. AREAS ARE ROUIINELY SECURED FROM CASUAL ENTRY.
. - . , . . . . - - . - w. .$ .
e' W .
M W -
.~~. . . - - - - .7 _ ~. .
, . . . . . ,. m.. . .
4 w
W I . .
1 4
'k
.-...,m . .-. __. .~# . , -. ,. _
W'N~~
. - - . e .m..,,a i y.* o- .
i
. . . . - . _ , . _ _ . . _ . . . - . , . . . . . - . . ~ . - - .
e et+ +
k *-wwg er 9em .d. e N g er 4 . - - , . . ~ - . . . -,.,a.,,m.. ~~ .w ~
m_.
) __ ..
i 4
4 i
i
. . _ _ . - . . . . ~- e._
.ALER-DECON UNC DECOMMISSIONING DATA SYSTEM - PUBLIC DOSE REPORT F3012 __ ._,
s 8 . . . ..
go...seessessemesseneseeneseesesome===mesmessessmenesessee....messesseeeeeeeeeeeeee==sessemeeeeeeeeeeeeeeeeeeeee . ...............e AVAILABILITY CF APPROPRIATE DATA IS INSUFFICIENT FOR REPORT GENERATION.
--- .e=6 +9pquetde ma ee.g 4 pe w .smae mem-
- ~. __- , -
I
.Ch O
e
. - . _ _ . - _. . ..e_..-~.- _
-.__ -e.--_ .
ee, e eer+_- ee, e weg..,we. .m w ene de ephe,.emp-= e+ uur a w.m
-.ey .-a oam ne es- g.ye+* s&w . me ee *--- e W- e 4-+6 W amw - .,
.me w -. p my a ase.re ee-s.-me ..e
.Me m we.
e4 + e m em es_=W e
__.___________._m_ _m __
NRC roau 335 1. REPORT NUMBER (Ass,pedby DDCJ 37-773 U.S. NUCLEAR REGULATORY COMMISSION BIBUOGRAPHIC DATA SHEET NUREG/CR-3336
- 4. TlTLE AND SU8 TITLE (Add Vasume No., eraparcyrease) 2. (Leave b/m41 Evaluation of Nuclear Decommissioning Projects Sumary Report . 3. RECIPIENT'S ACCESSION NO.
Ames Laboratory Research Reactor
- 7. AUTHOR (S) 5. DATE REPORT COMPLETED MONTH l YEAR B. W. Link, R. L. Miller May 1983
- 8. PERFORMING ORGANIZATION NAM 6 AND MAILING ADORESS (Include Zep Coef DATE REPORT ISSUED UNC Nuclear Industries uONrn lvcAR Dzcommissioning Programs Department July 1983 P.O. Box 490 s. Itea e Nm*J Richland, WA 99352
- 8. (Leave Nmkl
- 12. SPONSORING ORGAN 32ATION NAME AND MAILING ADDRESS (include Zip Co*/
1 PROJECT / TASK / WORK UNIT NO.
i Division of Engineering Technology Office of Nuclear Regulatory Research 11. CONTRACT NO.
V. S. Nuclear Regulatory Commission Washington D.C. 20555 HRC FIN B7568
- 13. TYPE OF REPORT PE RICO COVE RED (/nclussve daresl Technical IS. SUPPLEMENTARY NOTES 14. (Leave o/m41
- 16. ABSTR ACT 000 words or tossl This document summarizes the available information concerning the decommissioning of the Ames Laboratory Research Reactor (ALRR), a five-megawatt heavy water moderated and cooled research reactor. The data were placed in a computerized information retrieval / manipulation system wirich permits its future utilization for purposes of comparative analysis. This information is presented both in detail in its computer output form and also as a manually assembled summarization which highlights the more important aspects of the decommissioning program. Some comparative information with reference to generic decommissioning data extracted from NUREG/CR 1756, " Technology, Safety and Costs of Decommissioning Nuclear Research and Test Reactors," is included.
i l
- 17. KEY WORDS AND DOCUMENT ANALYSIS 17a. DESCRIPTORS
- Decommissioning, Reactors,
! Research ALARA, Radiation Exposure l Cost, Comparison Studies l
l l
17tt IDENTIFIE RS/OPEN-EN DE D TERMS I
- 18. AVAILABILITY STATEMENT 19 ITY C S (TA,s report / 21 NO. OF PAGES Unlimited **(MUN[ded'"'"# S S
N;tC FORM 335 (7 77)
1 l
l 4
UNITED STATE 3 losQ",C',$7do 2-NUCLEAR REGULATORY COMMISSION usmac C, WASHINGTON, D.C. 20555 n n"uN".."h m' o
OFFICIAL BUSINESS O PENALTY FOR PRIVATE USE, $300 3,
l -
m r
C d
O z'
O ri .
2 C-0 120555078877 1 1AN11D F:
US NRC y ADM-DIV 0F TIOC m POL IC Y G PUB MGT BR-POR NUREG .,
W-501 y WASHINGTON DC 20555 , o F
R O
m O
.0, E
E a-m l 51 z
z c'
T i 21 O !,
c m'
O' in '
l u
C r
C3 co
. - - . .- - . - - _