ML19310A404
| ML19310A404 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 03/15/1980 |
| From: | North Carolina State University, RALEIGH, NC |
| To: | |
| Shared Package | |
| ML19310A403 | List: |
| References | |
| NUDOCS 8006170482 | |
| Download: ML19310A404 (24) | |
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. DISMANTLING PIAN FOR THE
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R-3, 10 $ REACTOR '
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NRC License No. R-63 ' Docket 50-111
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Nuclear Reactor Progra:n . , i Department of Nuclear Engineering North Carolina State University at Raleigh Raleigh, North Carolina 27650 Date: 15 March 1980
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FOREWORD .
- In July,1976, a " Dismantling Plan, North Carolina State Univer-sity,10 Kilowatt Research Reactor" was prepared, reviewed by the NCSU Radiation Protection Coancil, and submitted to the Nuclear $legulatory .
Commission. This Plan was prepared to accommodate a specified ' objective. , Having a totally different objective to achieve, the following
" Dismantling Plan for the R 3 10 E Reactor" hac been prepared. The
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above cited plan was reviewed and pertinent parts incorporated. New . thoughts and ideas have been included to the point there is little, if any, similiarity between these plans, and the July,1976, submittal should be disregarded.
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The reactor to be dismantled and decontaminated is the 10 IGT re-search reactor at North Carolina State University known as the "R-3" - the third reactor on campus. The license for this reactor is NRC R-63
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TABLE OF CONIEFIS . Page
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FOREWORD . . . .. ...............- i
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FIGUBES ..... . .............. iii REVISIONS . ... ............... iv Introduction . . . . . . . , . . . . . . . . . . 1 Applicable Criteria .............. 1 Description History of the NCSUR-3 Reactor . . . 2
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Current Site. Status. . . s ......... . .. 7 Table I - Operating History .......... 8 Dismantling Operation .._......... . . 11 Safety Aspects of the Dismantling Operation . . 12 Description of the Facility After Dismantling . 13 NCSU Radiological Protection Office (RPO) . . . 114 Attachment 1: f - Task I - Control Room ........... 16 Task II - Pipe Pit . . . . . . . . . . . . . 17 Task III - External Piping to Shield . . . . 17 Task IV - Remove Pool Tank . . . . . , . . . 19 Task V - Graphite and Lead Bricks . . . . . 19 e Task VI - Decontaminated Biological Shield . 19 Task VII - R-3 Bay . . .......... . . 19 Task VIII - Final Radiation Survey . . . . . 19
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FIGURES -
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D* ; Figure 1, Raleigh Training Reactor . . . . . . -3 Figure 2, BEL Complex .....
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! Figure 3, Reactor Building Layou' Main
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.....,...... 5 Figure 4, Schematic Diagram of Reactor Coolant System .......... 6 l
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Figure 5, NCSUR-3 Operating History ..... 9 Figure 6, Frimary Cooling System . ; . . . . . 18
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REVISIONS
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Number Description Date
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- DISMANTLING PIAN FOR THE R-3, 10 KW REACTOR
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INTRODUCTION The objective of this document is to provide a plan for the disas-sembly of the North Carolina State University (NCSU) 10 kilowatt research
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reactor and for the ultimate disposal of unusable components, both contami-nated and non-contaminated. The successful dismantling and decommissioning of this reactor will be a prelude to a request for the termination of the NRC Reactor License R 63 APPLICABLE CRITERIA .
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NCSU shall use as criteiia for determining the success of this dis-mantling-decommission effort the following documents: o NRC Regulatory Guide 1.86, " Termination of Operating Licenses
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for Nuclear Reactors." .
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o NCSU Handbook for Protection Against Ionizing Radiation, Fifth Edition, 1978. At the Conference on Decontamination and Decommissioning of Nuclear Facilities, September 16-19, 1979, Sun Vaney, Idaho, it was apparent that
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other than the above documents there was very little acceptable experience
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data available on which to base criteria for the release of a research re-e actor site to unrestricted use. However, it will be the policy of the Uni-versity to reduce the radiological hazard associated with the R-3 reactor site to as low as reasonably achieveable (AIARA). Toward this objective, all , information received, official or private, will be evaluated and, if appli-
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cable, used. An individual in the NRC, Directorate for Operating Reactor Projects, has suggested that the residual radiation from any surface needs to be less than .05 mrem /hr before the item can be released for unrestricted use.
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This suggestion is consistent with 10CFR 20.105. l l
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Therefore, the resulting radiation level from any surface'in the R-3 reactor site shall be -less than 0.05 mrem /hr. , or less than the requirements
-of the above referenced documents, whichever results in the least hazard to l
the general public. , s . DESCRIPTION HISTORY OF THE NCSUR-3 REACTOR
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The NCSUR-3 Reactor is a 10 kilowatt graphite reflected tank-type re-actor using 18_ plate MER-type fuel elements. The core lattice is a 5 x 5 array of fuel (21) and graphite (4) elements. Figure 1 provides a drawing of the reactor facility. Figure 2 shows the relationship of the R-3 reactor to
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the Burlington Engineering Laboratories'.compler; Pigure 3 shows.the R-3 reactor and the adjacent offices and laboratories in the original building which was known as the "Burlington Nuclear Laboratory." Figure 4 shows the Reactor Coolant System. Attachment 1 provides a listing of Reactor Components,
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by suggested " tasks". '
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The NCSUR-3 Reactor was operated from 1960 to 1973, at which time the
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NRC %erating License was terminated and a license to " possess but not operate" was issued. In 1973, the reactor core was unloaded, the fuel placed in storage 1 racks within the reactor tank, the control rods removed to storage, and the l l' electrical controls were disconnected to prevent further operation. In Febru-ary,1974, the fuel was removed from water storage, examined, and placed in . 1
, dry storage. The reactor system was. drained completely at this time. The '
beam ports and thermal column were closed and each locked by its own three
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combination safe-type lock. The top of the reactor tank was covered by a
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two inch thick steel plate. The electrical circuit breaker. box containing
.the breaker for the overhead crane was locked. Thus, the amendment to our R-63 license "to possess but not operate" had been fulfilled. ,
A total of 52.5 megawatt hours of' operations were perfoimed over the
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, FIGURE 1 - Raleigh Training Reactor .
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License R-63
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License R-120
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A - NCSU R-3 Reactor , C - NCSU iUISTAR Reactor
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B - R-3 Bay , D - PUISTAR Bay
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E - FUISTAR Control Room, 2nd Floor
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F - FUISTAR Mechanical Equipment .
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C, D, E, F - PUISTAR Reactor Bldg.
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FIGURE 2 - BEL Complex .
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FIGURE 3
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REACTOR BillLDING LAYOUT ! u
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DISMANTLED ' s /n IN 1974 r-9 IC00 LING l
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pper; ting period cf th2 reacter. Tdblo~1 and Figure 5 provids data on ths fear-by-year operating history. The NCSUR-3 Reactor operations were termi-nated after the completion of the new 1 megawatt PUISTAR research reactor
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in 17[2. This new facility provided a11' reactor services. required at NCSU,
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and it was not economically feasible to continue operation of,the R-3 reactor.
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CURRENT SITE STATUS
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The NCSUR-3 facility is being maintained in a shutdown status with those radiation detection systems (area and radiation monitors) specified in Amendment No. 6 to the R-63 license ke,t in an operational status. A license modification to remove these detection systems and periodic surveillance from
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the license has been requested. .However, the status _ quo shall be maintained until fonnal relief is received. The R-3 irradiated fuel assemblies have been shipped to SR00, Aiken, S. C., and the unused (4) fuel assemblies have been moved to the RTLSTAR Bay for dry storage. The reactor electrical controls are disconnected. The re-actor coolant systems are dry, having been drained in February,17/4.
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Daily (working day) high volume air sampling and weekly contamination
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surveys have been conducted since February, 1973. Neither of these actions , have evidenced any radioactivity in the R-3 Bay. A Victoreen Area Monitor Portable, set to 41 arm at 1 mR/hr. , has been on the R-3 shield or over the
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Gamma Facility for over seven years. This instrument continuously reads in , orderof0.1'mR/hr.orless. , l On the basis of the preceding paragraph, there is a good indication that ~
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any radiation, contamination or airborne hazar.d in the R-3 Bay has been and is very low. ,. .
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i In June, 1978, the radiation level in the nose grid of the R-3 core was ; l
. measured by TLD chips, pocket dosimeters and a 2 5 R chamber 'of a Condenser '
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'R-meter. The location of each and the results of a two-hour exposure are given
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TABIE 1 - OPERAT1NG HISTORY N. C. STATE 10 KIIN ATT REACTOR - PERIOD ENERGY (Megawatt Hours)
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1966 2.65 1967 5.0 1968 5.4 1969 4.2 1970 ,
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8.6 l l 1971 5.3 i
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. Total 52.54 i -
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'61 .' 62 ' 63 ' 64 ' 65 ' 66 ' 67 ' 68 ' 69 ' 70 ' 71
- 72 ' 73 OPERATING YEAR
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I NCSUR 3 OPERATING HISTORY FIGURE 5
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. below:
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#5 #3 3 G - Graphite Stringers -
g R - 2.5R Chambei- - D D - Pocket Dosimeters
#2 #4 D D 1, 2, etc.'- Pairs of TLD Chips G G l l
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a mrem Pocket 2.5R ; l Position TID Dosimeter- Chamber l- l N 100 - 101 E 106 109 -
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Exposure Time - 2 Hours In June, 1976, a radiation measurement and swipes were taken in ' several beam ports. For the radiation measurement, a thin wall GM was at-
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tached to a board that was inserted into tt bean. ports to a point close ,
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to the core reflector. In a similar manner, the swipes were taken. The r-largestdose.atefoundwas20mR/hrandtheswiperesultswerelessthan j 120 dpm. The R-3 react r had been operated for a total of 52.54 megawatt-hour
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over its lifa span (cee Figure.5 and Table 1).
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.: The components cf the R-3 reactor in which the greatest amount of
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activation products are expected to be found are: Core Grid, bottom section of the reactor tank, and in the concrete under the reactor core. These c^m-ponents. each, may contain up to 100 mci of activation products. This esti-mate is consistent with that experienced in the dismantling of the 11TRI 75 Kw - Research Reactor and the 50 Kw Walter Reed hesearch Reactor. (Note: The fuel has been returned to DOE.)- -. - TheactivationproductsintheCoreGridandthereachortankwillbe removed fron the biological shield and will be a factor in their disposal.
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The amount of activity in the concrete under_the core will be determined prior to any decontamination of the biological shield. DISMANTLING OPERATION The dismantling operation as described in this plan will be supervised by the Nuclear Reactor Program (NRP). The principle concerns will be:
- a. Personnel safety, both radiological and industrial.
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- b. The identification and separation of conteminated and non-contaminated items.
- c. The proper disposal of both classes of items (see b. above)
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and compliance with pertinent regulations,
- d. The maintenance of complete records. ,
- e. The conduct of the final survey and preparation of completion report,
- f. The complete fulfillment of criteris to merit the release of '
thi,s facility to unrestricted use. , This dismantling plan . vill be organized in so far as possible into logical tasks such that work on one given task will not be dependent upon
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- partini cr tha complction of anoth2r task. Tha work on each task will b2 carried to 2cmpletion - disposal and record keeping - before initiating work on the next task. " Disposal" as used in the previous sentence means: plac-ing the item in the proper shipping package or, if the shipping package is filled, the temporary storage of the package pending actual shipment.
Upon the completion of all the tasks, a final radiological survey shall . be made to verify compliance with and fulfillment of the criteria established for the release of this facility to unrestricted use. A final report on the effort and .the results of this survey will be prepared to accompany- our request , to terminated the R-63 license, l l
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SAFETY ASPECTS OF THE DISMANTLING OPEBATION . Each task will be reviewed prior to initiating work to identify points of possible hazard either radiological or industrial. This information will be given to the workers so they may be alert to cope with and minimize the
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hazard. ,
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Before the initiation of work on the next task, a radiclogical survey, both radiation and contamination, will be made. The results will be given to the workmen and to the supervisor so that proper procedures and cautions may be exercised. This type survey may be conducted on a daily basis or more frequently if necessary.
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Although the R-3 reactor has been shut down for seven years, and has , been dry for six years, the NRP will be prepared to monitor the air in the working areas as well as have radiation detectors available. A hazardous radiation level or an airborne contaminant is not expected; however, every precaution will be taken until it is proven the work can be safely undertaken. The R-3 bay floor will, be arranged to provide separate areas for re-ceipt and examination of articles removed from the facility; e.g. a contami-nated area; holding areas prior to disposal; a working area, and a place of
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- transition betw n thn contaminatsa arca and tha " clean" arec. Standard health physics safety procedures will be observed during the entire opera-
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Contaminated solid wastes will be packaged in appropriate containers prescribed by NRC and DOT regulations. Records will be established and main-tained throughout this operation. These records will include waste shipnents - to insure compliance with appropriate regulations.
- During dismantling, the R-3 bay will be "off-limits" to all personnel not directly involved with this work. The only exception will be those iridi-viduals using the gama facility which is in the R-3 bay. These personnel
~ will ce admitted only for the duration of their work at the gamma facility.
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If necessary, the dismantling work will be temporarily interrupted while the gamma facility is being used. The disposal of non-contaminated solid waste will be handled locally. The early removal of non-contaminated items from the R-3 bay will facilitate operations as it is expected that the available space will be needed to hold i contaminated items prior to shipment to a burial site, c - DESCRIPTION OF THE FACILITY AFTER DISMANTLING
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After successful completion of the dismantling operation, the R-3 bay
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will be " clean" , free of any radiological contam% tion. The R-3 reactor biological shield, from the outside, will appear unchanged. If it is proven , that the shield on the inside is contaminated, this surface would show the j 1
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marks of decontamimation action. The beam tubes will be Iceled with their
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three combination safe lock as has been their status since 1973. 4 Briefly, all surfaces -of the biological shield will comply with the
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criteria that was intially established as necessary for its release to un- -
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restricted use status. The Nuclear Engineering Department is considering sever'al options for 4
. the use of this bay area after its release. Among these are:
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- 1) - Dividing th2 area into laboratorics. - The gamma facility would be isolated and retained as a " Restricted Area."
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- 2) Partial removal of the upper part of the biological shield to permit the installation of a second floor., This would extend the utilization of the bay. The gamma facility will
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be isolated. The biological shield would be used to support the second floor. '
- 3) The biological shield could be renovated to use as a " dry
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irradiation facility."
- 4) The thick steel plate could be placed on top of the shield
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and the entire structure, remain standing in- the " released conditon." A firm plan has not as yet evolved. However, the ultimate use of the area will include adequate provisions for the. gamma facility. 1 i NCSU RADIOLOGICAL PROI'ECTION OFFICE (RPO) .,
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The Nuclear Engineering Department, by irirtue of the PUISTAR reactor, has a, Reactor Health Physics Section which is responsible for the day-to-day ' radiological safety program related to reactor operations and utilization,
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The NCSU Radiological Protection Office has campus-wide responsibilities for all utilization of radioactive materials and radiation producing devices and the safety programs related thereto.
- The Department RHP will supervise the day-to-day dismantling work and will conduct the various radiation surveys as required. The RHP'shall super-vise the final survey on which our request to terminate our license will be i I
based. , , The NCSU-RPO will over see this operation, conduct " spot" radiological surveys as they deem necessary. They will provide the guidance and super-vision of the packaging, labeling and shipping of contaminated articles; a
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function they perform for the entire campus.
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In short, this dismantling operation will have close' supervision on a
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,. day-to-day bases by the Reactor Health Physics Section in the Nuclear Engi- ' neering Department and NCSU Radiological Protection Office will monitor this operation and confim the radiological condition of the facility by spot
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- i. DISMANTLING PIAN
. Attachment 1 This attachment identifies the tasks associated with the dismantling
, l of the R-3 reactor and the decontamination of the R-3 bay and' reactor bio-
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logical shield. Each task lists the ma,jor items of equipment to .be removed. ;
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or, in the case of task VII - R-3 Bay, lists the places of particular in- l terest for contamination survey and subsequent decontamination. TASK I Control Room.
- 1. Cut and remove cables from the biological shield top back to the Control Room to isolate the Control Room. -
- 2. Equipment to be removed:
2 Linear Power Channels I High Voltage Power Supplies I Amplifiers -
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' Difference Amplifier Recorders i . Meters -
Scram Circuits Alarm Circuits Log Power Channel
. Log Amplifier Period Circuit e
Period Recorder Lo6 N Period Meter ~ Lo6 N Power Meter Log Gamma Channel - Preamp 21fier ,
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Automatic Control and Override System Annunciator Panel
- Alarm Relay System
. - Warning Lights Relay System
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TASK I - Control Room (continued)
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. . Console
- Area Monitor Windjamer Panel, Meters, and Power Supply TASK II - Pipe Pit -
The equipment below floor level under the Bulk Irradiation. Tank. (Figure 6, Figure 1, page 3.)
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Equignent to be removed: Storage Tank
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Ion Exchange
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' Pumps Heat Exchanger
, mms Valves Electrical Lines
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NOI'E : , There are two pipes to this storage tank from outside this
, pit. One pipe is the drain line from the pool tank; and the other, the pool tank over-flow. Although these lines are included in "Ex-ternal Piping to Shield", it may be necessary, in fact, to remove these pipes.with Task II.
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- TASK III - External Piping to Shield
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See Note, Task 3I. Equipnent to be removed:
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Drain Line from Pool Tank j Over-flow Line from Pool Tank . Level Site Glass
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Bulk Irradiation Facility Pipe . .
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PRIMARY COOLING SYSTEM '
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TASK IV - Remove Pool Tank Equipent to be removed: Control Rod Drive' Motors on Top of Pool Tank Fuel Element Elevator Graphite " Elements" in Grid Corners
- Pool Tank
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TASK V - Graphite.and Lead Ericks Equipent to be removed: ,,
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1+ Instrumentation Cans and Associated Cabling Graphite - Thermal Column and Reflector Bricks - Pb around Reflector
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TASK VI - Decontaminated Biological Shield The inside of the biological shield and the beam ports must be surveyed to determine the extent of activation. This survey will determine the extent of the decontamination and the depth of concrete to be removed from the shield and the inside ends of the beam ports.
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TASK VII - R-3 Bay The following areas are to be strveyed and, if necessary, decontaminabed: Trenches y Beam Catchers in the Bay Walls - i Stora6e Tubes in the Bay Walls Remove the Bay Wall Power Level Indicator
. Remove Two Bay Area Monitors -
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Change Filter in Filter Room ,
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TASK-VIII - Final Radi'ation Survey ,
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The process of decontamination and survey will be continued until
-.all surfaces are acceptable for release to unrestricted' usage.
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