ML20090G610
| ML20090G610 | |
| Person / Time | |
|---|---|
| Site: | 05000310 |
| Issue date: | 01/04/1971 |
| From: | Reitler E NUCLEAR MATERIALS & EQUIPMENT CORP. (NUMEC) |
| To: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20090G464 | List: |
| References | |
| FOIA-90-558 NUDOCS 9203120384 | |
| Download: ML20090G610 (2) | |
Text
NUMEC
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i Nutlear Materials and Equipment Oceperation Apollo. Pennylonia IW11 Tettphone 412 H!till Cable NUMEC
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January 4, 1971 g-i
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t Mr. Donald J. Skovholt Assistant Director for Reactor Operations 3.,
Division of Reactor Licensing
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cN Y. 3 United States Atomic Energy Commission Washington, D. C.
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Dear Mr. Skovholt:
1.
Pursuant to 10CFR Part 50.82, the ARCO Radiation Process Center respectfully requests the Couunission to terminate Facility License Number R-72, whicn authoritas the Departrient of Potest and Waters of the Commonwealth of Pennsylvania and the Nuclear Materials r.nd Equipment Corporation (tMtEC) to possess, but not to operate, the reactor facility located near Quehanna. Pennsylyania, l'.
S *Nility has been licensed under By-Product License Nueber 37-12307-p in irradiation process facility for the process irradiation of cor t.cial products using Cobalt-60.- Both the small and large sections of tho former reactor pool have beer, converted for use of Cobalt-60 under the facility By-Product License.
2.
The reactor facility has been dismantled in the following manner:
1.
The Pu(14.99 gra) - Be Neutror. source, two fission 2
chambers and the reactor core grid plate have been transferred to the Pennsylvania State University as i
approved in the Acuandment No. 4 dated January 15, 1969; Q
2.
Unitradiated fuel elements containing 5.2 Kilograms of 6 Ih U-235 have been transferred to Brookhaven National
=~
Laboratory as approved in Amendment No. 5 dated I
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}$y g f f March 5, 1969:
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Your cadmium-Boron carbide safety shims are in storage g
in the Ser" e Area pool. These shims read 100 MR/hr.
P or less an'
'll be transferred for burial to an authortred nandler of radioactive vaste.
4.
The control console was dismantled and the parts were trans-fetTed to the Department of Forest and Waters of the Commonwealth of Per.nsylvania.
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9203120384 910708 PDR FOIA BRENNAN90-5F)O PDR
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W Mr. Donald J. Skovholt
' ' January 4, 1971 3.
Since the facility has'been converted for use as an irradiation process center, is licensed by the Connission for'this use and no longer possesses the capability.for use as a reactor facility, the ARCO Radiation 1. cess Center respectfully requests the
. Commission to terminate Facility License Number R-72.
If more information is required, please feel free to call Area Code 814 263-4871.
Very truly yours,
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Edvaro K. Reitler, Manager Health, Safety and Licensing EKR/kjr i
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ARCO Cl.amical Company Dwision of AttanhcRichheldCompany
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ARCO Ra' ' ion Process Center Post Ofbe on 115 WO O 'fs
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7 Telephone 614,263 4871 D
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MAR 2 619715 Fir. Al Brauner Division of Reactor Licensing g-n yQuH 7
United States Atomic Energy Commission am Washington, D. C.
20545 m t ma
Dear Mr. Brauner:
The foll' wing information concerning the contamination of the facility, the disposition of the remaining inventory of reactor components, and the presence of records pursuant to the R-72 License is offered to sup-plement and update __the letter of March 5, 1971, to Cocunission pursuant to Docket No.gu-J13 Under Byproduct License 37-12307-02, the ARPC is divided into two areas with respect to contamination; i.e. normally clean areas where contam-ination levels are maintained well below 500 dpm/100 cm2 removable beta and contaminated areac where the limits are 100 dpm/100 cm2 removable 2
alpha, 5,000 cpm /60 cm2 direct (fixed) alpha, 5,000 dpm/100 cm remov-able beta, and 5 mrad at 2.5 cm direct (fixed) beta. Strontium-90 and cobalt-60 constitute virtually all of the contamination found in contam-inated areas.
The Strontium-90 activity is residual in the duct-work of the hot cells and in the low-level portion of the liquid waste system from the operations of the Martin-Marietta Company.
No evidence of mixed fission product contaminetion nor alpha contamination has been found.
Thirty-five reactor activated assemblies were sh!pped to Kentucky for burial by Nuclear Engineering Company, Incorporated on March 19, 1971.
Two safety shims encased in concrete within a 55 gallon drum were retained and stored due to an external radiation level in excess of 200 mR/hr.
This 55 gallon drum will be additionally shielded and shipped at a later date.
NO records have been found which relate either radiation / contamination levels or personnel exposures during Curtiss-Wright Reactor Operations.
The records of radiation / contamination present in facility at the time of transfer to NLDIEC are the earliest records which remain.
If additional information is desired, please feel free to contact either the writer or Mr. Reicler at (814) 263-4871 and (412) 842-0111, respec-tively.
Very truly yours, 9
&gI' ARCO RADI ATION PROCESS CENTER 7
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b Henry J. Bicehouse, Supervisor
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' Introduction This ihformation'is provided in support of the ARCO Radiation' Process Center's request for termination' of the Facility License No. R-72.
This facility has been licensed under By-Product License Number 37-12307-02 as an irradiation process facility for cobalt-60 t rrad-intion of commercial products.
2.0 Disassembly and Conversion of the Reactor Facility _ _ Prior to this Request 2.1 The plutonium (14.99 gm)-beryllium source, two fission chambers and the reactor core grid plate were transferred to the Penn-sylvania State University. This transfer was approved in Amend-ment No. 4 dated January 15, 1969.
22 Unitradiated fuel. elements containing 5.2 kilograms of uranium.
235 were transferred to Brookhaven National laboratory. Amend.
ment No. 5 dated March 5,1969, authorized this transfer. -
2.3 The control console was dismantled and the parts were given to the Department of Terests and Waters of the Corinonwealth of Pe nnsy lva nia.
2.4 Amendoent No. 4 to Tacility License No. R-72 authorized the use of the former reactor pool as the location of a cobalt-60 ir-radiator originally licensed under By-Prcduct License No.
37 04456-08 and currently uader By-Product License No. 37-12307-02_
as amended.
2.5 The ARCO Radiation Process Center possesses no special nucicar material nor any irradiated fuel assemblics in the facility pursuant to the.R-72 license.
3.0 Procedures for Removal of Romaining Peactor Parts 3.1 Inventory of remaining reactor parts 3,1.1 Four (4) safety shim rods with outside dimensions 2.25 x 0.375 inches of laminated construction con-sisting of a 0.065 inch stainless steel outer shell, a 0.032 inch cadmium inner shell and the remairing cavity-filled with boron carbide crystals to pro-duce a minimum density of,1.5 gm/cm>.
3.1.2 Yhree core access elements with dimensions of 3 x 3 inches x 28% inches for_the cavitated portion with an overall length of 34 inches including nose piece.
iL 3.1.3 Twenty-six reflector elements, which are also 3 x 3 inches x 28\\ inches for the cavitated portion with an overall length of 34 inches including nose piece.
1 o
i-
l 3.1.4 Four " mock-up" fuel rods containing no special nuclear material raeasuring 3 x 3 inches x 2Si inches with 42 inches of aluminum connector of approximately 2 inches in outside dianeter.
These assemblies are reported a have been used in one experiment and then stored. The cavitated portions are constructed of aluminum, but the central volume is a void.
3.2 Radiation and contaminat ion levels of the remaining reactor parts 3.2.1 The four safety shims show external radistion readings ranging from 14 milliroentgens per hour on the ends to 100 milliroentgens per hour in the center of the vertical plane, (readings taken at approximately one (1) inch from the surface).
There is no measurable removable centamination on the accessible surfaces.
3.2.2 The three core access elements show no removable contamination on the accessible surfaces.
One of these subassemblies reads 12 milliroentgens per heur gamma and 8 milliroentgens per hour apparent beta as a maximum near the center of the vertical plane to a minimum of 2 milliroentgens per hour.
The second subassembly ranges from less than 1 milliroentgen per hour to a naximum of 3 milliro-entgens per hour gamma with virtually no measucable beta.
The third subassemblv reads less than 1 millircentgen per hour for both beta and gamma.
3.2.3 The reflector elements ranged f rom 2 to 40 millircentgens per heur gamma and from less than 1 to approximately 12 milliroentgens per hour beta.
No remavable contamination was measured on accessible surfaces.
3.2.4 The four " mack-up" fuel rods shewed approximately equal activation with ranges of 2 to 10 milliro-entgens per hour gamma.
Neither any fixed beta r.or removable contamination were present on these assemblies.
3.3 Pu rs uan t to Department of Transportation Title 49, part 173.90 (C) and Atomic Energy Cocetssion Title 10, Part 71.4 (P), the follow-ing classification is made for each item of paragraphs 3.1 and 3.2; I
Approxinate Possible
. Mav,imum -
-Transport
= Notnencla tu re Radionuelides Activity
. Group 60 113M Co, Cd-55 109 d,_57Co pe, C
14, 59 1, $3Ni.
160 mci
.III Type A Safety Shim-#1-C 3
- 2-o n
n n
n n-p3
- 4-55,,
S 7
Zn, Reflector
- 1 35,
C 100 mci IV Type A 5
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p3 n
n
.n n
- 4 50 mci o
n
- 5
- 6 25 mci n
n n
n n
- g7
'n pg n-30 mci n
n o
n n
pg
- 10 25 mci
- 11 50' mci
- 1r 100 mCL
- 13
- 14
- 15 70 mci
- 16
.#17 80 mci 70' mci
- 18-
- 19 25 mci 33 mci
- 20
'70 mci
- 21 o
n.
n n
n p22 100 mci
.#23 80 mci n-
- 24
- 25 25 mci n
.#26 30 mci 55 e, 65Zn, 35S x.10 mci F
Mock-Up. Fuel. Rod A B
-C D
Core Access-Elenent #1 55pe, 65Zn,
'S n
n n
- 2 45 mci
- 3 Virtually No Activity (41) l Note: These calculations are based on the follcuing assumptions:
(1) camma emitting radionuclide of 0.50 MeV; (2) Highest measured external field (usually at center of activated portion) extended over entire surface of the cavitated portion of the assembly; and (3) The external ' fields were primarily the result of activation products within the encapsulating material originating in trace contaminants.
Since these estimates of tetal activi vete based on basically censervative assumptions, the safety hazard of these materials should be considerably less than the calculated activity would i,dicate.
3.4 These subassemblies shall be packed in 55 gallon druns, suitably labeled, and t rans ferred t o a licensed radioactive waste dis-posal firm for autho.ized disposal.
The ccntainers will be packed to naintain less than 200 milliroentgens per hour at e c= n -
tact and le s s t-han 10 milliroentgens per hour at a meter.
4.0 Radioactive Waste Treatnent System 4.1 The liquid waste treatment plant is described in Paragraph 7.1.2 (see attachment) of the Application For By-Product License No.
37-12307-02.
Contamination and radiation levels within this system are the result of the activities of several by-product licenses as well as those from the R-7 2 Li c e ns e.
6.2 Since this sys t em is currently licensed and regulated under By-Product License Na. 37-12307-C2, t e rmi na t ion o f t he R-7 2 License should in no way endanger the health and safety of the general public.
S.O ARCO Padiation Process Cent er Ope rations 5.1 By-Product License Na, 37-12307-02 authorizes the use of the former reactor pool as a col alt-60 irradiation process system described as the AKC0 small and large paol irradiators in the application for this license.
5.2 Radiation and contaminaticn levels are licensed and regulated by By-Product License No. 37-12307-02 and termination of the R-72 license would in no way endanger the health and safety of the general public.
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inner cover put on, the top cavity filled with concrete, and the outer drum cover put on.
7.1.2 Liquid Wastes A liquid waste treacr.ent plant is available for disposal of both low level and high level liquid wastes. The plant for treatment of these vastes is housed in a separate building about 50 feet f rom the main building.
Figure 7.2 shows that wastes flew to the treatment plant by way of two collection systems.
The low 1cvel waste system originates in areas of potential radioactive liquid vastes contamination such as the radiochemistry laboratory drains and the fume hoods in the decontamination room. Drains from areas of unlikely, but possible, radioactive contumination lead to a " suspect" waste system and cliginate from such places as the change room showers, pool area and the personnel decontamination sink in the change room.
Each system cay be terminated in either of two 3000-gallon underground tanks.
When one tank in one sys tem is f ull, tne other tank in the same system may receive drainage.
There are two pumps for each system: one in each system operates when requ!. red, with the second used as a standby.
When a tank is full, the contents are mixed by circulation through the pump and back to the tank. A sample is then taken from the sacpling cock on the pressure side of the pump and an analysis made for radioactivity content
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filter 20 pst Cond ens e r 0-Sample 2
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(1)f Low Level Liquid Wastes:
If the activity concentration is_ below the maximum per -
missible' level for release, the contents of the tank-are pu= ped.out for disposal directly to the stream.
If the 9
activity _ concentration is :'above the permissible level, the contents of the tank are diluted until they are below the permissibic level or treated as high level liquid waste.
(2) High Level Liquid Wastes High level liquid wastes-are those liquid wastes which cannot be diluted to below permissible Icvels practically.
High level-liquid wastes are pumped to an evaporator where -
]
the liquid is vacuum evaporated to provide a condensate of sufficiently low icvel contamination for discharge to _ the I
-stream.- The high level residual sludge remaining in the,
- evaporator is drained into 55-gallon pre-loaded with Flor-Co 1
drums.which are-shipped offsite for ultimate disposal as solid radioactive vaste- (Figure 7.3).
-The water vapor-from the evaporator passes through a heat _ex -
changer-type condenser, -and the condensate ficws into the 100-gallon vacuum receiver tank and is then transferred to the 1000-gallon gravity head-tank where it is analyzed for activity concentration.
If the activity is below permissibic levels, it can be treated as low level liquid waste.
If the activity is above. permissible icvels and cannot be diluted, it' can again be put through the evaporator.
7-3 n...-.
.a.
A station has been provided for the addition of caustic to any storage tar.k for acid neutrali;:ation. This station nay also be used for the transfer of re.dioactive vaste solutions from other laboratorics-to one of the storage tanks.
Each group of two storage tr.nks is vented above roof Icvel through absolute type filters.
The system has been designed co be fic:<ible. The following operations are possible:
(1)
The contents of any storage tank can be pumped to the evaporator.
(2)
The contents of any storage tar-.k can be pumped to the gravity 4
head tank.
(3) The contents of any storage tank can be pu= ped to any other storage tank.
i (4)
The contents of the gravity head tank can be routed to any storag'e tank.
I i
i 7.1.3 Gascous Syst'm e
Airborne radioactive particulate containnent is leved through i
the principle of, and design for, multiple containment. This system includes a barrier of cultiple absolute filters i
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4-ft square Cemesto board outer cor.tainer 3/4-in. Cemesto board scaled on 3 sides, top and bottom with plexiglass dc, ors -
Figure 7..,
wast e T. cat uent--studge itemoval
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