ML20136A593
| ML20136A593 | |
| Person / Time | |
|---|---|
| Issue date: | 11/07/1985 |
| From: | Jamerson C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8511190561 | |
| Download: ML20136A593 (6) | |
Text
_ _ _. __._ _.
.N0TE T0:
File FROM:
Carole Jamerson Operating Reactors Branch No. 5 DL, NPR
SUBJECT:
HANDOUT ON LICENSED REACTOR DECOMMISSIONING REA MEETING The attached handout prepared by Peter B. Erickson of ORB #5 will be made available to participants at the Rural Electrification Administration (REA) meeting to be held at National Rural Electric Cooperation Association 4
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headquarters in Washington, D.C., on November 12, 1985. This material has been forwarded to the Document Control System for transmittal to the NRC PDR.
i odginal sWeed W Carole Jamerson Operating Reactors Branch No. 5 DL, NRR
Attachment:
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File FROM:
Carole Jamerson Operating Reactors Branch No. 5 DL, NPR
SUBJECT:
HAND 0UT ON LICENSED REACTOR DECOMMISSIONING REA MEETING The attached handout prepared by Peter B. Erickson of ORB #5 will be made available to participants at the Rural Electrification Administration (REA) meeting to be held at National Rural Electric Cooperation Association headquarters in Washington, D.C., on November 12, 1985. This material has s
been forwarded to the Document Control System for transmittal to the NRC PDR.
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Carole Jam on Operating Reactors Branch No. 5 DL, NRR
Attachment:
Handout on Decommissioning I
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LICENSED REACTOR DECOMMISSIONING REA MEETING NOVEMBER 12, 1985 P. B. ERICKSON, U.S. NRC Introduction Decomissioning as defined by the NRC means to remove a facility from service and reduce _ residual radioactivity to a level that permits release of the property for unrestricted use and termination of the license.
Three areas of interest Jn reactor decommissioning are presented in this paper: First, the pres'ent and the proposed NRC regulations and guides on y
decomissioning; Second, the impact of the Nuclear Waste Policy Act of 1982 R
and; Third, NRC experience in decournissioning licensed power reactors.
Present and Proposed Regulations and Guides The requiremer.th for authorization to dismantle a reactor facility and terminate a reector license are specified in 10 CFR 50.82. Other sections of NRC regulations-are also applicable during the decomissioning process such as 10 CFR Part 20, Standards for Protection Against Radiation and 10 CFR 50.90, Application for Amendient of License or Construction Pennit.
If
. spent fuel remains on site,10 CFR Part 70 on Special Nuclear Material and Part 73, Physical Protection of Plants and Materials are applicable.
10 CFR Part 51, Environmental Protection Regulations is applicable and requires an environmental impact statement for the decomissioning of a power reactor.
Regulatory Guide 1.86, "Tennination of Operating Licenses foc' Nuclear Reactors," enclosed, was specifically written for reactor decunmissioning.
This guide presents alternative methods acceptable for decomissioning, requirements for each alternative and the residual radioactivity requirements for terminating a license.
The regulations and guides for reactor decomissioning are being fevised.-
A proposed rule change dated February 11, 1985 would revise requirements with respect to decomissioning of reactors and other facilities.,-The significant changes with respect to reactors are the requirem'ents for funding plans,'for furiding assurance and for decomissioning plans.
As pr5 posed, an electric utility may submit'either a decomissioning funding plan or a certification that financial assurance for decommissioning will be provided in an amount at least equal to
$100,000,000 (1984 dollars). Financial assurance may be provided by, a variety of methods including internal reserve.
Three decomissioning' alternatives are defined in the February 11, 1985 proposed rule changes. These are DECON, SAFSTOR and ENTOMB.
DECON is an alternative in which all equipment, structures and portions of a facility and site containing radioactive contaminants.
l are removed or decontaminated to a level acceptable foF release to unrestricted use within a few years of termination of reactor -
l operations.
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, l SAFSTOR is an alternative in which a facility is placed and l
' maintained in such condition that it can be safely stored and subsequently decontaminated to levels that permit unrestricted use.
ENTOMB is.an alternative in which radioactive contaminants are encased in a structurally long-lived material, such as concrete. The entombed structure is appropriately maintained and surveillance is continued until the radioactivity decays to a level permitting Anrestricted use. This alternative would be allowable for facilities contaminated sith relatively short-lived radionuclides such that all contaminants would decay to levels permissible for unrestricted use within a period of about 100 years.
Very long-lived radionuclides in reactor vessels.such as niobium-94 and nickel-59 would make this alternative very unlikely for most power reactors.
Regulatory Guide 1.86, "Temination of Operating Licenses for Nuclear Reactors," is being revised to reflect the aforementioned terminology and requirements of the proposed rule change. This revised guide is not expected to be a significant change from the present guidance.
A second regulatory guide titled " Assuring the Availability of Funds for Decomissioning Nuclear Reactors" is being developed in conjunction with the proposed tule.
Its purpose is to provide guidance on methods for complying,with the requirements in the rule for submitting cost estimates for decommissioning.
It will also provide guidance on the form and content of acceptable funding methods.
A third guide, " Format and Content for Nuclear Reactor Decommissioning Plans",
identifies the information needed by the NRC for review and presents a fomat for a licensee's decommissioning plan.
?
The final rule changes on decommissioning are not scheduled to be issued until October-1987 due to the many coments received on the proposed changes. The regulatory guides presented above are expected to be published for comment in about 6 months.
Nuclear Wste Policy Act of 1982 The Nuclear Waite Policy Act of 1982 (Public Law 97-425, January 7,1983) established a framework for the disposal of high-level radioactive waste including spent nuclear fuel.
The Act provides for a high level waste repository to be built and operating by 1998.
It also established a program for the interim storage of a limited amount of spent nuclear fuel at DOE sites while 'the repository for ultimate disposal is selected and developed. The Act stated, however, that the primary responsibility for providing interim storage rests with the reactor licensee. The Act further provides that the interim storage would be available to a licensee only if:,1) the licensee cannot reasonably provide adequate spent fuel storage capacity at the reactor site or at another of the licensee's reactors; 2) the i
additionil capacity _ is needed to ensure continued orderly operation of the reactor ard; 3) the licensee is diligently pursuing alternatives to the use of'the Federal interim storage.
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. x The Waste Policy Act, therefore, dictates that fuel storage will continue at a permanently shutdown reactor facility until the Federal repository is ready to receive it. The net result of this condition is that nuclear power reactors will not likely be imediately decontaminated, i.e., the DECON alternative, when they are permanently shutdown because the fuel must l
remain on site until there is a permanent repository available.
Experience in Licensed Power Reactor Decommissioning About 50 licensed research reactors and critical facilities have been decontaminated and their licenses teminated, DECON, and 6 test reactors have been placed in safe storage, SAFSTOR. Also, three Demonstration power plants, Bonus, Piqua and Hallam have been entombed, ENT0MB and one Demonstration power plant, Elk River has been decontaminated, DECON. No licensed power reactors have been decontaminated to the point that the license could be terminated. Eight licensed power reactors have been pemanently shutdown, however, and have been or will be placed in some form of safe storage, SAFSTOR. Two of these plants, the CVTR, and Pathfinder, are now licensed under byproduct materials licenses with the State of South Carolina and the NRC, respectively. The remaining six power reactors which retain reactor licenses are addressed below.
Present NRC policy and the proposed new rules on decommissioning do not provide for the transfer of a reactor facility to byproduct license status. A possession-only reactor facility license would remain in effect during a SAFSTOR period.
Humboldt Bay Power Plant Unit No. 3 The Humboldt Bay Plant, Unit 3 is a 220 MW themal, boiling water reactor that has been shut down since 1976. Units 1 and 2 on the Humboldt Plant site are gas and oil fired. A decomissioning plan and environmental report have been submitted to the NRC.
PG&E, the licensee, has selected the SAFSTOR option for decomissioning. The licensee plans to retain the plant in the safe storage status for about 30 years after which time the facility would be decontaminated and the license terminated. The 30-year SAFSTOR period requires a 15 year extension to the present license.
Irradiated fuel will remain in the spent fuel storage pool until a Federal repository is ready for its receipt. DOE interim spent fuel storage cannot be used for temporary storage of Humboldt fuel because: 1) there is available storage onsite and 2) the facility is shut down already; therefore, the need "for i s
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continued orderly operation of the reactor" is not a factor.
N Indian Point Unit No. 1 Indian Point Unit 1 is a 615 MW thermal, r w wi d water reactor that has been shut down since 1974. sConsolidated Jcf uA de licensee, has submitted a decommissioning plan that' involves safe storage (SAFSTOR) until Unit 2 is permanently shut down, after which time Unit I would be decontaminated.
Spent fuel will remain in the spent fuel storage pool at Unit No. 1 until the Federal -repository is available.
Dresden Unit No. 1 Dresden Unit 1 is a 700 MW thermal, boiling water reactor that has been shut'down since 1978. The licensee, Commonwealth Edison, intends to select the SAFSTOR option for decomissioning.
Dresden Unit I will remain in a
safe storage status until after Units 2 and 3 are shut down. All of Unit I fuel will remain onsite until a Federal repository is available. We expect the licensee to submit a decommissioning plan in 1986.
Peach Bottom Unit No. 1 Peach Bottom Unit No. 1 is a 115 MW thermal, high temperature gas coolded reactor that has been shut down since 1974.
Peach Bottom Unit 1 is in SAFSTOR status now. All fuel has been removed from the site and shipped to DOE facilities in Idaho. All liquids and pressurized gases such as the helium primary coolant have been removed from the facility and the primary coolant system sealed. The radioactive waste processing system and several contaminated cooling systems have been removed from the site and shipped to low level radioactive waste burial sites. Accessible surfaces have been decontaminated. A chain link fence has been installed around the containment and spent fuel building to establish the exclusion area. The containment building and spent fuel building also have access control through the use of locked doors. Security for the site is maintained by the security force used for Peach Bottom Units 2 and 3.
Femi Unit No.1 Fermi Unit No.1 is a 200 MW thermal, sodium cooled, fast breeder reactor that has been shut down since 1973. Detroit Edison, the licensee, intends to retain Fermi Unit 1 in a safe storage (SAFSTOR) status until after Fermi Unit 2 is shut down at which time residual radioactivity would be removed.
In early 1985 Detroit Edison applied for a 40-year extension to the Fermi Unit 1 possession-only license to accomodate this SAFSTOR period. All fuel has been removed from the site as well as the natural uranium blanket assemblies.
The fuel was sent to the AEC Savannah River Plant for reprocessing and the blanket material sent to the AEC Idaho site.
The secondary sodium was free of radioactivity.
It was barreled in 55 gallon drums and sold comercially.
The primary sodium, which was slightly radioactive, was retained on site.
A contract was established with the AEC/ DOE to accept this sodium in 6 to 10 years for use in its sodium cooled reactor programs.
In 1984 this primary sodium was barreled and shipped to the DOE Idaho site.
Vallecitos Boiling Water Reactor The Vallecitos Boiling Water Reactor (VBWR) which operated at 50 MW thermal was shut down in 1963 and placed in a safe storage (SAFSTOR) status. All fuel has been removed from the site, the accessible areas decontaminated and access to the facility controlled through the use of locked doors and security guards.
Conclusions In the past the AEC/D0E has accepted spent fuel from licensed power reactors for storage and reprocessing when the facility was decommissioned. DOE continues to accept spent fuel from research and test reactors. The Waste Policy Act of 1982 removes that option, however, for power reactor decomissioning. Storage of spent fuel on site until a Federal repository is ready for pemanent disposal must, therefore, be considered by utilities that plan to decommission power reactors before the year 1998.
For single unit plants, where security and maintenance costs cannot be shared with operating units, the storage of fuel on site for a long term could be a significant cost.
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June 1974 U.S. ATOMIC ENERGY COMMISSION t REGU.LATORY GU DE o
DIRECTORATE OF REGULATORY STANDARDS
,%:s o' REGULATORY GUIDE 1.86 TERMINATION OF OPERATING LICENSES FOR NUCLEAR REACTORS A. INTRODUCTION A licensee having a possessionenly license must retain, with the Part 50 license, authorization for special Section 50.51, " Duration of license, renewal," of 10 nuclear material (10 CFR Part 70, "Special Nuclear CFR Part 50, " Licensing of Production and Utilization Material"), byproduct material (10 CFR Part 30," Rules Facilities," requires that each license to operate a of General Applicability to Licensing of Byproduct production and utilization facility be issued for a Material"), and source material (10 CFR Part 40, specified duration. Upon expiration of the specified
" Licensing of Source Material"), until the fuel, radio-period, the license may be either renewed or terminated active components, and sources ne removed from the by the Commission. Section 50.82, " Applications for facility. Appropriate administrative controls and facility termination oflicenses," specifies the requirements that requirements are imposed by the Part 50 license and the must be satisfied to terminate an operating license, technical specifications to assure that proper surveillance including the requirement that the dismantlement of the is performed and that the reactor facility is maintained facility and disposal of the component parts not be in a safe condition and not operated.
inimical to the common defense and security or to the health and safety of the public. This guide describes A possession-only license permits various options and methods and procedures considered acceptable by the procedures for decomnussioning, such as mothballing, O
Regulatory staff for the termination of operating entombment, or dismantling. The requirements imposed licenses for nuclear reactors. The Advisory Committee depend on the option selected.
on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
Section 50.82 provides that the licensee may dis-mantle and dispose of the component parts of a nuclear B. DISCUSSION reactor in accordance with existing regulations. For research reactors and critical facilities, this has usually When a licensee decides to terminate his nuclear meant the disassembly of a reactor and its shipment reactor operating license, he may, as a first step in the offsite, sometimes to another appropriately licensed process, request that his operating license be amended to organization for further use. The site from which a restrict him to possess but not operate the facility. The reactor has been removed must be decontaminated, as advantage to the licensee of converting to such a necessary, and inspected by the Commission to deter.
possessionenly license is reduced surveillance require-mine whether unrestricted access can be approved. In ments in that periodic surveillance of equipment im-the case of nuclear power reactors, dismantling has 3
portant to the safety of reactor operation is no longer usually been accomplished by shipping fuel offsite, required. Once this possessionenly license is issued, making the reactor inoperable, and disposing of some of reactor operation is not permitted. Other activities the radioactive components.
related to cessation of operations such as unloading fuel from the reactor and placing it in storage (either onsite Radioactive components may be either shipped off-of offsite) may be continued.
site for burial at an authorized burial ground or secured USAEC REGUt.ATORY GUIDES c
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on the site. Those radioactive materials remaining on the fluids and waste should be removed from the site.
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site must be isolated from the public by physical barriers Adequate radiation monitoring, environmental surveil.
or other means to prevent public access to hazardous lance, and appropriate security procedures should be levels of radiation. Surveillance is necessary to assure the established under a possession only license to ensure that long term integrity of the barriers. The amount of the health and safety of the public is not endangered.
surveillance required depends upon (1) the potential hazard to the health and safety of the public from
- b. In Place Eatombment. In-place entombment con.
radioactive material remaming on the site and (2) the sists of sealing all the remaining highly radioactive or integrity of the physical barriers. Before areas may be contaminated components (e.g., the pressure vessel and released for unrestricted use, they must have been reactor internals) within a structure integral with the decontaminated or the radioactivity must have decayed biological shield after having all fuel asemblies, radio.
to less than prescribed limits (Table !).
active fluids and wastes, and certain selected com.
ponents shipped offsite. The structure should provide The hazard asociated with the retired facility is integrity over the period of time in which significant evaluated by considering the amount and type of quantities (greater than Table I levels) of radioactivity remaining contamination, the degree of confinement of remain with the material in the entombment. An the remaming radioactive materials, the physical security appropriate and continuing surveillance program should provided by the confinement, the susceptibility to be established under a possession only license, release of radiation as a result of natural phenomena, and the duration of required surveillance.
- c. Removal of Radioactive Componesta and Dis-j mantling, All fuel assernblies, radioactive fluids and C. REGULATORY POSITION waste, and other materials having activities above ac-cepted unrestricted activity levels (Table I) should be
- 1. APPUCATION FOR A LICENSE TO POSSESS BUT removed from the site.The facility owner may then have i
NOT OPERATE (POSSESSION ONLY UCENSE) unrestricted use of the site with no requirement for a license. If the facility owner so desires, the remainder of A request to amend an operating license to a the reactor facility may be dismantled and all vestiges possession.only license should be made to the Director removed and disposed of.
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of Licensing, U.S. Atomic Energy Comnussion, Washing.
ton, D.C. 20545. The request should include the
- d. Conversion to a New Nuclear System or a Fossil following information:
Fuel System. This alternative, which applies only to
-5 nuclear power plants, utilizes the existing turbine system
- a. A description of the current status of the facility.
with a new steam supply system. The original nuclear steam supply system should be separated from the
- b. A descriptior of measures that will be taken to electric generating system and disposed ofin accordance prevent criticality or reactivity changes and to minimize with one of the previous three retirement alternatives.
I releases of radioactivity from the facility.
- 3. SURVEILLANCE AND SECURITY FOR THE RE.
- c. Any proposed changes to the technical specifica-TIREMENT ALTERNATIVES WHOSE FINAL tions that reflect the possession-only facility status and STATUS REQUIRES A POSSESSION ONLY the necessary disassembly / retirement activities to be LICENSE performed.
A facility which has been licensed under a posses.
- d. A safety analysis of both the activities to be sion.only license may contain a significant' amount of accomplished and the proposed changes to the technical radioactivity in the form of activated and contaminated specifications.
hardware and structural materials. Surveillance and commensurate security should be provided to assure that
- e. An inventory of activated materials and their the public health and safety are not endangered.
location in the facility, f
- a. Physical security to prevent inadvertent exposure
- 2. ALTERNATIVES FOR REACTOR RETIREMENT of personnel should be provided by multiple locked barriers. The presence of these baniers should make it Four alternatives for retirement of nuclear reactor extremely difficult for an unauthorized person to gain facilities are considered acceptable by the Regulatory access to areas where radiation or contamination levels staff. These are:
exceed those specified in Regulatory Position C.4. To prevent inadvertent exposure, radiation areas above 5
- a. Mothballing Mothballing of a nucleu reactor mR/hr, such as near the activated primary system of a facility consists of putting the facility in a state of power plant, should be appropriately marked and should protective storage. In general, the facility may be left not be accessible except by cutting of welded closures or intact except that all fuel assemblies and the radioactive the disassembly and removal of substantial structures 1.86-2
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l and/or shielding material. Means such as a remote-(1) Environmentalsurveys, readout intrusion alarm system should be provided to I
i{g-s indicate to designated personnel when a physicalbarrier (2) Facility radiation surveys, L,.
is penetrated. Security personnel that provide access control to the facility may be used instead of the (3) Inspections of the physical barriers, and physical barriers and the intrusion alarm systems.
(4) Abnormaloccurrences.
- b. The physical barriers to unauthorized entrance into the facility, e.g., fences, buildings, welded doors, and access openings, should be inspected at least
- 4. DECONTAMINATION FOR RELEASE FOR UN-quarterly to assure that these barriers have not deterior-RESTRICTED USE ated and that locks and locking apparatus are intact.
If it is desired to termir. ate a license and to eliminate
- c. A facility radiation survey should be performed at any further surveillance requirements, the facility should least quarterly to verify that no radioactive materialis be sufficiently decontaminated to prevent risk to the escaping or being transported through the contamment public health and safety. After the decontamination is barriers in the facility. Sampling should be done along satisfactorily accomplished and the site inspected by the most probable ph by which radioactive material the Commission, the Comrmssion may authorize the such as that stored in the inner containment regions lianse to be terminated and the facility abandoned or could be transported to the outer regions of the facility released for unrestricted use. The licensee should per.
and ultimately to the environs.
form the decontamination using the following guide-l lines:
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- d. An environmental radiation survey should be performed at least semiannually to verify that no
- a. The licensee should make a reasonable effort to signficant amounts of radiation have been released to the eliminate residual contamination.
environment frora the facilhy. Samples such as soil, vegetation, and water should be taken at locations for
- b. No covering should be applied to radioactive which statistical data has been established during reactor surfaces of equipment or structures by paint, plating, or operations.
other covering material untilit is known that contamina-tion levels (determined by a survey and documented) are O
resp. A site representative should be designated to be e
below the limits specified in Table 1. In addition, a onsible for controlling authorized access into and reasonable effort should be made (and documented) to movement within the facility.
further minimize contamination prior to any such covering.
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- f. Administrative procedures should be established for the notification and reporting of abnormal occur-
- c. The radioactivity of the interior surfaces of pipes, rences such as (1) the entrance of an unauthorized drain lines, or ductwork should be determined by person or persons into the facility and (2) a significant making measurements at all traps and other appropriate change in the radiation or contamination levels in the access points, provided contamination at these locations facility or the offsite environment.
is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork. Surfaces
- g. The following reports should be made:
of premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or (1) An annual report to the Director of Licensing, location as to make the surface inaccessible for purposes U.S. Atomic Energy Commission, Washington, D.C.
of measurement should be assumed to be contaminated 20545, describing the results of the environmental and in excess of the permissable radiation limits, facility radiation surveys, the status of the facility, and an evaluation of the performance of security and
- d. Upon request, the Commission may authorize a surveillance measures.
licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated in (2) An abnormal occurrence report to the Regula-excess of the liaits specified. This may include, but is tory Operations Regional Office by telephone within 24 not limited to, special circumstances such as the transfer hours of discovery of an abnormal occurrence. The of promises to another licensed organization that will abnormal occurrence will also be reported in the annual continue to work with radioactive materials. Requests report described in the precedingitem.
for such authorization should provide:
- h. Records or logs relative to the following items (1) Detailed, specific information describing the should be kept and retained until the license is termi-premises, equipment, scrap, and radioactive contami-nated, after widch they may be stored with other plant nants and the nature, extent,' and degree of residual records:
surface contamination.
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j (2) A detailed health and safety analysis indi-or a change in the technical specifications should be cating that the residual amounts of materials on surface reviewed and approved in accordance with the require-areas, together with other considerations such as the ments of 10 CFR g50.59.
I prospective use of the premises, equipment,or scrap,are unlikely to result in an unreasonable risk to the health if major structural changes to radioactive components and safety of the public.
of the facility are planned, such as removal of the pressure vessel or major components of the primary
)
- e. Prior to release of the premises for unrestricted system, a dismantlement plan including the information 5
use, the licensee'should make a comprehensive radiation required by {50.82 should be submitted to the Commis.
survey establishing that contamination is within the sion. A dismantlement plan should be submitted for all limits specified in Table 1. A survey report should be the alternatives of Regulatory Position C.2 except filed with the Director of Licensing, U.S. Atornic Energy mothballing. However, minor disassembly activities may Commusion, Washington, D.C. 20545, with a copy to still be performed in the absence of such a plan, the Director of the Regulatory Operations Regional provided they are permitted by existing operating and Office having jurisdiction. The report should be filed at maintenance procedures. A dismantlement plan should least 30 days prior to the planned date of abandonment.
include the following:
The survey report should:
- a. A description of the ultimate status of the facility (1) Identify the premises;
- b. A description of the dismantling activities and the (2) Show that reasonable effort has been made to precautions to be taken.
reduce residual contamination to as low as practicable levels;
- c. A safety analysis of the dismantling activities including any effluents which may be released.
(3) Describe the scope of the survey and the general procedures followed;and d.-A safety analysis of the facility in its ultimate status.
(4) State the finding of the survey in units specified in Table 1.
Upon satisfactory review and approval of the dis-mantling plan, a dismantling order is issued by the After review of the report, the Commission may Commission in accordance with Q50.82. When dis-J inspect the facilities to confirm the survey prior to mantling is completed and the Commission has been granting approval for abandonment.
notified by letter, the appropriate Regulatory Opera.
tions Regional Office inspects the facility and verifies
- 5. REACTOR RETIREMENT PROCEDURES completion in accordance with the dismantlement plan.
If residual radiation levels do not exceed the values in As indicated in Regulatory Position C.2, several Table I, the Commission may terminate the license. If altematives are acceptable for reactor facility retirement.
these levels are exceeded, the licensee retains the If minor disassembly or "mothballing" is planned, this possession only license under which the dismantling could be done by the existing operating and mainte-activities have been conducted or, as an alternative, may nance procedures under the license in effect. Any make application to the State (if an Agreement State) planned actions involving an unreviewed safety question for a byproduct materials license.
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1.86-4 I
8 s
TABLEI ACCEPTABLE SURFACE CONTAMINATION LEVEL.S NUCLIDEa AVERAGE c MAXIMUMbd REMOVABLE e b
b 2
2 U-nat, U-235, U-238, and 5,000 dpm a/100 cm 15,000 dpm a/100 cm 1,000 dpm a/100 cm2 associated decay products 2
20 dpm/l00 cm2 Transuranics, Ra-226, Ra-228, 100 dpm/100 cm2 300 dpm/100 cm Th-230, Th 228, Pa-231, Ac 227,I 125,I 129 2
2 2
3000 dpm/100 cm 200 dpm/100 cm Th-nat, Th-232, Sr-90, 1000 dpm/100 cm Ra 223, Ra-224, U-232, I126,I131,I133 2
2 2
Beta-gamma emitters (nuclides.
5000 dpmiky/100 cm 15,000 dpm h/100 cm 1000 dpm /Py/100 cm with decay modes other than alpha emission or spontaneous fission) except Sr-90 ano others noted above.
aWhere surface contamination by both alpha-and beta-gamma <mitting nuchdes exists, the limits establahed for alpha-and betagmma-emitting nuclides should apply independently.
bAs used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors assocuted with the instrumentation-cMeasurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.
G--v.
d 2
The maximum contamination level apphes to an area of not more than 100 cm,
2
'The amount of removable radioactive material per 100 cm of surface area should be determiried by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
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