ML20207R940
| ML20207R940 | |
| Person / Time | |
|---|---|
| Site: | 07000572 |
| Issue date: | 04/30/1983 |
| From: | MONSANTO CO. |
| To: | |
| Shared Package | |
| ML20207R676 | List: |
| References | |
| NUDOCS 8703180327 | |
| Download: ML20207R940 (53) | |
Text
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LICENSE SPECIFICATIONS f
8703180327 860314 REG 3 LIC70 SNM-0567 PDR.
O MONSANTO RESE ARCH CORPORAT19N e
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C LICENSE SPECIFICATIONS TABLE OF CONTENTS 1.0 AUTHORIZED ACTIVITIES 1.1 DEFINITIONS 2.0 POSSESSION LIMITS 2.1 SPECIAL NUCLEAR MATERIALS 2.2 BY-PRODUCT MATERIALS-3.0 LOCATIONS OF USE 3.1 PRINCIPAL PLACE OF BUSINESS 3.2 SOURCE RADIOGRAPHY 3.3 SHOWS AND EXHIBITIONS 3.4 CUSTOMER'S LICENSED FACILITIES 3.5 STORAGE OF SOURCES OFFSITE 3.6 FIRE PROTECTION FOR ENGINEERED PRODUCTS 3.6.1 AUTOMATIC SYSTEMS 3.6.2 MANUAL FIRE PROTECTION APPARATUS 3.6.3 GLOVE B0X PROTECTION 3.6.4 LARGE REMOTE B0X PROTECTION 3.7 ENGINEERED PRODUCTS PROCESSING AND STORAGE AREA 3.7.1 CONTROLLED SUPPORT AREA 3.7.2 CONTROLLED PROCESS AREA 3.7.3 WASTE STORAGE AREA 4.0 PREPARATION OF PLUT0NIUM ALPHA CALIBRATION SOURCES 5.0 ADMINISTRATIVE ORGANIZATION 5.1 GENERAL 5.2 ORGANIZATION RESPONSIBILITIES 5.2.1 MANAGER OF ENGINEERED PRODUCTS DEPARTMENT 5.2.2 OPERATIONS MANAGER 5.2.3 MANAGER OF MANUFACTURING 5.2.4 RADIATION SAFETY OFFICER 5.2.5 RADIATION SAFETY COMMITTEE 5.2.6 PERSONS AUTHORIZED TO USE AND/0R SUPERVISE USE OF RADI0 ACTIVE MATERIALS i
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LICENSE SPECIFICATIONS TABLE OF CONTENTS (CONT'D) 5.2.7 PERSONS OCCUPYING DESCRIBED POSITIONS 5.3 DEVELOPMENT OF OPERATING PROCEDURES 5.4 INTERNAL AUDITS OF PERFORMANCE 5.5 CHANGES IN OPERATING PROCEDURES, FACILITIES AND EQUIPMENT 5.6 AMENDMENTS TO THE NRC LICENSE 5.7 INSTRUCTION OF NEW EMPLOYEES AND REFRESHER TRAINING FOR PERSONNEL 5.7.1 TRAINING OF NEW EMPLOYEES IN PROCESS AREA 5.7.2 REFRESHER TRAINING 5.7.3 WORK CERTIFICATION 6.0 EMERGENCIES 7.0 RADIATION CONTROL 7.1 SPECIFICATIONS FOR FILM BADGES 7.2 RADIATION MONITORING AND CONTAMINATION CONTROL 7.2.1 GENERAL REQUIREMENTS 7.2.2 RADIATION MONITORING 7.2.3 CONTAMINATION CONTROL 7.3 SHIELDING 7.3.1 PROVISION 7.3.2 USE 7.3.3 MATERIAL 7.4 PROTECTIVE CLOTHING 7.4.1 CLOTHING REQUIREMENTS 7.4.2 CLOTHING PROVISION 7.4.3 LAUNDRY REQUIREMENTS 7.5 REMOTE HANDLING DEVICES 7.5.1 PROVISION 7.5.2 TYPE 7.6 RADI0 ACTIVE WASTE 7.7 MATERIAL AND EQUIPMENT RELEASE LIMITS 7.7.1 MONITORING 7.7.2 LIMITS 11 April 1983 e MONSANTO RESEARCH CORPORAT00N e
LICENSE SPECIFICATIONS TABLE OF CONTENTS (CONT'D) 7.8 INSTRUMENTATION 7.8.1 INSTRUMENT REQUIREMENTS 7.8.2 PORTABLE INSTRUMENT SPECIFICATIONS 7.8.3 AIR MONITORING AND SAMPLING INSTRUMENTATION SPECIFICATIONS 7.9 B10 ASSAY 7.9.1 GENERAL REQUIREMENTS 7.9.2 MAXIMUM PERMISSIBLE BODY BURDEN 7.9.3 ACCEPTABLE PRACTICES 7.10 POSTING AND CONTROL
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7.10.1 ACCESS 'id CONTROLLED AREAS 7.10.2 POSTING 8.0 DESIGN FEATURES - AIRBORNE CONTAMINATION CONTROL 8.1 INTER-AREA FLOW DESIGN 8.2 ENCLOSURES 8.3 AIRBORNE CONTAMINATION CONTROL 9.0 RECEIPT AND SHIPMENT OF RADI0 ACTIVE MATERIALS 9.1 RECEIPT OF RACKAGES CONTAINING RADI0 ACTIVE MATERIALS 9.2 SHIPMENT OF RADI0 ACTIVE MATERIALS 10.0 WORK LIMITATIONS 11.0 PROCESS LIMITS 12.0 MAXIMUM. PERMITTED QUANTITIES OF RADI0 ACTIVE MATERIAL PER SOURCE CAPSULE iii April 1983 e MONSANTO RESEARCH CORPORATION e
o LICENSE SPECIFICATIONS FOR MONSANTO RESEARCH CORPORATION ENGINEERED PRODUCTS 1.0 AUTHORIZED ACTIVITIES The types of activities authorized include: manufacture, development, distribution of radiation sources and devices containing radioactive material.
Also, installation, removal, servicing and wipe testing of sealed sources at licensed locations away from the license's location.
In addition, the licensee designs, manufactures, uses, and sells shipping containers for radioactive materials.
Pursuant to Section 70.39 of 10 CFR Part 70, manufacture of calibration and/
or reference sources containing plutonium for distribution to persons generally licensed pursuant to Section 70.19 of 10 CFR Part 70 is authorized as described in Sections 4.0 and 9.0 of these License Specifications, Pursuant to Section 20.105(a) of 10 CFR Part 20, production of radiation levels in unrestricted areas as specified in Section 3.5 of these License Specifications is authorized.
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1.1
-DEFINITIONS (A)
LICENSE SPECIFICATIONS The License Specifications detail the authorized activities, the required conditions under which the authorized activities are to be carried out, and the specific restrictions applicable to the authorized activities.
No changes in the License Specifications may be made without prior approval of.the Nuclear Regulatory Commission as evidenced by a license amendment.
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(B)
OPERATIONS MANUAL r
L The Operations Manual describes the methods, management structure, and procedures and facilities established to assure that all activities 1
are carried out in compliance with the License Specifications.
Changes may be made in the Operations Manual without prior approval of the Nuclear Regulatory Commission if the changes are such that compliance with the License Specifications remains assured. Each
.such change must be approved by the Radiation Safety Committee, and a record of the change and approval shall be maintained as long as the' license remains in effect.
(C)
RADIOLOGICAL CONTINGENCY PLAN The Radiological Contingency Plan, submitted to the Nuclear
. Regulatory Commission on August 20, 1981 and revised on October 27, 1981 and December 24, 1981 shall be considered to be a part of the License.
No change in the-Radiological Contingency Plan that would decrease the response effectiveness of the Plan may be made without prio'r approval of. the Nuclear Regulatory Commission as evidenced by a license amendment. Changes to the Radiological Contingency Plan may be made without prior Commission approval if the changes do not decrease the response effectiveness of the Plan. Records of all such changes shall be maintained for a period of two years from the-date of the change. A report containing a description of each such change shall be furnished to the Chief, Material Licensing Branch, Division of Fuel Cycle and Material Safety, NMSS, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, and to the appropriate NRC Regional Office specified in Appendix D of 10 CFR Part 20, within six months after the change is made.
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i (D)
ABNORMAL OCCURRENCE Abnormal occurrence means any emergency situation as defined in Section 3.0, " Class of Radiological Contingencies" of the license's Radiological Contingency Plan and any other situation designated as such by the Radiation Safety Officer or the Radiation Safety Comittee.
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2.0 POSSESSION LIMITS 2.1 SPECIAL NUCLEAR MATERIALS The following quantities of special nuclear materials are authorized:
CHEMICAL AND/OR MATERIAL PHYSICAL FORM QUANTITY A.
- A.
Any A.
199 g
- Plutonium may consist of any of the following isotopes in any combination: Pu-236, Pu-238, Pu-239, Pu-240, Pu-241 and Pu-242.
CHEMICAL AND/0R MAXIMUM QUANTITY 2.2 BY-PRODUCT MATERIALS PHYSICAL FORM 0F RADI0 ACTIVITY-B.
Any by-product B.
Any B.
25 Ci of each material having an by-product atomic number from material 3 to 83 inclusive with certain except-ions in list below:
C.
Cesium-137 C.
Any C.
210 Curies D.
Curium-243 D.
Any D.
10 Ci E.
Cobalt-60 E.
Any E.
50 Ci of each Strontium-90 by-product Thallium-204 material Antimony-124 Bismuth-210 F.
Promethium-147 F.
Any F.
1200 Ci Polonium-210 3000 Ci Neptunium-237 100 mci Americium-241 6000 Ci Curium-242 600 Ci Curium-244 600 Ci G.
Californium G.
Any G. 10 milligrams
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3.0 LOCATIONS OF USE 3.1 PRINCIPAL PLACE OF BUSINESS Monsanto Research Corporation, Dayton Laboratory,1515 Nicholas Road, Dayton, Ohio 45407. Engineered Products shall use rooms 3 through 14 of Building 2 for manufacture, development and distribution of authorized materials. Waste materials will be stored in Building 7 until transfer out of plant for disposal.
3.2 SOURCE RADIOGRAPHY Sealed radioactive sources that meet special form requirements may be transported to properly licensed facilities for radiographic exami-nation. The conditions of transport must be in accordance with Department of Transporation and NRC regulations.
The handling of such sources will be by Engineered Products personnel only, and under the supervision of any of the competent technical personnel specified in Section 5.2 of these License Specifications as authorized to use or supervise the use of radioactive materials.
3.3 SHOWS AND EXHIBITIONS Shows and exhibitions in "non agreement" states. Any source dis-played shall contain less than a large quantity of radioactive material in special form. The source capsule or holder must bear indentification as to model number. isotope, amount of isotope, and bear the words " CAUTION, RADI0 ACTIVE". The radiation levels from the display shall conform to the requirements of 10 CFR 20.105.
Since radioactive materials would be on display for periods of less than eight hours, the radiation level at any location where an individual could continuously occupy is limited to 2 mrem /hr.
In the event that sources are to be displayed for periods of eight or more hours, the radiation levels will be further limited as required by 10 CFR 20.105. The sources will be displayed only in the presence of or under constant surveillance of Engineered Products personnel.
When not on display, the sources will be kept in their shipping container and stored as specified in Section 3.5 of these License Specifications.
l 3.4 CUSTOMER'S LICENSED FACILITIES Sealed radioactive sources supplied to customers may be installed, removed, serviced, or wipe tested within a customer's licensed facility by any of the competent technical personnel listed in Section 5.2 of these License Specificaitons.
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3.5 STORAGE OF SOURCES OFFSITE Sealed sources stored at locations other than the location specified in Item 3.1 above, under authority of this license, shall be securely housed in a shielded container which is either stored in a secure area under the surveillance at all times of security personnel or stored in a general storage area with container being locked, security sealed and with access controlled at all times. The storage container itself will be such that the external dose. rate is less than 0.5 mrem /hr. at the surface.
In the event of storage of 5 or more weeks, the radiation levels will be further limited as required by 10 CFR 20.105.
3.6 FIRE PROTECTION FOR ENGINEERED PRODUCTS 3.6.1 AUTOMATIC SYSTEMS All the rooms used for processing and storing radioactive materials or finished sources (except the waste storage area described in Section 3.7.3 below) shall be protected with automatic sprinkler systems.
The systems shall be monitored electronically at a central location where immediate telephone notification shall be made whenever a water flow is detected. There shall be two systems, one for the controlled support area and one for the controlled process area.
The systems shall be checked monthly by a water flow test.
1 6.2 MANUAL FIRE PROTECTION APPARATUS Carbon dioxide, dry chemical and/or halon fire extinguishers shall be located around the area as appropriate. Each extinguisher shall be checked monthly to see that its seal is intact and that it appears to be ready for use. Each cylinder is weighed yearly to check its content.
3.6.3 GLOVE BOX PROTECTION The glove boxes shall be protected externally by the sprinkler systems. The combustibles allowable in the glove boxes shall be severely limited to reduce the possibility of fire. The com-bustible wastes generated in processing shall be stored in closed metal containers until removal. Plutonium cetal and other pyrophoric forms of radioactive material shall be maintained under an inert atmosphere except under the following conditions:
Material is in process and personnel are in attendance.
Each glove box in use shall contain a manually-operated hand fire extinguisher containing halon gas, except that if the glove box contains materials which may adversely react with halon gas, other appropriate exting-uishing means will be provided.
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,z 3.6.4 LARGE REMOTE BOX PROTECTION The large remote box (north part of Room 6) shall be protected as
~ described'in Section 3.6.3 above, except that it shall contain an automatic halon system with external manual trips'in place of the hand-held halon unit. The automatic system shall have an override so that it may be inactivated during periods when the box contains materials which may adversely react with halon gas.
3.7 ENGINEERED PRODUCTS PROCESSING AND STORAGE AREA 3.7.1 CONTROLLED SUPPORT AREA Those processes which involve handling of sealed or packaged radioactive materials, preparation of non-radioactive assemblies, and shipping are accomplished in Rooms 3, 4, 10, 11, 13, and 14 of Building 2.
The building construction consists of the following:
Walls:
Poured concrete (one foot, one inch thick) walls with interior lined with glazed tile. Windows have been removed and filled in with eight inch concrete blocks.
Floor:
Six inch thick poured concrete reinforced.
Roof:
Concrete beams and roof deck with built-up asphalt roof, all covered by a wood-truss peaked roof.
3.7.2 CONTROLLED PROCESS AREA Those processes which involve the encapsulation of radioactive materials or handling of raw materials are accomplished in Rooms 6, 7, 7A, 8, and 9 of Building 2.
The building construction con-sists of the following:
Walls:
Room 6, 8, 9, Steelox wall panels with insulation and masonite interior panels.
t Room 7 Steel Frame Steelox wall panels with insulation, and dry wall.
Room 7A Wood Frame, Steelox wall panels, insulation, and dry wall.
Floor:
Room 6, 7, 8, 9, Six inch reinforced concrete.
Room 7A, Eight inch reinforced concrete.
Roof:
Room 6, 8, 9 Four inch wide 18 gage Steelox roof panels, 3-5/8 inch Rockwool insulation, wood sheating and built-up roofing. A wood-truss peaked roof has been added above the roof panels.
Room 7, Wood and Steel frame, steel pan, insulation board, tar paper and tar.
Interior ceiling is dry wall.
Room 7A Wood frame and steel sheet metal. Dry wall interior ceiling.
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3.7.2 CONTROLLEDPROCESSAREA(Cont'd)
Fence:
Chain-link, 7 feet high around manufacturing area creating restricted access area.
3.7.3 WASTE STORAGE AREA Radioactive waste material is properly packaged and stored in Building 7 while awaiting shipment to a commercial site. Building 7 is a poured, reinforced concrete bunker, built into the incline on the east side of Building 2.
The door to Building 7 is within the fenced restricted access area surrounding the manufacturing portion of Engineered Products and is kept locked.
Any combustible material stored in Building 7 must be kept in sealed metal or specially constructed fire resistent con-tainers.
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t 4.0 PREPARATION OF PLUTONIUM ALPHA CALIBRATION SOURCES Calibration sources to meet 10 CFR 70.39 specifications are prepared by deposition of acid solution containing plutonium onto a one-inch diameter by 0.030 inch thick stainless steel disc. The naterial is then affixed by firing to a red heat. This source shall be our Model No. MRC-A-Pu-SS. These sources are subjected to e leak test prior to transfer to another person. The leak test consits of a dry wipe, a wet wipe, and then a dry wipe. The wet wipe consists of a tissue moistened with distilled water. Any wipe in excess of 0.005 microcuries is cause for rejection of the source.
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y 5.0 ADMINISTRATIVE ORGANIZATION 5.1 GENERAL Name of organization:
Engineered Products Department Monsanto Research Corporation P.O. Box 8, Station B Dayton, Ohio 45407 State of incorporation:
Delaware Location of principal 800 North Lindbergh Blvd.
corporate office:
St. Louis, Missouri 63166 Corporation control:
Monsanto Research Corporation is a wholly owned subsidiary of Monsanto Company, St. Louis, Missouri.
Neither company is subject to control by any alien, foreign corporation or foreign government.
5.2 ORGANIZATION RESPONSIBILITIES 5.2.1 MANAGER OF ENGINEERED PRODUCTS DEPARTMENT The Manager of Engineered Products Department is responsible for the over-all conduct and operation of the organization. A functional organizational breakdown is shown in Figure 5.2.1.
The Manager of Engineered Products reports to the Director of the Dayton Laboratory of Monsanto Research Corporatis9. of which the Engineered Products Department is a part. The Director of the Dayton Laboratory, in turn, reports to the President of the Mo.nSanto Research Corporation.
The Manager of the Engineered Products Department must have a bachelor's degree or equivalent training and experience in the physical or biological sciences or in engineering and have at least five year's experience in the management of similar type operations.
He must be cognizant of company policies and operating procedures and be able to conduct the Engineered Products Department consistent with goud business practices.
5.2.2 OPERATIONS MANAGER The Operations Manager must have a bachelor's degree or equivalent training and experience in the physical or biological sciences or in engineering and have at least five year's experience in a technical field involving multi-discipline operations.
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DAYTON 3
LABORATORY y
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ENGINEERED PRODUCTS DEPARTMENT SECRETARIES l
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ACCOUNTING ENGINEERING OPERATIONS DESIGN A MARKETING l PURCHASING l
DEVELOPMENT l FACILITY LIBRARY l
QUALITY CONTROL NUCLEAR HEALTH NUCLEAR MANUFACTURING MANUFACTURING PHYSICS SHIPPING &
ENGINEERING
-RECEIVING
& SHOP Figure 5.2.1
i-5.2.3 MANAGER OF MANUFACTURING The Manager of Manufacturing must have a bachelor's degree or equivalent. training and experience.in the physical or. biological sciences or in engineering and have at least five years' experience
.in handling of radioactive materials. He must be knowledgeable in the characteristics of ionizing radiation, units of radiation dose and quantities, radiation detection instrumentation, and biological hazards of exposure to radiation.
5.2.4 RADIATION SAFETY OFFICER The Radiation Safety Officer must have a college degree of bachelor level or higher or equivalent training and experience in plysical or biological sciences or engineering, and he must have at least five years' experience in the safe handling of radioactive materials.
He must be knowledgeable in the characteristics of ionizing radiation, units of radiation dose and quantities, radiation detection instru-mentation, and biological hazards of exposure to radiation appropriate to the type and forms of radioactive materials used. The Radiation Safety Officer is responsible for holding periodic (normally biweekly) 4 meetings of the Radiation Safety Committee to review safety matters.
4 If necessary, meetings will be held to fonnulate the course of action to be taken in the instance of abnormal occurrences.
The responsibility and authority of the Radiation Safety Officer includes the following:
(A)
General surveillance over all activities involving radioactive material, including routine monitoring and special surveys of all areas in which radioactive material is used.
(B)
Determining compliance with rules and regulations, license conditions, and the conditions of project approval specified by the radiation safety committee.
(C)
Monitoring and maintaining absolute and other special filter systems associated with the use, storage, or disposal of radioactive l.
material, or supervising other persons performing these activities.
(D)
Furnishing consulting services on all aspects of radiation protection to personnel at all levels of responsibility.
(E)
Receiving, delivering, and opening all shipments of radioactive material arriving at the institution and receiving, packaging, and i
shipping all radioactive material leaving the institution, or i
supervising others performing those activities.
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5.2.4 RADIATIONSAFETYOFFICER(Cont'd)
(F)
Distributing and processing personnel monitoring equipment, determining the need for and evaluation of bioassays, keeping personnel exposure and bioassay records, and notifying individuals and their supervisors of exposures approaching maximum permissible amounts and recommending appropriate remedial action.
(G)
Conducting training programs and otherwise instructing personnel in the proper procedures for the use of radioactive material prior to use, at periodic intervals (refresher training), and as required by changes in procedures, equipment, regulations, etc.
(H)
Supervising and coordinating the radioactive waste disposal program, including keeping waste storage and disposal records and monitoring effluents.
(I)
Storing or supervising the storage of all radioactive materials not in current use, including wastes.
(J)
Performing or supervising others performing leak tests on all sealed sources.
NOTE:
Sealed sources that are in storage and are not being used shall be excluded from periodic testing (to minimize radiation exposure), but shall be leak tested prior to being put into use or shipment.
(K)
The authority to stop immediately a project or activity that is found to be a threat to health or property.
(L)
Maintaining other records not specifically designated above, e.g.,
receipt, transfer, and survey records as required by Paragraph 30.51, " Records," of 10 CFR Part 30.
l (M)
Providing periodic physical inventories of radioisotopes on site, maintaining records of receipts and shipments of radioisotopes l
(including waste), and reporting the results of the physical inventories and each receipt and shipment to the person responsible for recording radioactive materials changes and maintaining running l
radioisotope inventories.
(The Operations Manager is responsible i
for limiting the quantity of radioisotopes on site to the amounts authorized by the license.)
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5.2.4 RADIATIONSAFETYOFFICER(Cont'd)
An assistant to the Radiation Safety Officer must have a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> training plus a year's experience in the handling of radio-active materials and knowledge of the characteristics of ionization radiation, units of radiation dose and quantities, radiation detection instrumentation, and biological hazards of exposure to radiation appropriate to the type and forms of radioactive materials to be used. More than one assistant to the Radiation Safety Officer may be designated during a particular time period. An assistant to the Radiation Safety Officer may be designated by the Radiation Safety Officer as assuming the latter's responsibility and authority during specified periods during which the Radiation Safety Officer is not present on site with the exception that the assistant may use or supervise the use of radioactive materials only if he has been designated as a technical specialist per Section 5.2.6 below and is on the current list of such specialists in Section 4.2 of the Operations Manual.
5.2.5 RADIATION SAFETY COMMITTEE The Radiation Safety Comittee administers the radioactive material program.
It has the authority to approve or disapprove any proposed or existing use of radioactive materials. Any individual member of the Committee has the authority to immediately stop any activity involving radioactive materials which he believes to be a threat to health or property; activities so stopped may be resumed only after they have been reviewed and approved by the Comittee.
The Comittee has three permanent members as listed below:
Engineered Products Department Manager l
Operations Manager Radiation Safety Officer Additional persons may be appointed to or deleted from the Committee by the Committee.
l The Chairman of the Committee is the Engineered Products Manager; the Operations Manager acts as Chairman during periods when the Manager of Engineered Porducts is not present on the site. Three members constitute a quorum for the Comittee to act provided that either the Radiation Safety Officer or an assistant to the Radiation Safety Officer is present, and that at least one management member l
is present. The Comittee shall meet periodically (normally biweekly) as called by the Radiation Safety Officer and at other times as may be necessary to formulate the course of action in the instance of abnormal occurrences, to act on proposals for the use of radioisotopes, or to discuss and/or act on other matters related to the radioactive material program. The Comittee shall meet at least quarterly.
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5.2.5 RADIATIONSAFETYCOMITTEE(Cont'd)
The Radiation Safety Comittee has the following duties and responsibilities:
(A)
Periodic review (normally biweekly) of radiation exposure and exposure to radioactive material received by all persons as a result of licensed activities.
If any' person has exceeded the internal targets for such' exposures, review of the corrective. actions taken to prevent reoccurrence, and if necessary in the opinion of the Comittee, establishment of additional corrective actions.
(B)
Review of each abnormal occurrence, of each violation of applicable NRC or DOT regulations, and of each item of non-compliance to the License to determine whether corrective actions and actions taken to prevent reoccurrence are adequate, and if not deemed adequate, to formulate additional corrective actions.
(C)
Timely discussion of any occurrence which might be a violation of or act of non-compliance with applicable NRC or DOT regulations or the License, to determine whether the occurrence is or is not a violation or act of non-compliance.
(D)
Review of the findings of the periodic Internal Audits of Performance to determine whether the radiation safety program, including (1) maintenance of required records, (2) procedures for controlling and maintaining radioisotope inventories, procurement, possession limits, and transfers, and (3) personnel training as specified in other paragraphs of this Section are being properly and adequately performed. The Comittee shall formulate corrective actions as necessary.
(E)
The,Comittee shall approve any proposed changes to the Operations Manual prior to implementation of the changes, and shall approve any proposed process or procedure involving radioisotopes which is significantly different than presently in use prior to implementation of the process or procedure. The Comittee also shall approve signif-icant changes and/or additions to the facilities in which radioisotopes are used.
In deciding to approve or disapprove proposals, the Committee shall consider the adequacy of facilities and equipment; operating, handling, and emergency procedures; and the experience and training of the proposed users.
Review any activity which has been stopped as being a threat to health (F) or property to determine whether a threat actually exists, corrective actions, and conditions under which the activity may be restarted.
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5.2.5 RADIATIONSAFETYC00MITTEE(Cont'd)
Records of each meeting of the Committee shall be prepared and maintained by the Radiation Safety Officer (if the Radiation Safety Officer is not present at a particular Comittee meeting, an assistant to the Radiation Safety Officer shall prepare the record for that meeting). The record shall include the date of. the meeting, persons
.present, items discussed, and all decisions made by the Committee.
The records shall be maintained as part of the Health Physics Log until notification is received from the.NRC that the records may be disposed of.
A current list of persons designated as assistants to the Radiation Safety Officer and as technical specialists shall be maintained in Section 4.2 of the Operations Manual along with a description of each Comittee member's training and experience with radioactive material.
5.2.6 PERSONS AUTHORIZED TO USE AND/0R SUPERVISE USE OF RADIOACTIVE MATERIALS Under the program set up by the department, the radioactive materials may be used by or under the supervision of the Manager of Manufacturing and the Radiation Safety Officer, the assistant (s) to the Radiation Safety Officer, or by a technical specialist. A technical specialist must have a bachelor's degree or equivalent' training and experience relevant to radiation safety and radioactive materials handling judged to be acceptable'for this type of responsibility by the Radiation Safety Committee.
In addition, he must have at least three years of training or experience in the safe handling of radioactive materials and be knowledgeable in the characteristics of ionizing radiation, units of radiation dose and quantities, radiation detection instru-
.mentati7n, and biological hazards of exposure to radiation.
Two levels of supervision will be consulted prior to hiring new l
personnel for the above positions.
5.2.7 PERSONS OCCUPYING DESCRIBED POSITIONS A current listing of all persons occupying positions defined by paragraphs 5.2.1 through 5.2.4 and 5.2.6 above shall be maintained in Section 4.2 of the Operations Manual along with a description of each person's experience, training, and other qualifications.
5.3 DEVELOPMENT OF OPERATING PROCEDURES Written procedures are prepared and/or reviewed by the appropriate immediate function supervisor. Procedures relating to Operations are approved by the Operations Manager, the Radiation Safety Officer, April 1983 16 e MONSANTO RESEARCH CORPORATION e
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5.3 DEVELOPMENTOFOPERATINGPROCEDURES(Cont'd)
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and the Engineered Products Department Manager. 'Should any of these three people feel the procedure being considered is significantly different than procedures presently in use, the procedure is referred to the Radiation Safety Comittee for review and approval.
It is a responsibility of line supervision and management to see that approved procedures are being followed.
5.4 INTERNAL AUDITS OF PERFORMANCE To further insure adherence to the operating procedures, company.
internal audits of performances are performed by the Laboratory Director or a person designated by the Director who is outside the area of Engineered Products.
These audits will be performed yearly. A written report of the audit will be given to the Operations Manager and to the Radiation Safety Committee for their review and action.
Records of each audit I
shall be maintained indefinitely as part of the Health Physics Log.
5.5 CHANGES IN OPERATING PROCEDURES, FACILITIES AND EQUIPMENT Any change in operating procedure must be approved by the Manager of the Engineered Products Department.
If there is any doubt that the changes are within the framework of the license, then the recommended change will be submitted to the Division of Materials Licensing of the NRC for approval.
5.6 AMENDMENTS TO THE NRC LICENSE Any change in our NRC License must be approved by the Manager of the Engineered Products Department. Any request for amendment must be signed by the Opers d ons Manager, the Manager of the Engineered Products Department or the Director of the Dayton Laboratory.
5.7 INSTRUCTION OF NEW EMPLOYEES AND REFRESHER TRAINING FOR PERSONNEL 5.7.1 TRAINING 0F NEW EMPLOYEES IN PROCESS AREA New employees will be given an apprenticeship type training for the handling of radioactive materials. Each new person will work under the guidance of an experienced person for a period of at least two months before he is permitted to work without constant supervision.
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u 5.7.2 REFRESHER TRAINING Training sessions will be held at least quarterly for personnel who are involved in handling radioactive material. The training session shall review the techniques and methods of handling radioactive material with emphasis on health physics aspects.
5.7.3 WORK CERTIFICATION A work certification system is used which requires that each person management (usually the Manufacturing Manager)y Officer and by be certified in writing by the Radiation Safet as approved to perform an operation or class of operations within the controlled areas prior to being permitted to peform that operation or class of operations without a certified person being present. Certification in operations involving radioactive materials constitutes permission to use_ radio-active materials for that operation. Work certification records shall be maintained indefinitely. A typical work certification record form is included in the Appendix to the Operations Manual.
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6.0 EMERGENCIES The licansee has a Radiological Contingency Plan which has been submitted to and approved by the U.S. Nuclear Regulatory Comission; that Plan anJ any amendments thereto shall be considered part of the License.
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~7.0 RADIATION CONTROL 7.1 SPECIFICATIONS FOR FILM BADGES Minimum detection capabilities are as follows:
Area of Detection Beta X or Gamma Neutron Whole Body 40 mrem 20 mrem to 20 mrem to to 1000 500 Rem 50 Rem Rem 1.
Extremity 40 mrem 20 mrem to 20 mrem to to 1000 500 Rem 50 Rem Rem i
7.2 R,;DIATION MONITORING AND CONTAMINATION CONTROL 7.2.1 GENERAL REQUIREMENTS Licensee shall conduct or otherwise provide for radiation monitoring and contamination control in a manner sufficient for compliance with the requirements of all applicable regulatory agencies.
7.2.2 RADIATION MONITORING (A)
Operating personnel shall conduct environmental radiation surveys prior to, during, and after completion of individual work assignments i
involving processing of radioactive materials.
(B)
Personnel shall not undertake work assignments in any area with radiation levels exceeding 100 mrem /hr of penetrating radiation to l
the whole body without approval of the Radiation Safety Officer or j
his assistant.
I (C)
In addition to operating personnel surveillance of radiation levels daring processing of radioactive materials, the Radiation Safety Officer or his assistant shall at their discretion conduct periodic l
spot radiation surveys of process areas to insure compliance with
(
established procedures and/or license conditions, f
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7.2.2 RADIATIONMONITORING(Cont'd)
.(D)
.The Radiation Safety Officer, or assistant, shall for any reason and frequency deemed appropriate for insuring safe operations and compliance with license conditions, conduct independent fomal radiation surveys of any process or area under licensee's control.
LThe purpose of this type survey shall be to determine and record the radiation-levels in and around the facility, and to determine radiation levels in new or unusual operations, or when there has e
been a change of materials.
7.2.3 CONTAMINATION CONTROL (A)
Each sealed source containing byproduct or special nuclear material, other than Hydrogen 3, with a half-life g* eater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months except that each i-source designed for the purpose of emitting alpha particles shall be 4
tested at intervals not to exceed three months.
i (B)
(1) Each sealed source acquired from another person and containing licensed material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for contamination and/or leakage prior to use.
In the l-absence of a certificate from a transferor indicating that a i
test has been made within six months prior to the transfer, the sealed source shall not be put into 'use until tested.
(
(2) Notwithstanding the periodic leak test required by this condition, any licensed sealed source is exempt from such leak tests when the source contains 100 microcuries or less of beta and/or gamma emitting material or 10 microcuries or less of alpha emitting material.
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(3) Except for alpha sources, the periodic leak test required by 7.2.3(A) does not apply to sealed sources that are stored on site and not being used. The sources exempted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within six months prior to the date of use or transfer.
(C)
Each sealed source fabricted by the licensee shall be inspected and tested for construction defects, leakage, and contamination prior to use or transfer as a sealed source.
If the inspection or test reveals any construction defects or 0.005 microcurie or greater of contamination, the source shall not be used or transferred as a sealed source until it has been repaired, decontaminated, reinspected and retested.
April 1983 21 e MONsANTO RESE ARCH CORPORATION e g
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7.2.3 ~
CONTAMINATION CONTROL (Cont'd)
(D)
The test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. The test sample shall be taken from the sealed source or from the surfaces of the device in which the sealed source is permanently or semi-
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permanently mounted or stored on which one might expect contamination to accumulate.
Records'of leak test results shall be kept in unf ts of microcuries and maintained for inspection by the Commission.
e (E)
If the test required by Subsection (A) or (B) of this section reveals the presence of 0.005 microcurie or more of removable contamination, the licensee shall imediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired or to be disposed of in accordance with Commission regulations.
If the source has been transferred from our licensed facility and placed in service and subsequently found to be leaking, an investigation will be made to establish the circumstances and a report shall be filed within 30 days of the test with the Director, Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Comission, Washington, D.C., 20545, describing the equipment involved, the test results and the corrective action taken.
A copy of such report shall also be sent to the Director, Region III, Office.of Inspection and Enforcement, USNRC, 799 Roosevelt Road, Glen Ellyn, Illinois, 60137.
(F)
Operating personnel shall conduct environmental surface contamination surveys prior to, during, and after completion of individual work assignments involving processing of radioactive materials.
(G)
Personnel shall not undertake routine work assignments in any area where removable contamination levels-have been determined to be above established acceptable limits, without approval of the Radiation Safety Officer. Personnel shall report such excessive levels of contamination to the Radiation Safety Officer, or his assistant, for appropriate action.
(H)
In addition to operating personnel surveillance of removable contamination levels during processing of radioactive materials, the Radiation Safety Officer, or his assistant, shall at their discretion conduct periodic spot smear surveys of any area to insure compliance with established procedures and/or license conditions. Complete routine surveys are conducted twice each month.
The Radiation Safety Officer, or his assistant, shall for any reason (I) and frequency deemed appropriate for insuring safe operations and compliance with established procedures and/or license conditions, conduct independent formal contamination surveys of any process or crea under licensee's control.
22 April 1983 e MONsANTO RESEARCH CORPORATION e
(J)-
Contamination Limits:
(1) Licensee shall limit removable contamination in the controlled process area excluding glove and remote handling box interiors to:
2.25 x 10- 9C1/100 cm2 (500 dpm/100 cm ) alpha 2
2 1 x 10-3 9C1/100 cm2 (2200 dpm/100 cm ) beta-gamma (2) Licensee shall limit removable contamination in the controlled support area to:
2 5 x 10 5 pCi/100 cm2(110dpm/100cm) alpha 2
1 x 10 '+ pCi/100 cm2 (220 dpm/100 cm ) beta-gamma (3) Licensee shall undertake appropriate decontamination efforts when levels are detected that exceed established limits including the internal fume hoods.
7.3 SHIELDING 7.3.1 PROVISION Licensee shall provide appropriate shielding materials, and shall require the use of such materials by all personnel actively engaged in processing or handling radioactive material.
7.3.2 USE Licensee shall interpose maximum practical shielding materials in all instances of radiation posing an unwarranted exposure hazard to personnel.
7.3.3 MATERIAL Typical shielding materials normally used shall include, but are not limited to:
iron, steel, lead, benelex, lucite, water, paraffin, concrete, and polyethylene with fire-resistant shielding being used in permanently-shielded installations whenever feasible.
7.4 PROTECTIVE CLOTHING 7.4.1 CLOTHING REQUIREMENTS Licensee shall provide protective clothing to, and shall require the appropriate use of such clothing by, all authorized personnel entering licensee's controlled area.
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7.4.2 CLOTHING PROVISION Such items of protective clothing shall include, but are not limited to: shoes or shoe covers, laboratory coats, trousers, shirts, skirts, blouses, dresses, aprons, gloves, bubble suits, face shields, and respirators.
7.4.3 LAUNDRY REQUIREMENTS (A)
Licensee shall provide a properly identified container for deposit of used protective clothing subject to routine laundering.
(B)
Licensee shall monitor all protective clothing after each use.
Clothing with detectable contamination, excluding shoe soles, shall be decontaminated or discarded. Clothing with detectable contamination will not be sent to the laundry.
7.5 REMOTE HANDLING DEVICES 7.5.1 PROVISION Where radiation exposure rates are expected to exceed 100 mrem /hr the licensee shall provide remote handling devices, and shall require the appropriate use of such devices by all personnel actively engaged in processing or handling radioactive material.
7.5.2 TYPE Typical remote handling devices used shall include, but are not limited to:
tweezers, forceps, tongs, neutron source holders, and articulated tongs.
7.6 RADI0 ACTIVE WASTE The collection, packaging, monitoring, labeling, storage, and disposal of radioactive waste generated by licensee shall be adequately controlled to ensure compliance with applicable NRC regulations. Liquid waste will be solidified in accordance with applicable State and/or Federal regulations pertaining to radio-active waste. The storage and shipping containers shall comply with appropriate regulatory requirements. The packaged waste shall l
be stored in a locked building of fire resistant construction with no combustibles contained in the storage area outside of sealed i
metal or specially constructed containers. The building shall be posted as required by 10 CFR Part 20. Access to the building shall be limited. Licensee shall maintain permanent records of radioactive waste disposal.
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- 7.6 RADIOACTIVEWASTE(Cont'd)
The Radiation Safety Officer is responsible for the safe transfer, packaging, and transport of radioactive waste material. He shall maintain a current set of DOT and NRC regulations concerning the transfer, packaging, and transport of radioactive waste; prior to each shipment of radioactive waste he shall obtain a current set of requirements (license) placed upon the waste disposal firm to be used by the Agreement State in which the materials will be disposed (or by the U.S. NRC if the materials will be disposed of in a non-Agreement State) and a current copy of the requirements of the waste collection contractor to be used, and shall assure that the waste to be shipped complies with all applicable requirements.
The yearly management-controlled internal audits required by Section 5.4 of these License Specifications shall include an audit of all transfer, packaging, and transport activities related to radioactive waste.
In the event that a regular yearly internal audit does not occur within six months following a radioactive waste shipment, a special audit covering waste-related activities shall be performed as otherwise described 'in Section 5.4 for yearly audits.
Water used for certain purposes (such as the laundering of clothing used in the controlled area and water from emergency showers) first goes into a holding tank, is monitored for radioactive material content, and if found to meet the requirements of paragraph 20.303 of 10 CFR Part 20, is pumped into the sanitary sewerage system.
Detailed operating procedures shall be provided to all persons in-volved in any aspect of radioactive waste activities, with attention given to controls on the chemical and physical form of the radioactive materials and on containment integrity of the packaging. The pro-cedures and changes thereto shall be approved by the Engineered Products Manager, the Operation Manager, and the Radioactive Safety Officer.
Initial and periodic training in the DOT and NRC regulatory and other requirements and in the operating procedures related to radioactive waste shall be provided to all personnel involved in waste-related activities.
Records of training dates, attendees, and subject material shall be maintained indefinitely.
7.7 MATERIAL AND EQUIPMENT RELEASE LIMITS 7.7.1 MONITORING License shall monitor materials and equipments for radioactivity prior to authorized release from the controlled area. Such items may include tools, glassware, hardware, assemblies, sub-assemblies.
components, gas bottles, containers, etc.
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7.7.2' LIMITS The following limits of radioactivity shall' apply:
(A)
Beta-gama:
<4.5 X 10-5 uti/100 cm2 removable (100 dpm/100cm2)-
<0.02mr/hrdirect(fixedatsurface)
(B)
Alpha:
9.0 X 10-* 9C1/100 cm2 removable, (20 dpm/100 cm2) 9.0 X 10-* uti direct (fixed at surface) 7.8 INSTRUMENTATION 7.8.1 INSTRUMENT REQUIREMENTS License shall provide personnel with properly maintained and calf-brated radiation detecting instruments for use in perfoming surveys, personnel monitoring, and laboratory analyses.
Instruments provided shall be capable of providing a useful indication of the types of radiation normally encountered, i.e., aplha, beta, gama, or neutron.
7.8.2 PORTABLE INSTRUMENT SPECIFICATIONS (A)
ALPHA MEASURING INSTRUMENTS Alpha survey meters will have an efficiency of at least 25% for alpha radiation of energy greater than 1 Mev.
(B)
BETA-GAMMA MEASURING INSTRUMENTS Beta-Gamma measuring instruments will be avai'able with a combined capability of monitoring over the range of 0.1 mrem /hr to 5000 mrem /hr. Accuracy is to be within 20% of actual value.
(C)
NEUTRON MEASURING INSTRUMENTS Portable neutron measuring instruments will be available capable of indicating over the range of 0.5 mrem /hr to 5 rem /hr with an accuracy of 20% of the actual value.
(D)
MINIMUM NUMBER OF SURVEY INSTRUMENTS A minimum of two (2) instruments of each category described in Paragraphs (A),(B),and(C)aboveshallbeavailable.
7.8.3 AIR MONITORING AND SAMPLING INSTRUMENTATION SPECIFICATIONS (A)
PORTABLE ALPHA AIR MONITORS Portable alpha air monitors shall be of the type which uses an analyzer to detect the isotope of interest, shall be equiped with background subtraction circuits and adjustable alarm points with internal-local alarm and remote contacts, and shall be capable of 26 April 1983 o MoNSANTO RESEARCH CORPORATION e
7.8.3.
PORTABLE ALPHA AIR MONITORS (Cont'd) routinely detecting the M.P.C. (maximum permisable concentration as specified in 10 CFR 20.103, 20.106) for the particular alpha-emitting istotopes likely to be present at the sampling location.
(B)
ALPHA / BETA / galea SAMPLE COUNTING SYSTEM LWipe counting systems shall be of the automatic type which distinguish between alpha and beta-gamma activity, and shall be equiped with background subtraction circuits and/or shielding to maintain low background count levels. The systems shall have sufficient sensitivity ~
to routinely detect the clean area limits specified in Section 7.7.2 above.
(C)
MINIMUM NUMBER OF INSTRUMENTS A minimum of four (4) portable alpha air monitors and one (1) alpha / beta / gamma counting system meeting the specifications of 1
paragraphs (A) and (B) above, respectively, shall be available.
7.9 BI0 ASSAY 7.9.1 GENERAL REQUIREMENTS License shall establish, maintain, and administer a bioassay program for all personnel who handle, process, or are exposed to radioactive materials within the controled area.
7.9.2 MAXIMUM PERMISSIBLE BODY BURDEN Maximum permissible body burdens shall be limited in accordance with the " Recommendations of I.C.R.P., Report of Committee II, on Permissible Dose for Internal Radiation".
7.9.3 ACCEPTABLE PRACTICES (A)
Provisions shall be maintained for routine or special collection and analysis 'of bioassay samples such as urine, feces, or sputum.
(B)
Routine bioassay samples shall consist of 24-hour urine voids, and shall normally be collected off-site or in an area known to be free of radioactive contamination.
During the period of collection the individual shall be restricted from working in areas or under conditions in which further exposure may occur.
(C)
Routine Urine Sample Frequency:
(1) Radiation Workers & Supervisors - Routine frequency shall be, as a minimum, once per quarter for employees who work routinely 27 April 1983 o MONSANTO RESEARCH CORPORATION e
7.9.3 (Cont'd)
(1) (Cont'd) with isotopes and semiannually for supervisors, and other persons who frequently enter materials handling areas, but who do not actually perform operations with unsealed forms of materials.
(2) The type and number of samples, type of material analysis, and sampling frequency required for all personnel shall be determined by the Radiaiton Safety Officer.
(D)
Special bioassay procedures shall be employed to evaluate possible disposition from known or suspected accidential exposures.
Fecal and/or lung counting shall be performed for such exposures, as well as for follow-up evaluation of confirmed routine urinalysis, if evidence indicates that exposure may have been to relatively in-soluable forms of radioactive materials.
(E)
Action levels and lower detectable limits for routine urine samples.
Isotope Lower Detectable Limit Action Level Pu-238 0.03 0.02 dpm/ sample 0.2 dpm/ sample Pu-239 0.03 2 0.02 dpm/ sample 0.2 dpm/ sample Cf-252 0.03 2 0.02 dpm/ sample 0.2 dpm/ sample Am-241 0.03 1 0.02 dpm/ sample 0.2 dpm/ sample Po-210 0.15 dpm/ liter 20 dpm/ sample By-products 0.1 dpm/ml Each case considered individually By-product samples will be analyzed for gross beta minus K-40.
If the net beta is greater than 0.5 dpm/m1, the seperated sample will be pulse height analyzed.
If gama pulse height analysis indicates a need for chemical separation of a nuclide, licensee will authorize processor to chemically spearate and determine the amount of nuclide present in the urine.
Resampling and investigation as to the possible source, cause and magnitude of the exposure is required when action levels are exceeded; excluded are persons who routinely excrete any of these materials above the depositions. Mandator.y resampling for such persons shall be performed if routine urinalysis indicates possible additional intake.
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7.9.3 (Cont'd)
(F)
License will obtain expert bioassay consultation and assistance for cases of known or suspected significant deposition.
(G)
License will obtain lung or whole body counting of personnel for cases of known or suspected significant deposition.
7.10 POSTING AND CONTROL 7.10.1 ACCESS TO CONTROLLED AREAS Normal entry into the controlled areas is through an air lock into the Support Area (see drawing number A2608-L-08, Operation Manual).
The outer door of the airlock is lockable from the outside by means of either a key-operated lock or an electronic combination lock. All other doors into the Support Area and the Controlled Process Area, and all gates through the fence surrounding the controlled area, are lockable from the outside by means of key-operated locks. All doors and gates to the controlled area are kept locked with key-operated locks except when one or more of the persons authorized to use or supervise the use of radioactive materials (Section 5.2.6) is on site, during which times the key lock on the outer door to the air-lcck may be unlocked with access control being maintained by the electronic combination lock.
Persons certified as qualified to work inside the controlled area without ininediate supervision are given
-the combination to the electronic lock, and may enter the controlled area at will during times when the key-lock is open. The combination to the electronic combination lock is changed periodically at the discretion of the Radiation Safety Officer. Other doors and gates into the controlled area are opened only when performing operations requiring them to be open, and only when a certified person is present. All doors into the controlled area are equipped so that they lock automatically when closed.
7.10.2 POSTING The outside of the outer airlock door to the Support Area is contin-uously posted with " Caution Radioactive Material" and " Caution Radioactive Area" signs, and with a sign specifying the minimum protection clothing requirements for entry. The fence surrounding the controlled area is posted with " Caution Radiation Area" and other precautionary signs. The outside of all doors into the controlled area which may be unlocked from the outside are posted with
" Caution Radiation Area" and other precautionary signs. All caution signs contain the radiation symbol as defined by paragraph 20.203 of 10 CFR Part 20. Additional postings are made inside and outside of the controlled areas as specified by paragraph 20.203 of 10 CFR Part 20 when conditions exist which require such posting.
April 1983 29 e MONSANTO RESEARCH CORPOR ATION e
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8.0 DESIGN FEATURES - AIRBORNE CONTAMINATION CONTROL 8.1 INTER-AREA FLOW DESIGN
^
Ventilation equipment in Engineered Products is designed to provide an air. flow from areas of lesser contamination to areas of poten-tially higher contamination.' Drawings C2608-L-01, A2608-L-02 through-
-05, B2608-L-06, A2608-L-07. C2608-L-08, A2608-L-09 and -10, and-D6901-AA-01, sheets 6 and 7 (in the Operations Manual) show features of air handling systems and layout of air sample points.
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8.2 ENCLOSURES The following system of enclosures is used in the handling of materials:
(A)
Glove boxes: Constructed of corrosion resistent sheet metal with safety glass windows. All seams are welded or gasketed to retain materials within the enclosures. Glove boxes are held at a negative pressure of s1.0 in H 0.
Entrance into the glove box is made through 2
a double door air lock system. Boxes are provided with glove ports i
for working within the enclosures. Where appropriate the boxes are surrounded with shielding to reduce radiation levels. The atmosphere within the box is vented through a closed air filtration system. Air l
flow through the box is minimal and results from leakage only when the box is closed. However, the box filtration system is designed g
for an air flow of 50 cfm through an 8" glove port should the port be P
opened.
(B)
Remote boxes: Constructed of corrosion resistent metal with safety glass, leaded glass, water-filled, or oil-filled windows or windows composed of two or more of these types. Remote manipulators are provided for handling high-level sources; all work on such sources is accomplished from behind shielding adequate for attenuating radiation to the operator to 60 mrem /hr or less.
Set-up and mainte-nance operations, and operations involving low-level sources may be accomplished through glove ports.
Remote boxes are operated at a negative pressure of $1.0 in. H 0.
Entrance into remote boxes is 2
made through double door air lock systems. The atmosphere within the remote boxes is vented through a closed filtration system. All penetrations are designed such that air flow is inward through the box and out the filtration system.
Filtrations: Air exhausted ' om each glove box or shielded box (C) passes through two absolute t "ters in series, each with an efficiency of 99.9% for 0.3 micron part les. The systems consist of a primary filter at each box connected
/ metal and vinyl covered flexible ductwork to a secondary filtt. at the exhaust stack. Filters, gaskets, and fittings'on the filter are in compliance with MIL-F-51068C specification. The ductwork is made up of 90% metal pipe and there-fore is quite fire resistant.-
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8.2 (Cont'd)
(D)
Replacement limit for filters: In place testing of the final high efficency exhaust ventilation system filter shall be perfomed after each change of the filter and, as a minimum annually thereafter using the " cold" DOP test. The acceptance efficiency for a filter using the standard pol (countmediandiameterofabout
.0.8 micron) y-disperse DOP aersol shall be 99.95 percent.
(E)
In normal operation, when dampers are installed past the primary filter to facilitate changing of filters, the dampers are completely open.
(F)
Box pressure differential:
In normal operation, the boxes are kept at a negative pressure differential of 1-inch of water. This differential is produced by a fan on the roof that exhausts into a 50-foot high stack. The negative pressure on the boxes is controlled by an air-operated damper, Minneapolis-Honeywell pneumatic modulating motor #MP903B1011, that bleeds air into the stack fan past the final filter. The control unit, Minneapolis-Honeywell, PP904A, static pressure regulator, is set to keep the air differential at a pressure of 1-inch 1 1/4-inch of water.
(G)
Exhaust air from dry boxes: Sampled upstream from the final filter at the rate of 20 liters per minute for the entire 24-hour per day /7 days per week. The filter paper through which the sample is pulled is then counted in a proportional counter to determine the concen-tration of radioactive material in the exhaust air.
Records shall be kept of these air samples. The records will be made available upon request by the N.R.C.
(H)
Operational limitation: The use of volatile, flamable liquids and flamable gases are severely restricted. They may be used only with the approval of the Manager of Manufacturing and the Radiation Safety Officer or their alternates. After their use, the enclosure must be purged with air for 15 minutes. This action is to remove the chance of pockets of explosive mixtures being trapped and then ignited inside a closed area.
8.3 AIRBORNE CONTAMINATION CONTROL The airborne contamination control design features include:
(A)
Routine Sampling: The licensee is maintaining a routine sampling program which provides for the determination of airborne concen-trations of radioactivity to which personnel have or may be exposed.
April 1983 31 o MONSANTO RESE ARCH CORPOR ATION e
8.3 (Cont'd)
(B)
Sampling Methods: The air sampling system consists of a type F2-AF-Roots Connerville blower to supply the vacuum, and a series of copper tubing to the sampling points. Each sampling point has a Gelman sampling head, an accurate flow meter, and flow adjusting valves. Each sample point is individually calibrated to the desired flow rate. The air sampling system is equiped with a timing device for automatic daily start-up and shut-down.
The filters are changed on a daily basis just prior to facility shut-down. Filters are changed for each of the room air samplers.
Location of air samplers are shown in diagram C2608-L-08 (in the Operations Manual).
(C)
Limits: Licensee, in no case, plans or intends for personnel to be exposed to airborne concentrations in excess of the limits specified in Appendix B, Table 1,10 CFR 20.
All general and stack air samples are counted three (3) times on the following schedule:
Count Time Action Level Note 1st end of sample period 1.5 X 10-10 pCi/ml(a)
(1) 2nd next work day 1/2 applicable MPC for one day or /4 applicable MPC on (2) l two successive days The activity recorded in the permanent records is that obtained from a third count made seven days after the end of the sample period.
If a sample exceeds the action level an investigation is made to determine the cause and corrective steps are taken immediately. The concentration determined on the third count is used for air sample records as the actual concentration above natural background (radon and thoron).
Note:
1.
This action level includes natural radioactivity up to sl.4 x 10-10 2.
Applicable M.P.C. (maximum permissable concentration) is deter-mined based on the specific isotopes in the area sampled, and 10 CFR 20.103, 20.106.
April 1983 32 o MONSANTO RESE ARCH CORPOR ATION e a
8.3 (Cont'd)
(D)
Records and Reports:
Individual exposures to airborne concentrations of radioactive material are determined in accordance with the re-quirements of 10 CFR 20.103. Reports of over-exposure of personnel are made in accordance with the requirements of 10 CFR 20.405.
Management is immediately made aware of any such required report.
Permanent records are on file for all daily air samples.
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9.0 RECEIPT AND SHIPMENT OF RADIOACTIVE MATERIALS 9.1 RECEIPT OF PACKAGES CONTAINING RADI0 ACTIVE MATERIALS Packages containing radioactive material are normally delivered to the licensee's site during normal working hours. A guard is present on site at all times; should a carrier arrive at the site to deliver a package containing radioactive materials during other than normal working hours, the guard will call persons appropriate to receive the shipment.
In the event that a package containing greater than Type A quantities of radioactive material (as defined by Paragraph 20.205, 10 CFR Part 20) is to be picked up by the licensee at a carrier's terminal, arrangements shall be made to receive notice of the arrival of the package at the time of its arrival, and the package shall be picked up from the tenninal expeditiously upon receipt of notification from the carrier of its arrival.
Upon receipt of a package containing radioactive material, the external surfaces of the package shall be monitored for radioactive contamination by wipe testing except that packages containing no more than exempt quantities of radioactive materials as specified in Paragraph 20.205 of 10 CFR Part 20, packages containing only radioactive material as gasses or in special form, packages contain-ing only radioactive material in other than liquid form and not exceeding the Type A quantity limit, and packages containing only radionuclides with half-lives less than 30 days and a total quantity of no more than 100 mil 11 curies, are excluded from the external contamination monitoring requirement.
If removable radioactive contamination in excess of 0.01 microcuries per 100 square centimeters of package surface is found on the external surfaces, both the final delivering carrier and the appropriate Regional Office of the Nuclear Regulatory Commission as specified in Appendix D of 10 CFR Part,20 shall be immediately notified.
Upon receipt of a package containing quantities of radioactive material in excess of Type A quantities (other than those transported by exclusive use vehicle), the radiation levels external to the package shall be monitored.
Both ganna and neutron radiation shall be measured at the surface of the container and at three feet from the container surface.
If the total radiation level at the surface is found to be greater than 200 millirem per hour, or if the total radiation level at three feet from the surface is found to be greater than 10 millirem per hour, both the final delivering carrier and the Director of the appropriate Regional Office of the NRC shall be immediately notified.
April 1983 34 e MONSANTO RESEARCH CORPORATION e
9.1 RECEIPTOFPACKAGESCONTAININGRADI0ACTIVEMATERIALS(cont'd)
' The monitoring actions required above shall both be performed as soon as practicable after receipt, but no later than three hours after the package is received on site if received during normal working hours, or eighteen hours if received outside of normal working hours.
Required notifications shall be made to the final delivering carrier by telephone or telegraph, and to the appropriate Regional Office of the NRC by telephone and by telegraph, mailgram or facsimile.
Packages containing radioactive material shall be opened following procedures established by the Radiation Safety Officer.
9.2 SHIPMENT OF RADIOACTIVE MATERIALS Shipments of radioactive materials from Engineered Products shall be made under 10 CFR Part 71, Paragraphs 71.5, 71.5a 71.5b, 71.6, 71.7, 71.9, and 71.12. All shipments from Engineered Products are made in D.O.T. Specification Containers or in packages for which a license, Certificate of Compliance or other approval has been issued by the Nuclear Regulatory Commission..The licensee has a Quality Assurance Program which has been submitted to and approved by the Nuclear Regulatory Comission as satisfying the requirements of Section 71.51 of 10 CFR Part 71 (approval number 0248), and complies with the documentation and notification requirements of Paragraph 71.12 of 10 CFR Part 71.
For these conditions of shipment, a special license under 10 CFR Part 71 is not necessary.
l.
All sources containing radioactive material shall, prior to removal from the licensee's facilities, have a label permanently marked on the source surface, or have a label attached to the source or source holder, which shall identify the radioactive contents and contain l
the words, " CAUTION RADI0 ACTIVE MATERIAL" or "DANi.R RADI0 ACTIVE i
MATERIAL". Methods of marking labels on source surfaces include but are not limited to engraving, chemical etching, electroetching, vibratool marking, stamping, and embossing. Labels attached to sources or source holders include'but are not limited to metal tags attached by means of a wire, cable, or chain, and metal foil labels attached by means of adhesive. Source holders upon which the label may be marked or to which the label may be attached include but are not limited to devices in which the source will remain during use, and metal containers in which one or more sources are located during shipment (i.e., crimp-sealed metal cans, DOT Specification 2R inner containers, screw-top metal vials).
April 1983 35 lMONsANTO RESEARCH CORPORATION e
e 9.2 SHIPMENTOFRADI0ACTIVEMATERIALS(Cont'd)
The sources prepared to meet 10 CFR 70.39 specification shall be packed in primary containers (typically, screw-top glass jars) which bear labels similar to the following example, cAuvioN N
M E
g=ll.
h, u
l*.
gr j e.;7 a.=4"*c*=nnunon
~
o AM0HT nonmin..--
BATE Handling instructions will accompany these sources. A sample is included in Section 8 of the Operations Manual.
The transportation of NRC-licensed material shall be subject to all applicable regulations of the Department of Transportation and other s
agencies of the United States having jurisdiction.
When Department of Transportation regulations in Title 49, Chapter 1, Code of Regulations, Parts 173-179, are not applicable to shipments by land or NRC-licensed material by reason of the fact that the transportation does not occur in interstate or foreign commerce, (1) the transportation snall be in accordance with the requirements relating to packaging of radioactive material, marking and labeling of the package, placarding of the transporatation vehicle, and accident reporting set forth in the regulations of the Department of Transportation in 49 CFR Part 173, " Shipper," and CFR Part 177,
" Regulations Applying to Shipments Made by Way of Common, Contract or Private Carriers by Public Highways," and (2) any requests for l
modifications or exceptions to those requirements, and any notiff-cations referred to in those requirements shall be filed with, or I
made to, the Nuclear Regulatory Commission.
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i April 1983 36 l
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10.0 WORK LIMITATIONS (A)
No person shall work alone in the controlled area with " normal form" radioactive material.-
(B)
No more than 100 pCi of unsealed radioactive material shall be processed in a fume hood in the controlled process area.
k l
April 1983 37 s MONSANTO RESEARCH CORPORATION e
J 11.0 PROCESS LIMITS, The following quantities of radioactive material may be in process, i.e., out of storage and unencapsulated, at any one time:
(A) 5 Ci of cobalt-60, or a quantity of other beta-ganna emitting isotope producing an equivalent amount of radiation.
(B) 5 milligrams of Cf-252.
(C) 250 Ci of an alpha emitting isotope.
April 1983 38 o MONSANTO RESEARCH CORPORATION e
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12.0 MAXIMUM PERMITTED QUANTITIES OF RADI0 ACTIVE MATERIAL PER SOURCE CAPSULE (A) 5 Ci of cobalt or sources producing an equivalent amout of radiation.
(B) 5 milligrams of Cf-252.
(C) 50 Ci polonium beryllium neutron source, or polonium and other target materials producing an equivalent amount of radiation.
(D) 250 Ci of an alpha emitting isotope.
h l
l April 1983 39 i
[
e MONSANTO RESEARCH CORPORATION e
'1 L
OPERATIONS MANUAL Demonstration of Monsanto Research Corporation's Compliance to License Specifications a
4 h
l o MONSANTO RESEARCH CORPOR ATION e l
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OPERATIONS MANUAL'
-TABLE OF CONTENTS
'l.0 AUTHORIZED ACTIVITIES 1.1 SCOPE OF OPERATIONS MANUAL 1.2
. CHANGES TO THE OPERATIONS MANUAL 2.0
~ LOCATIONS OF USE 2.1 PRINCIPAL PLACE OF BUSINESS 2.2 SOURCE RADIOGRAPHY
^
2.3 SHOWS AND EXHIBITIONS 2.4 CUSTOMER'S LICENSED FACILITIES 7
2.5 STORAGE OF SOURCES OFF-SITE 2.6 FIRE PROTECTION FOR ENGINEERED PRODUCTS 2.6.1 AUTOMATIC SYSTEMS 2.6.2 MANUAL FIRE PROTECTION APPARATUS 2.6.3 GLOVE BOX PROTECTION 2.6.4 LARGE REMOTE BOX PROTECTION 2.7 ENGINEERED PRODUCTS PROCESSING STORAGE AREA
.2.7.1 CONTROLLED SUPPORT AREA 2.7.2 CONTROLLED PROCESS AREA 2.7.3 WASTE STORAGE AREA 3.0 PREPARATION OF PLUTONIUM ALPHA CLAIBRATION SOURCES 4.0 GENERAL ADMINISTRATIVE ORGANIZATION 4.1 GENERAL 4.2 ORGANIZATIONAL RESPONSIBILITIES 4.3 DEVELOPMENT OF OPERATING PROCEDURES 4.4 INTERNAL AUDITS OF PERFORMANCE 4.5 CHANGES IN OPERATING PROCEDURES 4.6 AMENDMENTS TO NRC LICENSE 4.7 INSTRUCTION OF NEW EMPLOYEES AND REFRESHER TRAINING FOR PERSONNEL 4.7.1 IND0CRINATION OF NEW EMPLOYEES 4.7.2 TRAINING OF NEW EMPLOYEES IN PROCESS AREAS 4.7.3 REFRESHER TRAINING 4.7.4 WORK CERTIFICATION A pril 1983 i
e MONSANTO RESEARCH CORPORATION e
OPERATIONS MANUAL TABLE OF CONTENTS (CONT'D) 4.8 RADIATION SAFETY COMMITTEE 5.0 EMERGENCIES 5.1 RADIOLOGICAL CONTINGENCY 5.1.1 GENERAL 5.1.2 EMERGENCY PLAN OBJECTIVES 5.1.3 EMERGENCY ASSUMPTIONS 5.1.4 ADMINISTRATIVE AUTHORITY 5.2 EVACUATION ROUTES, ASSEMBLY AREAS, PERSONNEL INSTRUCTIONS, EVACUATION DRILLS 5.2.1 PERSONNEL INSTRUCTIONS 5.2.2 EVACUATION DRILLS 5.2.3 UNPLANNED EVACUATIONS 5.2.4 RECORDS 5.3 EMERGENCY PERSONNEL TRAINING 5.3.1 TRAINING 5.3.2 EXCERISES 5.3.3 RECORDS 5.4 ASSEMBLY POINT, EMERGENCY EQUIPMENT AND SUPPLIES, PERFORMANCE CRITERIA, EQUIPMENT MAINTENANCE 5.4.1 SELECTION OF EMERGENCY EQUIPMENT 5.4.2 PERFORMANCE CRITERIA 5.4.3 EMERGENCY EQUIPMENT AND SUPPLIES
- 5. 5 ON-SITE EMERGENCY FIRST-AID AND PRELIMINARY DECONTAMINATION 5.5.1 MEDICAL DISPENSARY 5.5.2 MEDICAL STAFF 5.5.3 PROTECTIVE ACTIONS AND EXPOSURE CONTROL 5.6 HOSPITALS, PHYSICIANS, AND AMBULANCE SERVICES 5.6.1 PHYSICIANS 5.7 EXPERT OFF-SITE CONSULTANTS 5.8 RADIOLOGICAL CONTINGENCY MEASURES
- 5. 9 RE-ENTRY CRITERIA F0LLOWING EMERGENCY EVACUATION ii April 1983 e MONSANTO RESEARCH CORPORATION e L
OPERATIONS MANUAL TABLE OF CONTENTS (CONT'D) 5.10 DAYTON FIRE AND POLICE DEPARTMENT ORIENTATION 5.10.1 FIRE DEPARTMENT 5.10.2 POLICE DEPARTMENT 5.11 0FF-SITE EVACUATION AND CIVIL AUTHORITY AGREEMENTS 5.12 PROVISIONS FOR MAINTAINING EMERGENCY PLANS, PROCEDURES, AND LISTS OF PERSONEEL UP-TO-DATE 5.13 REPORTS 5.14 PUBLIC INFORMATION DURING EMERGENCIES 6.0 RADIATION CONTROL 6.1 PtRSONNEL MONITORING 6.1.1 GENERAL REQUIREMENTS 6.1.2 RECORDS 6.1.3 REPORTS 6.1.4 ESTIMATED EXPOSURES 6.1. 5 SPECIFICATIONS FOR FILM BADGES 6.1.6 TARGET LEVELS-FOR WHOLE-BODY DOSE 6.2 RADIATION MONITORING AND CONTAMINATION 6.2.1 GENERAL REQUIREMENT 6.2.2 RADIATION MONITORING 6.2.3 CONTAMINATION CONTROL 6.3 SHIELDING 6.3.1 PROVISION 6.3.2 MATERIALS AND USE 6.4 PROTECTIVE CLOTHING 6.4.1 CLOTHING REQUIREMENT 6.4.2 CLOTHING PROVISION l
6.4.3 LAUNDRY REQUIREMENTS 6.5 REMOTE HANDLING DEVICES 6.5.1 PROVISION 6.5.2 TYPE April 1983 e MONSANTO RESEARCH CORPOR ATION e L
OPERATIONS MANUAL TABLE OF CONTENTS (CONT'D) 6.6 RADI0 ACTIVE WASTE 6.6.1 COLLECTION AND PACKAGING 6.6.2 MONITORING AND LABELING 6.6.3 STORAGE AND DISPOSAL 6.7 MATERIAL AND EQUIPMENT RELEASE LIMITS 6.7.1 MONITORING 6.7.2 LIMITS FOR ITEMS RELEASED TO NON-RESTRICTED AREAS 6.8 INSTRUMENTATION 6.8.1 INSTRUMENT PROVISIONS 6.8.2 PROTABLE INSTRUMENT SPECIFICAITONS 6.8.3 LABORATORY INSTRUMENTS 6.8.4 INSTRUMENT SURVEILLANCE 6.9 BI0 ASSAY 6.9.1 GENERAL REQUIREMENT 6.9.2 MAXIMUM PERMISSIBLE BODY BURDENS 6.9.3 ACCEPTABLE PRACTICES 7.0 DESIGN FEATURES - AIRBORNE CONTAMINATION CONTROL 7.1 INTER-AREA FLOW DESIGN 7.2 ENCLOSURES 7.3 AIRBORNE CONTAMINATION CONTROL 8.0 RECEIPT AND SHIPMENT OF RADI0 ACTIVE MATERIALS 8.1 RECEIPT OF PACKAGES CONTAINING RADI0 ACTIVE MATERIALS 8.2 SHIPMENT OF RADI0 ACTIVE MATERIALS 9.0 RANGE OF POSTULATED ACCIDENTS 10.0 STANDARD OPERATING PROCEDURES 10.1 GENERAL RULES OF OPERATION 10.2 TYPICAL PROCEDURES FOR HANDLING RAID 0 ISOTOPES IN HOT AREA 10.2.1 OPENING 0F RECEIVED RADI0IS0 TOPE 10.2.2 HIGH LEVEL BETA AND GAMMA SOURCES 10.2.3 ' POLONIUM-BERYLLIUM SOURCES 10.2.4 PLUT0NIUM-BERYLLIUM SOURCES iv April 1983 e MONSANTO RESEARCH CORPORATION e t
4 OPERATING-MANUAL TABLE OF CONTENTS (CONT'D) 10.2.5 AMERICIUM-BERYLLIUM SOURCES 10.2.6 ret 10 VAL OF CALIFORNIUM-252 RAW MATERIAL FROM SHIPPING CONTAINER 10.2.7 PRIMARY ENCAPSULATION OF CALIFORNIUM-252 10.2.8 SECONDARY ENCAPSULATION OF CF-252 10.2.9 FACILITY SAFETY ANALYSIS FOR NEUTRON SOURCES UP TO 5 MG CF-252 AND 250 CI 0F PU-238 OR AM-241 y
April 1983 e MONSANTO RESEARCH CORPORATION e
OPERATIONS MANUAL FOR MONSANTO RESEARCH.0RPORATION ENGINEERED PRODUCTS DEPARTMENT 1.0 AUTHORIZED ACTIVITIES The types of activities authorized include: manufacture, development, distribution of radiation sources and devices containing radioactive material. Also installation, removal, servicing and wipe testing of sealed sources at licensed locations away from the licensee's location..In addition, the licensee designs, manufactures, 4
uses, and sells shipping containers for radioactive materials.
Pursuant to Section 70.39.of 10 CFR Part 70, manufacture of calibration and/or reference sources containing plutonium for 4
distribution to persons generally licensed pursuant to Section 70.19 ~
of 10 CFR Part 70 is authorized as described in Sections 4.0 and 9.0 of these License Specifications.
Pursuant to Section 20.105(a) of 10 CFR Part 20, production of radiation levels in unrestricted areas as specified in Section 3.5 of these License Specifications is authorized.
1.1 SCOPE OF OPERATIONS MANUAL The Operations Manual describes the methods, management structure and procedures, and facilities established to assure,that activities are carried out in compliance with the License Specifications.
It contains information which may be expected to change over the life of the license, such as the names of individuals in specific positions, facility details, and general operational procedures.
1.2 CHANGES TO THE OPERATIONS MANUAL Changes may be made in the Operations Manual without prior approval of the Nuclear Regulatory Commission if the changes are such that compliance with the License Specifications remains assured.
Each such change must be approved by the Radiation Safety Committee, and a record of each change and approval will be maintained as long as the license remains in effect.
April 1983 40 e MONSANTO RESE ARCH CORPORATION e
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1 2.0 LOCATIONS OF USE 2.1 PRINCIPAL PLACE OF BUSINESS Monsanto Research Corporation, Dayton, Laboratory, 1515 Nicholas Road, Dayton, Ohio 45407. Engineered Products shall use Room 3 through 14 of Building 2 for manufacture, development and distribution of the authorized materials (map of plant and map of area on pages that follow). Waste materials will be stored in Building 7 until transfer out of plant for disposal.
2.2 SOURCE RADIOGRAPHY Sealed radioactive sources that meet special form requirements may be transported to properly licensed facilities for radiographic 4
examination. The conditions of transport must be in accordance with Department of Transportation and NRC regulations. The handling of such sources will be by Engineered Products personnel only, and under the supervision of any of the competent technical personnel listed in 4.2 of the Operations Manual.
2.3 SHOWS AND EXHIBITIONS Shows and exhibitions in "non-agreement" states. Any source displayed shall contain less than a large quantity of radioactive material in special form. The source capsule or holder must bear identification as to model number, isotope, amount of isotope, and bear the words
" CAUTION, RADI0 ACTIVE". The radiation levels from the display shall conform to the requirements of 10 CFR 20.105. Since radioactive materials would be on display for periods of less than eight hours, the radiation level at any location where an individual could continuously occupy is limited to 2 mrem /hr.
In the event that sources are to be displayed for periods of eight or more hours, the radiation levels will be further limited as required by 10 CFR 20.105.
The sources will be displayed only in the presence of or under constant 1
surveillance of Engineered Products personnel. When not on display, the sources will be kept in their locked shipping container.
(See Section 2.5.)
2.4 CUSTOMER'S LICENSED FACILITIES Customer's licensed facilities in "non-agreement" states. Sealed radioactive sources may be installed, removed, serviced, or wipe tested within a customer's licen,2d facility by any of the competent technical personnel listed in 4.2 of the Operating Manual.
April 1983 41 e MONSANTO RESE ARCH CORPOR ATION e
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2.5 STORAGE OF SOURCES OFF-SITE Sealed sources stored at locations other than the location specified in Item 2.1 above, under authority of this license, shall be securely housed in a shielded container which is either stored in a secure area under the sur'veillance at all times of security personnel or stored in a general storage area with the container being locked and security sealed with access controlled at all times. The internal shielding of the storage container will be such that the external dose rate is less thsn 0.5 mrem /hr. at the surface. In the event of extended storage of 5 or more weeks, the radiation levels will be further limited as required by 10 CFR 20.105. 2.6 FIRE PROTECTION FOR ENGINEERED PRODUCTS 2.6.1 AUTOMATIC SYSTEMS All the rooms used for processing of radioactive materials are protected with automatic sprinkler systems continually monitored by an electronic security service. In the event of an alarm during working hours, the service notifies the Monsanto Research Corporation operator, who in turn notifies a predetermined list of key plant personnel whenever a water flow is detected. During non-working hours; that is, holidays, nights, and weekends, the service notifies the Monsanto guard on duty who in turn calls persons on the emergency call list for instructions and assistance. There are two systems -- one for alarming a " cold" area fire and a second for alarming a " hot" (high radiation) area fire. Each system contains several alarm stations which identify specific areas. The systems are tested monthly by causing water flow and verifying the event at the electronic monitoring station. The test is performed by security service personnel. In addition, our remote box designed to handle up to 5 mg of Cf-252 is equipped with its own autoinatic fire extinguishing system. 2.6.2 MANUAL FIRE PROTECTION APPARATUS The following is a list of available fire protection equipment and its location: Type Location 5 lb. CO2 extinguisher Inside Room 3, near door 15 lb. CO2 extinguisher Inside Room 4 15 lb. CO2 extinguisher, x 2 Inside Room 7A 15 lb. CO2 extinguisher Outside Room 8 17 lb. Dry chemical extinguisher Outside Room 8 April 1983 47 e MONSANTO RESE ARCH CORPOR ATION e
2.6.2 MANUAL FIRE PROTECTION APPARATUS (Cont'd) Type Location 15 lb. CO2 extinguisher Outside Room 11 Fire Blanket Outside Room 11 & Room 7 15 lb. CO2 extinguisher Outside Room 13 Each extinguisher is checked monthly to see that seals are intact and the extinguishers are ready for use. Each extinguisher is weighed yearly to check its contents. 2.6.3 GLOVE BOX PROTECTION The glove boxes shall be protected externally by the sprinkler systems. The combustibles allowable in the glove boxes shall be severely limited to reduce the possibility of fire..The combustible wastes generated in processing shall be stored in closed metal containers until removal. Plutonium metal and other pyrophoric forms of radioactive material shall be maintained under an inert atmosphere except under the following conditions: Material is in process and personnel are in attendance. Each glove box in use shall contain a manually-operated hand fire extinguisher containing halon gas, except that if the glove box contains materials which may adversely react with halon gas, other appropriate extinguishing means will be provided. 2.6.4 LARGE REMOTE BOX PROTECTION The large remote box (north part of Room 6) shall be protected as described in Section 2.6.3 above, except that it shall contain an automatic halon system with external manual trips in place of the hand-held halon unit. The automatic system shall have an override so that it may be inactivated during periods when the box contains materials which may adversely react with halon gas. 2.7 ENGINEERED PRODUCTS PROCESSING STORAGE AREA 2.7.1 CONTROLLED SUPPORT AREA Those processes which involve handling of sealed or packaged radioactive materials, preparation of non-radioactive assemblies, and shipping are accomplished in Rooms 3, 4,10,11,13 and 14 of Building 2. The building construction consists of the following: 1 April 1983 48 i e MONSANTO RESEARCH CORPORATION e m......... _. -,_4 ..-:2.. i '
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.. ~ ~,.. 2.7.1 CONTROLLEDSUPPORTAREA(Cont'd) Walls: Poured concreta (one foot, one inch thick), walls with interior lined with glazed tile. Windows have been removed and filled in with eight inch concrete blocks. Floor: Six inch thick poured concrete reinforced. Roof: Concrete beams and roof deck with built-up asphalt roof, all covered by a wood-truss peaked roof. 2.7.2 CONTROLLED PROCESS AREA Those processes which involve the encapsulation of radioactive materials or handling of raw materials are accomplished in Rooms 6, 7, 7A, 8, and 9 of Building 2. The building construction consists of the following: Walls: Room 6, 8, 9, Steelox wall panels with insulation and masonite interior panels. Room 7 Steel Frame, Steelox wall panels with insulation and dry wall. Room 7A Wood Frame, Steelox wall panels, insulation, and dry wall. Floor: Room 6, 7, 8, 9, Six inch reinforced concrete. Room 7A, Eight inch reinforced concrete. Roof: Room 6, 8, 9, Four inch wide 18 gage Steelox roof panels, 3-5/8 inch Rockwool insulation, wood sheating and built-up roofing. A wood-truss peaked roof has been added above the roof panels. Room 7, Wood and steel frame, steel pan, insulation board, tar paper and tar. Interior ceiling is dry wall. Room 7A Wood frame and steel sheet metal. Dry wall interior ceiling. Fence: Chain-link, 7 feet high around manufacturing area creating restricted access area. 2.7.3 WASTE STORAGE AREA Radioactive waste material is properly packaged and stored in Building 7 while awaiting shipment to a commercial site. Building 7 is a poured, reinforced concrete bunker, built into the incline on the east side of Building 2. April 1983 49 e MONSANTO RESEARCH CORPOR ATION e
2.7.3 WASTE STORAGE AREA (Cont'd) ~ The door to Building 7 is within the fenced restricted access area surrounding the manufacturing portion of Engineered Products and is kept locked. Any combustible material stored in Building 7 must be kept in sealed metal or specially constructed fire resistent containers. 50 e MONSANTO RESEARCH CORPORATION e
3.0 PREPARATION OF PLUTONIUM ALPHA CALIBRATION SOURCES Calibration sources to meet 10 CFR 70.39 specifications are prepared by deposition of acid solution containing plutonium onto a one inch diameter by 0.030 inch thick stainless steel disc. The material is i then affixed by firing to a red heat. This source shall be our Model No. MRC-A-Pu,-SS. These sources are subjected to a leak test i prior to transfer to another person. The leak test consists of a dry wipe, a wet wipe, and then a dry wipe. The wet wipe consists of a tissue moistened with distilled water. Any wipe in excess of 0.005 microcuries is cause for rejection of the source. t s 51 e MONSANTO RESEARCH CORPOR ATION e
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- n.... n 4.0 GENERAL ADMINISTRATIVE ORGANIZATION 4.1 GENERAL Name of Organization:
Engineered Products Department Monsanto Research Corporation P.O. Box 8. Station B Dayton, Ohio 45407 State of Incorporation: Delaware Location of Principal 800 North Lindbergh Boulevard Corporate Office: St. Louis, Missouri 63166 Location of Licensed 1515 Nicholas Road Facility: Dayton, Ohio 45418 Principal Corporate Hilliard L. Williams, President (Citizen, USA) Officers: 800 North Lindbergh Boulevard St. Louis, Missouri 63166 D. J. Anstine, Controller (Citizen USA) 800 North Lindberg Boulevard St. Louis, Missouri 63166 Corporation Affiliation: Monsanto Research Corporation is a wholly owned subsidiary of Monsanto Company, St. Louis, Missouri. Neither company is subject to control by an alien, foreign corporation or foreign goverrr..ent. Corporate Financial Shown in appended Annual Report for 1982 Position: The Dayton Laboratory of the Monsanto Research Corporation, in which the Engineered Products Department is situated, is a research and development facility carrying out both government and company programs. The Director of the Laboratory reports to the President of the Monsanto Research Corporation. l 4.2 ORGANIZATIONAL RESPONSIBILITIES The Manager of the Engineered Products Department is responsible for the overall conduct and operation of the organization. The Manager of Operations and the Radiation Safety Officer are responsible to the Manager of Engineered Porducts for the conduct of nuclear and l radiation programs. The Manager of the Engineered Products Department reports to the Director of the Dayton Laboratory. The organization is l shown in the following pages. I I April 1983 52 l e MON $ANTO RESEARCH CORPOR ATION e l
4 R. M. Scott Director Dayton Laboratory and Engineered Products ~._ R. L. Schimmel Manager Engineered Products Department i E E 5 i 0 Secretaries a C! l I !5 l 8 G. D. Rawlings E. E. Janzow J. A. Booth J. A. Booth Manager Manager Manager Manager g Marketing Operations Quality Eng. Design & Dev. Asturance j 5z O H. L. Coleman R. R. Hawley S. D. Hoadley* anager of Supervisor 0f Health Nuclear Shipping Nuclear Manufacturing Manufacturing Physicist & Receiving Engineering & Shop
- Radiological Safety Officer Figure 4-1
. w. s. 4.2 ORGANIZATIONAL RESPONSIBILITIES (Cont'd) The Manager of the Engineered Products Department is Robert L. Schimnel. Robert L. Schinnel Birthplace and date - Fairmont, W. Va.,10 December 1923 Education - Fairmont West High School, Fairmont, W. Va., 1942; Fairmont State College, 1943; West Virginia University, Morgantown, W. Va., BSEE,1950; Drexel University, Philadelphia, Pa., grad program MBA 1960-1966. Experience -U.S. Army 1943-1946, Sgt. Infantry; U.S. Army 1950-1952, 1st. Lt., Signal Corp. Monongahela Power Co. of W. Va., and Central Illinois Public Service Co., 1952-1955, Engineer. Westinghouse Bettis Plant, Pittsburgh, Pa., group leader on Shippingport Nuclear Power Plant; control, instrumen-tation, and electrical, 1955-60. Martin Marietta Corp., Nuclear Division, Baltimore, Md.; supervisor of control, instrumentation and electrical work on PM-1, PM-3A, and MH-1A Nuclear Power Plants, 1960-1964. Manager of Development Department, direct materials, chemistry, radiation effects, and critical facility operation, 1965-1969. Monsanto Research Corp., Dayton, Ohio; Manager of Nuclear R&D, 1969; Manager of Engineered Products Department, 1970-present. The Manager of Operations of the Engineered Products Department is Edward F. Janzow. Edward F. Janzow l Birthplace and date - St. Louis, Missouri, 19 March 1941. Education - Normandy High School, Normandy, Missouri, 1955-1959. Washington University, St. Louis, Missouri, 1959-1963 (B.S. Mechanical Engineering). University of Missouri, Columbia, Missouri, 1963-1964 (M.S. in Nuclear Engineering). University of Illinois, Urbana, Illinois, 1964-1970 (Ph.D. in Nuclear Engineering). University of Dayton, Dayton, Ohio,1976-1981 (M.B. A.). 54 April 1983 ?"'* "'"^""""'"^""-
= L 4.2 ORGANIZATIONAL RESPONSIBILITIES (cont'd) Experience - E.O. Lawrence Radiation Laboratory, Livermore, CA..(USA). Mechanical Engineer. Various projects including device component design, nuclear desalination study, and laser output calibration, Summers 1963, 1964. University of Illinois, Urbana, Illinois. Graduate student and researcher in seawater desalination. Supported by National Science foundation traineeship, 1964-1970. U.S. Army Reserve, Aberdeen Proving Ground, Aberdeen. Maryland. Active duty for training, Captain, Ordanance, -1970. Engineered Products Department of the Monsanto Research Corporation, Dayton, Ohio (USA). 1971-1973. Senior Research Engineer. Designed and analyzed radioisotopic neutron and gamma sources, radio-isotope shipping containers, and facilities for fabricating radioactive sources. 1973-1975. Supervisor, Design Engineering. Supervised activities.as described above. 1975-1980. Manage.r. Engineering Design and Development. as above, with additional responsibility for development of new and improved radioactive sources. 1980-1981. Manager, Engineering and Quality Assurance. As above, with additional responsibility for the quality assurance program for radioactive sources and radioisotope shipping containers. I 1981 - Present. Mana'ger of Operations The Manufacturing Manager of the ~ Engineered Products Department is ( Harold L. Coleman. Harold L. Coleman l Birthplace and date - Humphrey, Arkansas 29 April 1932. Education - Sikeston High School, Sikeston, Missouri, 1946-1950. S. E. Missouri State College, 1950-1952. San Antonio (Texas) College, 1954-1956(evenings). University of j Texas, Austin, Texas, 1956-1969, B.S. Chemistry. l-April 1983 55 i e MONSANTO RESEARCH CORPORATION e i' ,-.... =...,.
~ _ _ _ _ i 4.2 ORGANIZATIONALRESPONSIBILITIES(Cont'd) Experience - U.S. Army, 1952-1954 Infantry. Jack Amann Photogrammetric Engineers, San Antonio, Texas, 1954-1956. Mapping and aerial survey compilation, supervision. Monsanto Research Corporation Mound Laboratory, Miamisburg, Ohio,.1959-1966. Operation Chemist, Production Department, production, research, development, assay, quality control, design, engineering of radio-isotope separation facilities and processes. Monsanto Research Corporation, Dayton, Ohio, 1966-1968. Production and development, design and assay of radio-active sources. 1968-July,1971, Manager of Marketing, Engineered Products Department. July, 1971-1973, Manager, Technical Requirements. October,1973 - June,1978, Nanaaer, Manufacturing Support. Uune, 1978 - Present, Manager of Manufacturing. The Radiation Safety Officer and responsible Health Physicist is Stephen D. Hoadley. Stephen D. Hoadley Birthplace and date - Washington, DC, 24 October 1939. Education - Palmyra High School, Palmyra, New Jersey, 1955-1957. Napoleon High School, Napoleon, Ohio, 1957-1959; Earlham College, Richmond, Indiana, 1959-1962; Findlay College, Findlay, Ohio, 1962-1964, B.S. Experience - 1964-1966, Controls for Radiation, N.A.S.A. Plum Brook Station, Sandusky, Ohio, Health Safety Operations Office. Radiation Technician I, Radiological surveys for direct radiation, surface contamination, air borne contamination and related Health Physics services. 1966-1971, Westinghouse Bettis Atomic Power Laboratory, West Mifflin, Pennsylvania. Radiation Control Department, Radiation Control Engineer, direct and assist service technicians in health physics services in radio chemistry labs and hot lab facilities. 1971-Present, Monsanto Research Corporation, Dayton, Ohio, Radiation Safety Officer, Engineered Products Department, responsible for establishing and maintaining effective radiation safety policies and procedures connected with production of nuclear sources (neutron, alpha, beta, gamma). Overall responsibility for administering the health physics program. April 1983 56 e MONSANTO RESE ARCH CORPOR ATION e
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.~ 4.2 (Cont'd) Harold A. Malson is a Senior Research Engineer and an Assistant Radiation Safety Officer. Harold A. Malson Birthplace and date - Wadsworth Ohio, 9 March 1930. Education - Wadsworth High School, Wadsworth, Ohio, 1944-1948. McKim Technical Institute, Akron, Ohio, radio repair, 1948-1949. U.S. Anny Signal Corps, Ft. Monmouth, New Jersey, radio repair, 1951-1952. Kent State University, Kent. Ohio, 1954-1958. B.S.C. Experience - Monsanto Research Corporation, Mound Laboratory Miamisburg, Ohio, 1958-1961. Neutron Source Department.~ Operating Chemist, production development, designing, and assay of radioactive sources. Monsanto Research Corporation Dayton, Ohio, 1961-1968. Nuclear Products group. leader, Radiation Safety Officer, production, design, assay of radioactive sources, radiation control and health physics. 1968-1978. Supervisor of Manufacturing and Assistant Radiation Safety Officer, Monsanto Research Corporation, Engineered Products Department. 1978-Present. Senior Research Engineer and Assistant Radiation Safety Officer, Engineered Products Department. Undertheprogramsetupbythedepartmeni',theradioactivematerials may be used by or under the supervision of the Manager of Manufactur-l ing,' the Radiation Safety Officer, the assistant (s) to the Radiation Safety Officer,.or by a technical specialist. Those persons qualifying as technical specialists are: Stanley E. Moyer, Nuclear Fabrication Lead Technician I Birthplace and date - Arcanum, Ohio, 30 December 1929 Education - Arcanum High School, Arcanum, Ohio, 1943-47. I. University of Dayton, Dayton, Ohio, 1954-1955 evening courses in Mechanical Engineering, Advance Algebra, Geometry, Mechnical Drawing, Logic, Psycology, public i-speaking; University of Dayton / Metals Engineering Institute 1976. Principles of Machining. Experience - 1948-1952 U.S. Army, artillery mechanic 1952-1953, Aero Products Co., Vandalia, Ohio, Pro-duction Machinist. 57 April 1983 e MONSANTO RESEARCH CORPORATION e
u : t.,.. ;= = a w;.... - .. a ; ~ a 4.2 (Cont'd) 3 . q2. ? 1953-1964, Precision Rubber Cc.,~ Dayton, Ohio ' Assistant Foren.an and Job Setter, responsible for < production equipment set-up and job assignments for 7 i 15-252 prodsction workers. ; 1964-1965, Mon anto Researc rpoNtion, Mound Laboratory, Miamisburg, Ohio.. Lab Technician and Health Physics technician, Radiation and contatJMtion [ survey work and Plutonium-238 processing a % %; very. A 3a 1965-Present,,Monsanto Research Corporatiod Dayton, & \\s a u' Ohio. Sr. Research technicion.\\ Lead technician ina Nuclear cperations group. Assignments ha've Scludad' development and production of sealed radiatioqsources,; health physics services assistance, radiation measure-ments fand calibration of equipment, development of radioisotope' processing and handling methods, and quality control. i Stanley Moyer's responsibilities at Monsanto Research '3 0 Corporation include the manufacture of radioactive alpha, gansna, and neutron sources. He conducts the ANSI testing program and works closely with-outside i x testing labs in the furtherance of this work. Mr., Moyer frequently assits in the design _of snew sources.' and equipment or facility improvementt ' An important, 3 part of his. current endeavor is working with the . Radiat' ion Safety Officer in the reduction of radiation b ~, 1 exposure to personnel. Edward F. Janzow, Operat' ions Manager 4i Education and experience-asf previously cited. 4.3 DEVELOPMENTOFOPEREffsiROCEDURES Writtenproceduresarepreparedand/orreviewedbykappropriate immediate function supervisor. Procedures relatingfto.0perations
- are-approved by the Operations i4anager, the Radiation Safety Officer,
'and the Engineered Products Department Manager. Should any of these three people feel the procedure being considered is significantly different than procedures' pre:ently in use, the procedure is referred to the Radiation Safety Committee for review and approval. Procedures-for other functions of the department are prepared'by the appropriate function manager and approved by the Engineered Products' Department Manager. It is a responsibility of line supervision and management to see that approved procedures are being followed. April 1983 58 1 ~ 1, s o MONSANTO' RESEARCH CORPORATION e
4.4 INTERNAL AUDITS OF PERFORMANCE To further insure adherence to the operating procedures, company internal audits of performance are carried out by the Laboratory Director or a person designated by the director, who is outside the area of engineered products. These audits are carried out annually. A written report of the audit is given to the Operations Manager and to the Radiation Safety Committee for their review and action. Records of each audit shall be maintained indefinitely as part of the Health Physics Log. 4.5 CHANGES IN OPERATING PROCEDURES Any change in operating procedures must be approved by the Operations If there is any doubt that the changes are within the Manager. framework of the license, then the reconsnended change will be sub-mitted to the NRC Division of Materials Licensing for approval. 4.4 AMENDMENTS TO NRC LICENSE Any change in our NRC license must be reviewed by the Manager of Engineered Products, the Operations Manager, the Manager of Requests for Manufacturing, and the Radiation Safety Officer. amendment must be signed by the Operations Manager, the Manager of Engineered Products or the Director of Monsanto Research Corporation, Dayton Laboratory. INSTRUCTION OF NEW EMPLOYEES AND REFRESHER TRAINING FOR PERSO 4.7 4.7.1 IND0CTRINATION OF NEW EMPLOYEES Indoctrination of new employees will be as outlined below, covering the subjects indicated: ~ Develop radiation safety consciousness Objectives of Health Physics: (A) among employees and maintain sound, realistic, and economical l' radiation protection program. L (B) Radiation Protection History _: Radiation exposure record, Radiation Protection Sign Program: Discussion of signs, use of j (C) radiation tape and ropa, and discussion or radiation tags. I (D) Radiation Alarms: Type of alarms, meaning of alarms, and action required. (E) Personnel Dosimetry: Film badges, pocket meters, and hand counters. (F) Use of Protective Clothing: Selection, use, and disposition. (G) Use of Respiratory Equipment _: Selection, care, testing, and disposition. 59 April 1983 e MONsANTO RESEARCH CORPOR ATION e
~... . ~... 4.7.1 (Cont'd) (H) Transfer of Radioactive Materials: On-site transfers and off-site shipments. (I) Nature of Radiation Injury: Human senses as radiation detectors, physiological effects of radiation, and genetic effects of radiation. (J) Radiatio _n Limit: Purpose of in-house limits, limits in comparison with NRC limits, and airborne radioactive material concentration limits. (K) Health Physics Services: Personnel records, meter testing, calibrat-ion and radiological services such as monitoring, consultation, and energency assistance. (L) Radiation Safety Consciousness Emphasis: Repsonsibility and need for developing radiation safety consciousness in one's self and others. 4.7.2 TRAINING 0F NEW EMPLOYEES IN PROCESS AREAS New employees will be given an apprenticeship type training for the handling of radioactive materials. Each new person will work under the guidance of an experienced person for a period of at least two months before he is permitted to work without constant supervision. 4.7.3 REFRESHER TRAINING Training sessions will be held at least qputterly for personnel who are involved in handling radioactive material. The subject of a training session shall be chosen from the outline of 4.7.1, shall concern the processing of radioactive material, or shall relate to other aspects of radiation safety or radioactive materials handling i chosen by the Radiation Safety Officer. l 4.7.4 WORK CERTIFICATION t A work certification system is used which requires that each person l be certified in writing by the Radiation Safety Officer and by management (usually the Manufacturing Manger) as approved to perform l an operation or class of operations within the controlled areas prior l l to being permitted to perform that operation or class of operation l without a certified person being present. Certification in operations involving radioactive materials constitutes permission to use radioactive materials for the operation. Work certification records l shall be maintained indefinitely. A typical work certification record [ form is included in the Appendix to the Operations Manual. 60 April 1983 ( e MONSANTO RESEARCH CORPORATION e
. s....u..... s l 4 l 4.8 RADIATION SAFETY COP 9tITTEE The general operations of the Engineered Products Department are under the guidance and supervision of the Radiation Safety Comittee. i The composition, responsibilities, authority, and function of this Comittee is specified in Section 5.2.5 of the License Specifications. 1 i l l l' l i 61 April 1983 e MONSANTO RESEARCH CORPOR ATION e
.-u ....a.. w. a..... w....... .c w..., ~.. 5.0 EMERGENCIES Management is responsible for the protection of personnel, buildings, and equipment prior to, during, and after any plant emergency. This shall be accomplished by formulating and maintaing an emergency organization and radiological contingency plan. 5.1 RADIOLOGICAL CONTINGENCY 5.1.1 GENERAL Licensee has prepared a written Radiological Contingency Plan wherein appropriate consideration is given the Engineered Products Department. The plan has been approved by the U.S. Nuclear Regulatory Commission and is considered to be a part of the License. The plan outlines the emergency organization, assigns individuals for various emergency functions, and specifies their associated duties. 5.1.2 EMERGENCY PLAN OBJECTIVES (A) To inform all personnel of their responsibilities during a major or minor emergency. (B) To prevent any disaster which can be possibly averted. (C) To minimize the effects of those disasters which could not be avoided by: (1) Preventing further injuries and saving lives. (2) Reducing property damage. (3) Provide for continuous or expediticus resumption of plant operations, and i 1 (4) Maintaining continuity of plant management. 5.1.3 EMERGENCY ASSUMPTIONS ~(A) That a cause of emergency may be from: Unexpected operation accidents: These may result in fires, (1) explosions, release of toxic fumes, acids, radioactive material. (2) Forces of nature: These may include severe wind storms, tornados, floods, earthquakes, or lightnir.g. (3) Deliberate damage: This may occur because of malicious activities, sabotage, act of war, or civil disorder. l l 62 April 1983 i e MONsANTO RESEARCH CORPORATION e t_
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. ~. 5.1.3 (Cont'd) (B) That the emergency may be: (1) Local in nature, such as a " spill" in a single room, small fire, or other minor accidents. (2) A disaster involving partial destruction of systems or equip-ment within a laboratory or department. (C) That the notice of an emergency may be from any of the following . sources: (1) Sprinkler system. (2) Telephone. (3) Word of mouth. (4) Manual activation of alarm systems. (D) That the Laboratory Director or his alternate will be promptly advised of the location, type and extent of the emergency. (E) That the emergency organization and brigade shall inmediately respond to emergencies during normal working hours, and shall be capable of dealing with: (1) Personnel first-aid and rescue. (2) Fires. (3) Special hazards of gases, chemicals, explosives, or ranioactive materials. 5.1.4 ADMINISTRATIVE AUTHORITY Lines of administrative authority under emergency conditions in the Engineered Products Department shall be as follows: Laboratory Director Manger, Engineered Products Engineered Products Operations Manager Radiation Safety Officer Plant Safety Officer Alternate expert personnel April 1983 63 e MONSANTO RESEARCH CORPORATION e
. c. J. ,._.z .m. 5.2 EVACUATION ROUTES, ASSEMBLY AREAS, PERSONNEL INSTRUCTIONS, EVACUATION DRILLS Evacuation routes have been established, posted, and published in the Radiological Contingency Plan. The immediate assembly area is located just East of Building 2. In actual emergency conditions an alternate assembly location may have to be specified if wind or other conditions render this location undesirable. An alternate assembly area would be specified by the Radiation Safety Officer or his alternate. 5.2.1 PERSONNEL INSTRUCTIONS All personnel are instructed on conditions which may require evacu-ation such as fire alarm and coded emergency signals released from the guard house because of an emergency in another part of the laboratory. Emergency exits are identified and evacuation routes are posted. The assembly area and evacuation rcutes are posted in both the process and support areas of the department. Department personnel are also provided with a written copy of emergency and evacuation procedures. 4 5.2.2 EVACUATION DRILLS Periodic testing of the evacuation plan is accomplished by activiting the audible evacuation alarms. Personnel from Building 2, 3, 4, 5, and 6 then evacuate their respective areas and proceed to the assembly area. The testing of alarms in this manner with subsequent evacuation of affected buildings, aids considerably in insuring adequate personnel familiarity with evacuation and assembly procedures. Practice evacuations for Zone 2 ( including the Engineered Products Department) are held quarterly. 5.2.3 UNPLANNED EVACUATIONS Any emergency evacuation clarm other than those intentionally set off for exercise purpose, which efficiently evacuates all personnel in Zone 2 will be considered of equal value in acquainting personnel with their responsibilities during an emergency. 5.2.4 RECORDS A written record of evacuation drills is kept in the Health Physics Log. 5.3 EMERGENCY PERSONNEL TRAINING 5.3.1 TRAINING Emergency personnel are trained as described in Section 7.2 of the Radiological Contingency Plan. April 1983 e MONSANTO RESEARCH CORPOR ATION e
c 5.2 EVACUATION ROUTES, ASSEMBLY AREAS, PERSONNEL INSTRUCTIONS, EVACUATION DRILLS Evacuation routes have been established, posted, and published in the Radiological Contingency Plan. The imediate assembly area is located just East of Building 2. In actual emergency conditions an alternate assembly location may have to be specified if wind or other conditions render this location undesirable. An alternate assembly area would be specified by the Radiation Safety Officer or his alternate. 5.2.1 PERSONNEL INSTRUCTIONS All personnel are instructed on conditions which may require evacu-ation such as fire alarm and coded emergency signals released from the guard house because of an emergency in another part of the laboratory. Emergency exits are identified and evacuation routes are posted. The assembly area and evacuation routes are posted in both the process and support areas of the department. Department personnel are also provided with a written copy of emergency and evacuation procedures. 5.2.2 EVACUATION DRILLS Periodic testing of the evacuation plan is accomplished by activiting the audible evacuation alarms. Personnel from Building 2, 3, 4, 5, and 6 then evacuate their respective areas and proceed to the assembly area. The testing of alarms in this manner with subsequent evacuation of affected buildings, aids considerably in insuring adequate personnel familiarity with evacuation and assembly procedures. Practice evacuations for Zone 2 ( including the Engineered Products Department) are held quarterly. 5.2.3 UNPLANNED EVACUATIONS Any emergency evacuation alarm other than those intentionally set off for exercise purpose, which efficiently evacuates all personnel in Zone 2 will be considered of equal value in acquainting personnel with their re.iponsibilities during an emergency. 5.2.4 RECORDS _ A written record of evacuation drills is kept in the Health Physics Log. 5.3 EMERGENCY PERSONNEL TRAINING 5.3.1 TRAINING Emergency personnel are trained as described in Section 7.2 of the Radiological Contingency Plan. April 1983 e MONSANTO RESEARCH CORPORATION e
5.3.2 EXERCISES l The emergency organization including the emergency squads will conduct tests and drills as described in Section 7.3 of the Radiological Contingency Plan. 5.3.3 RECORDS A written record of simulated nuclear emergency exercises shall be kept in the Health Physics Log. 5.4 ASSEMBLY POINT, EMERGENCY EQUIPMENT AND SUPPLIES, PERFORMANCE CRITERIA, EQUIPMENT MAINTENANCE Criteria for emergency equipment performance and maintenance includes: 5.4.1 SELECTION OF EMERGENCY EQUIPMENT The Radiation Safety Officer must approve the selection of any emergency equipment provided by Monsanto Research Corporation for use in the Engineered Products area. Personnel rescue and fire fighting equipnent criteria are specified by the Plant Safety Officer. 5.4.2 PERFORMANCE CRITERIA In general, the emergency equipment criteria shall be based on the recommendations of Chapter 13. Radiological Emergency Operations Manual, TID-24919, Division of Technical Information, U.S. NRC as follows: (A) Be capable of monitoring all types of contamination and radiation hazards normally encountered at licensee's facility. (B) Be able to function in any environment. (C) Be light, compact, and durable. (D) Relatively maintenance free, simple to repair and operate under emergency conditions. 5.4.3 EMERGENCY EQUIPMENT AND SUPPLIES Emergency medical supplies, radiological emergency equipment and emergency monitoring equipment are maintained on site as specified in Section 6.4 and 6.5 of the Radiological Contir.gency Plan. 5.5 ON-SITE EMERGENCY FIRST-AID AND PRELIMINARY DECONTAMINATION ~ 5.51 MEDICAL DISPENSARY An industrial type medical dispensary is located in Building 1 on company premises. Treatment available at the dsipensary is limited April 1983 e MONSANTO RESE ARCH CORPORATION e ]
5.5.1 (Cont'd) to first-aid measures. First-aid supplies can readily be taken to the accidnet scene or emergency assembly area. Such supplies are in kit form at the dispensary and are also available at other plant locations. Additional rescue and emergency equipment including first-aid supplies, are readily transferrable according to need during emergency operations. 5.5.2-MEDICAL STAFF The medical dispensary is staffed by a para-medic who is available eight hours daily, Monday through Friday. Other personnel ~at the plant have had first aid training and are immediately available if needed. Additional first-aid assistance can be provided by the Dayton Fire Department, as needed. 5.5.3 PROTECTIVE ACTIONS AND EXPOSURE CONTROL Protective actions including contamination control measures will be taken by license to minimize exposure to radiation or radioactive materials of on-site personnel as described in Section 5.4 of the Radiological Contingency Plan. Exposure control including personnel decontamination will be performed as described in Section 5.5 of the Radiological Contingenecy Plan. 5.6 HOSPITALS, PHYSICIANS, AND AMBULANCE SERVICES License has made arrangements for hospital, physician, and ambulance services for the care of injured porsonnel who may be contaminated and/or who have received excessive exposure to radiation as described in Section 5.6 and 5.7 . the Radiological Contingency Plan. 5.6.1 PHYSICIANS The Chief Radiologist at St. Elizabeth Hospital will be contacted annually for exchange of information regarding the appropriate hospital reception and care of radiation casualties. The following professional personnel have been contacted and informed of postulated injuries and possible associated radioactive contami-nates. Dr. K. Kircher, Radiologist, St. Elizabeth Hospital, Dayton, Ohio 66 April 1983 e MONSANTO RESEARCH CORPORATION e J
~... 5.6.1 (Cont'd) Dr. J. Leary, Internist, St. Elizabeth Hospital, Dayton, Ohio, (Monsanto Research Corporation - physician for the Dayton Laboratory) Additionally, the following expert medical personnel are available for consultation by the above named physicians. Dr. E. L. Saenger, Radiologist, College of Medicine, University of Cincinnati, Cincinnati, Ohio. 5.7 EXPERT OFF-SITE CONSULTANTS Licensee has determined where expert off-site consultation or assistnace may be obtained for emergencies involving radioactive materials. These off-site expert consultants are listed in Sections 4.3 and 4.4 of the Radiological Contingency Plan. 5.8 RADIOLOGICAL CONTINGENCY MEASURES Radiological contingency response measures for each class of radiological contingency will be performed as specified in Section 5.0 of the Radiological Contingency Plan. 5.9 RE-ENTRY CRITERIA FOLLOWING EMERGENCY EVACUATION Re-entry criteria and procedures during each class of radiological contingency, and general re-entry criteria, are specified in Sections 5.0 and 9.0, respectively, of the Radiological Contingency Plan. 5.10 DAYTON FIRE AND POLICE DEPARTMENT ORIENTATION 5.10.1 FIRE DEPARTMENT The licensee meets annually with the District Fire Chief of 0parat-ions at the Fire Department's discretion. The purpose of this meeting is to exchange information with the fire department f concerning appropriate response to a fire, at any hour, in the l Engineered Products Department. Summary of meeting topics: (A) Facility tour with description of normal operations involving radiation. Floor plan review, identifying rooms with special hazards such as (B) solvents, gas bottles, chemicals, and radioactive materials. (C) Sprinkler system review, and shut-off valve locations. April 1933 g e MONSANTO RESEARCH CORPORATION e
5.10.1 .(Cont'd) (D)' Location and types of ' department fire fighting and rescue equipment. .(E) Types of radiation likely to be encountered, alarm systems, warning signs, etc. .(F) Potentially required protective clothing and equipment. (G)- Segregation of fire department personnel and equipment for monitoring. (H) First-aid capabilities and precautions, the rescue or recovery and transport of casualties. (I) Need for following MRC instructions under emergency situations in the Engineered Products Department. (J) Manpower, equipment, and capability of initial fire department re-sponse crew. (K) Fire department response during laboratory operating and non-operating hours. 5.10.2 POLICE DEPARTMENT Licensee, meets annually with the Dayton Police Department at the. Police Department's descretion. This meeting is held for exchange of information concerning the appropriate police department re-sponse to emergencies in the Engineered Products Department. Summary of Agreements: (A) Police Department will control traffic and establish road blocks as requested, allowing only MRC approved individuals access to plant premises. (B) Police Department will escort vehicles in transporting casualties, or samples to local facilities specified. (C) Police Department will assist in establishing emergency communications, and will place calls as requested. (D) Police Department will assist in effecting off-site evacuation if requested. (E) Police Department will assist in securing affected area from unauthorized entry if requested. (F) Police Department will escort vehicles transporting expert consul-tants and/or equipment to the emergency scene if requested. April 1983 68 e MONSANTO NESEARCH CORPORATION e
~ ~ - -~ ,..-...c+: l f i 5.11 0FF-SITE EVACUATION AND CIVIL AUTHORITY AGREEMENTS Arrangements have been established with the local Police Department for off-site evacuation. As concluded in the Radiological Contingency Plan, the threat to life or health, and the exposure potential to any individual in the off-site environment is considered to be of very low probability. 5.12 PROVISIONS FOR MAINTAINING EMERGENCY PLANS, PROCEDURES, AND LISTS OF PERSONNEL UP-TO-DATE The Dayton Laboratory Safety Officer is directly responsible for maintaining laboratory emergency plans, procedures, and lists of personnel up-to-date. The plant disaster emergency plan is also subject to periodic review by the Safety Steering Committee. The Engineered Products Department Radiation Safety Officer _is respons- 'ble for developing and maintaining supplemental emergency procedures that apply specifically to the Engineered Products Department. These are contained in NPD-STD-002. A copy is put in the emergency cabinet in Building 1. Maintenance of the Radiological Contingency Plan is tne responsibility of the Engineered Products Operations Manager. 5.13 REPORTS Reports during radiological contingencies shall be as specified in Section 5.0 of the Radiological Contingency Plan for the particular class of contingency. Other records and reports shall be as specified in Section 8.0 of the Radiological Contingency Plan. In all the above situations, reports will be made as required by 10 CFR Part 20. 5.14 PUBLIC INFORMATION DURING EMERGENCIES All' news releases will be handled by the Laboratory Director or appointed alternate. Assistance in press release preparation will be requested of the U.S. Nuclear Regulatory Commission, Division of Compliance, Region III, Chicago, Illinois, in the event of any incident involv-ing radioactive materials. Past experience has indicated that MRC-NRC concurrence on press releases have been mutually advantageous. s 69 April 1983 o MONSANTO RESEARCH CORPORATION e
i 6.0 RADIATION CONTROL 6.1 PERSONNEL MONITORING External radiation to whole body and extremities. 6.1.1 GENERAL REQUIREMENTS: (A) Licensee uses film dosimetry methods for determining whole body and extremity exposure to external radiation. R. S. Landauer, Jr., & Company is supplying and processing all film badges required by licensee. Other qualified companies may be used at MRC descretion. (B) All personnel assigned to Engineered Products Department work within the controlled area are provided with a beta-gamma-neutron film badge for measurement of whole body exposure. Department personnel who handle radioactive material are also provided with a special wrist type film badge for measurement of gamma-neutron exposure to the extremities. Department personnel are required to wear their assigned whole body film badges at all times when working within the controlled area. Special wrist film badges are worn only when handling or processing radioactive materials. Both types of film badges are identified by name, code, health physics number, and date. Personnel l are required to wear the whole body film badge on the outside of their graments. (C) All film badges for department personnel are returned to supplier for analysis on a weekly basis. Licensee has a special arrangement whereby the supplier is reporting all exposures via telephone within a few days following receipt of the badges for analysis. (D) Similar whole body and extremity film badges are provided for visitors to the Engineered Products Department. The Radiation Safety Officer determines the requirements for visitor use of dosimetry equipment in accordance with 10 CFR 20. A visitor's film badge register is maintained which includes the minimum information required for completion of NRC Form 5. Used or exposed visitor badges are processed at not more than 30. day inter-vals. 6.1.2 RECORDS Licensee maintains permanent records of exposure for all personnel or whom monitoring is required by 10 CFR 20. The folicwing types of records are on file within the deaprtment: (A) NRC Forms 4 and 5 or equivalent as appropriate. (B) Film badge reports for department personnel and visitors. (C) Visitor film badge register. 70 April 1983 e NONSANTO RESEARCH CORPORATION e L-
~_ m 6.1.3 REPORTS The manager of Engineered Products shall submit reports of excessive personnel exposure in accordance with 10 CFR 20.403. Management is immediately notified of any such report requirements, and a copy of such a report is filed in the appropriate personnel file. The Radiation Safety Officer submits reports of personnel monitoring and exposure in accordance with 10 CFR 20.405, 20.407, and 20.408. 6.1.4 ESTIMATED EXPOSURES In the case of loss or damsge to a film due to moisture or light leak, the Radiation Safety Officer or his assistnat will make the best estimate he can, and the estimated exposure is entered into the appropriate radiation exposure records. 6.1.5 SPECIFICATIONS FOR FILM BADGES R. S. Landauer, Jr., & Company, Licensee's current film badge. supplier, has certified that they do in fact meet the specifications outlined in 7.1 of Specifications. 6.1.6 TARGET LEVELS FOR WHOLE-BODY DOSE As part of his ef'.' ort to keep radiation doses to personnel as low as is reasonably achievable, the licensee establishes internal target levels on personnel whole-body dose. The target levels are set periodically by the Manager of Engineered Products in consultation with the Rah ation Safety Officer and the Operations Manager; levels are set be'.,ed upon expected volume and types of sources to be manufactured, available and obtainable equipment and facilities, and other tactors. Receipt of a whole-body radiation dose is excess of the target level by any individual requires that the Radiation Safety Committee review the circumstances of the exposure to determine what corrective measures (if any) must be taken to minimize the likelyhood of reoccurrance. The present whole-body target dose level is 550 mrem per calender quarter. 6.2 RADIATION MONITORING AND CONTAMINATION CONTROL 6.2.1 GENERAL REQUIREMENT Licensee has an established and effective program for radiation and contamination monitoring and control. The program is designed to provide prompt detection, evaluation, and appropriate corrective measures for real or potential radiation hazards to personnel in all areas under licensee's control. In addition, the program provides the required information for determining compliance with licensee specifications and/or the requirements of 10 CFR 20. 71 April 1983 e MONSANTO RESEARCH CORPORATION e
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~ I 4 6.2.1 (Cont'd) The basic aim of the program is to minimize internal deposition of radioactive contaminants, and to keep the total external radiation exposure received by personnel at the lowest practical level in all cases. The success of this program depends largely upon the individual radiation worker. It is further recognized that an effective pro-gram of radiation control is dependent upon the cooperative effort of all personnel in the implementation of the prescribed requirements as well as the care and proper use of the equipment provided. Accordingly, licensee requires 41 department personnel to know-the established procedures, and to apply them di1 gently to achieve maximum protection for himself and for his fellow workers. Licensee en-courages all employees to discuss with supervision, and/or Radiation Safety Officer, any questions which may arise pertaining to radiation safety. 6.2.2 RADIATION MONITORING (A) As a matter of routine, operating personnel are required to conduct appropriate radiation surveys prior to, during, and at completion of individual work assignment involving the handling or processing of radioactive material. Each day, the first person entering a room in the hot area conducts a general room survey including his assigned work station. Radiation + signs are used, as required, to identify levels detected. Of 3 principle interest are the radiation levels along the box lines, fume hoods, and storage safes. Normally only the levels exceeding 5 rem /hr i are so posted. Unusual or significant variations in the levels detected are reported to the Radiation Safety Officer. During pro-cessing of radioactive material in the hot area, only intermittent monitoring is performed when the radiation levels are moderate and not subject to significant change. More frequent monitoring is required as the level increases or if the radiation level is subject a to significant increase. A typical example of a significant increase i would be when a PoBe-210 neutron source is reacted. In such a case the j glove box is surveyed prior to and after reaction. Continuous moni-toring is required when radiation levels are high or in untried a situations. Continuous monitoring requirements are specified by the Radiation Safety Officer. A final survey is conducted by operating personnel at the conclusion of the work assignment, and supervision is notified of any unsatis-i factory or unusual conditions left in the work area. i (B) Radiation Safety Officer's knowledge and approval is required before 4 an individual is authorized to undertake a work a.ssignment in an area where the radiation level at the assigned work station exceeds 100 mrem /hr of penetrating radiation to the whole body. Previous exposures 72 April 1983 e MONSANT,0 RESEARCH CORPORATION e
..,m_.. 6.2.2 (B) (Cont'd) are reviewed and an acceptable additional exposure is determined. Working time limits are established and monitoring requirements are Further consideration is given to possible methods of specified. reducing the radiation level by any safe means and possibilities of reducing exposure time. In addition to operating personnel surveillance of radiation levels, (C) the Radiation Safety Officer, or his assistant, conducts independent Such spot radiation surveys in all areas under licensee's control. surveys are conducted in periods between formal routine surveys. The The equipment or areas surveyed are often selected at random. general intent is for verification of posted and unposted levels within the controlled area. Such surveys aid in maintaining a high level of confidence in monitoring procedures. This type of survey is considered to be a major backup to operating personnel surveillance and formal radiation surveys, and is of vital importance to the overall radiation monitoring program. Spot radiation surveys are conducted as needed. In addition to operating personnel surveillance of radiation levels (D) and spot verification surveys, the Radiation Safety Officer, or his assistant, conducts complete routine surveys of all appropriate areas under licensee's control. Routine radiation surveys are performed without a special request The initiating the survey each time, and is done periodically. purpose of routine surveys is to determine and record the radiation levels in and around the facility at a particular time, and to provide permanent records for determining compliance with license conditions and/or 10 CFR 20. The areas surveyed include all the rooms in the controlled area, occupied rooms immediately adjacent to the controlled area, and exterior wall surfaces of controlled area, perimeter fence, and the radioactive waste storage building. Radiation survey frequency varies according to a particular area's need based on previous experience, anticipated levels, production schedules, occupancy factors, degree of hazard, and occasionally because of spot survey results. Surveys are also conducted in new or unusual operations or circum-stances, so that the radiation levels are known for better estimation of personnel exposure. 73 April 1983 m f%C30ANTO RESEARCH CORPORATION e
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.w. ...... :.. w... ...g. 6.2.2 (Cont'd) (E) RECORDS (1) Licensee is maintaining written records of radiation surveys conducted in accordance with 7.2.2 (D) of Specifications. Such records are considered to be a part of licensee's permanent records and, as such, are readily available for reference. (2) Licensee is not maintaining permanent radiation survey records for the type of surveys specified in 7.2.2 (A) and (C) of specifications. 6.2.3 CONTAMINATION CONTROL (A) Each sealed source containing byproduct or special nuclear material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months except that each source designed for the purpose of emitting alpha particles shall be tested at intervals not to exceed three months. (B) (1) Each sealed source acquired from another person and containing licensed material, other than Hydrogen 3, with a half-life greater tha thirty days and in any form other than gas shall be tested for contamination and/or leakage prior to use. In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, the sealed source shall not be put into use until tested. (2) Notwithstanding the periodic leak test required by this condition, any licensed sealed source is exempt from such leak tests when the source contains 100 microcuries or less of beta and/or gamma emitting material or 10 mii.rcuries or less of alpha emitting material. (3) Except for alpha sources, the periodic leak test required by 6.2.3 (A) does not apply to sealed sources that are stored on site and not being used. The sources exempted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within six months prior to the date of use or transfer. (C) Each sealed source fabricated by the licensee shall be inspected and tested for construction defects, leakage, and contamination prior to ~ use or transfer as a sealed source. If the inspection or test reveals any construction defects or 0.005 microcurie or greater of contami-nation, the source shall not be used or transferred as a sealed source until it has been repaired, decontaminated, re-inspected, and re-tested. J4 April 1983 e MONSANTO RESEARCH CORPORATION e
6.2.3 (Cont'd) (D) The test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. The test sample shall be taken from the sealed source or from the surfaces of the device in which the sealed source is permanently or semi-permanently mounted or stored on which one might expect contamination to accumulate. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the Commission. (E) If the test required by Subsection (A) or (B) of this section reveals the presence of 0.005 microcurie or more of removable contamination, the licensee shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired or to be dis-posed of in accordance with Commission regulations. If the source.has _ been transfarred from our licensed facility and placed in service and subsequently found to be leaking, an investigation will be made to establish the circumstances and a report shall be filed within 30 days of the test with the Director, of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, D.C., 20545, describing the equipment involved, the test results and the corrective action taken. A copy of such report shall also be sent to the Director, Region III, Office of Inspection and Enforcement, USNRC, 799 Roosevelt Road, Glen Ellyn, Illinois 60137. (F) Operating personnel chall conduct environmental surface contamination surveys prior to, during, and after completion of individual work assignments involving processing of radioactive materials. (G) Personnel shall not undertake routine work assignments in any area where removable contamination levels have been determined to be above established acceptable limits, without approval of the Radiation Safety Officer. Personnel shall report such excessive levels of contamination to the Radiation Safety Officer, or his assistant, for. appropriate action. (H) In addition to operating personnel-surveillance of removable contam-ination levels during processing of radioactive materials, the Radiation Safety Officer, or his assistant, shall at their discretion conduct periodic spot smear surveys of any area to insure compliance with established procedures and/or license conditions. Complete routine surveys are conducted twice each month. (I) The Radiation Safety Officer, or his assistant, shall for any reason and frequency deemed appropriate for insuring safe operations and compliance with established procedures and/or license conditions, conduct independent formal contamination surveys of any process or area under licensee's control. 75 April 1983 e MONSANTO RESEARCH CORPORATION e
k l-L 6.2.3 (Cont'd) t (J) Contamination Limits: (1) Licensee shall limit removable contamination in the controlled process area excluding glove and remote handling box interiors to: 2.25 X 10_4pCi/100 cm2 (500 dpm/100 cm2) alpha 1 X 10_3 pCi/100 cm2 (2200 dpm/100 cm2) beta-gamma (2) Licensee shall limit removable contamination in the controlled support area to: 5 X 10>uci/100 cm2 (110 dpm/100 cm2) alpha 1 X 10_4pCi/100 cm2 (220 dpm/100 cm2) beta-gamma (3) Licensee shall undertake appropriate decontan.ination efforts when levels are detected that exceed established limits includ-ing the internal fume hoods. 6.3 SHIELDING 6.3.1 PR_0 VISION Shielding is provided for routine or special use, as appropriate, when radiation levels pose an unwarranted exposure hazard to personnel. 6.3.2 MATERIALS AND USE Shielding appropriate to attenuate the type of radiation emanating from a glove or remote box may be affixed to the outer surface of the box, or placed adjacent to the outer surface. Transparant shielding over the glove box windows may consist of glass, leaded glass, lucite, water-filled tanks or other appropriate materials. Shielding for the non-window box surfaces may consists of lead sheeting or bricks, lead-loaded paste, steel sheets, benelex sheets, water extended polyester (with or without a neutron absorber such as boron), plastic (polye-thylene, polypropylene, etc.) or other appropriate materials. Shielding of radiation remote from glove or remote boxes may be achieved using materials similar to those listed above, fabricated or erected into walls or other barriers. Shielding of this type is frequently set up for a particular task or operation and is frequently temporary in nature. April 1983 e MONSANTO RESEARCH CORPORATION e -___L
. ~. ~... ~.. -.. ~ 6.4 PROTECTIVE CLOTHING 6.4.1 CLOTHING REQUIREMENT _ All visitors and department personnel are provided with protective clothing appropriate to the occasion. Minimum protective clothing requirements have been established and posted for all personnel entering the controlled area. 6.4.2 CLOTHING PROVISION Department peisonnnel have been provided with, or have readily available all of the items as specified in 7.4.2 of Specifications. Visitors are provided with laboratory coats, shoe covers, and other items as specified by the Radiation Safety Officer or his assistant at the time of entry. 6.4.3 LAUNDRY REQUIREMENTS All department personnel are required to monitor their individual protective clothing prior to deposit in the labelled laundry drum. Laundering of protective clothing is usually performed by licensee personnel using equipment located adjacent to the emergency decon-timination shower between the Controlled Process Area and the Controlled Support Area. Water from the laundry facility drains into a holding tank, and is disposed of as described in Section 7.6 of the License Specifications. In the event that protective clothing is to be laundered outside of the controlled area, it is monitored by the Radiation Safety Officer or an Assistant Radiation Safety Officer prior to transfer to the laundry facility. Any clothing found to have radiation levels exceeding established limits is either decontaminated or disposed of as radioactive waste. 6.5 REMOTE HANDLING DEVICES 6.5.1 PROVISION Operating personnel are provided with laboratory tweezers, forceps, and tongs, for manipulation of radioactive materials. The physcial size and weight of the radioactive materials handled permit manual Master-slave manipulators are provided for handling in all cases. handling in several remote boxes and in certain other facilities. 6.5.2 TYPE Typical remote handling devices used shall include, but is not limited tweezers, forceps, tongs, neutron source holders, articulated to: tongs, and master-slave manipulators. .77 April 1983 e MONSANTO RESEARCH CORPOR ATION e
u--z m u m. m - m ~ - - - - 6.6 RADI0 ACTIVE WASTE 6.6.1 COLLECTION AND PACKAGING (A) Liquid radioactive waste from process lines are chemically neutralized, solidified by mixing with concrete, put into plastic bottles and then bagged out and placed in plastic-lined drums. Mop water and other liquids used in decontamination procedures are mixed with concrete and Absorb-All in steel drums. (B) All containers used for storage, or shipping and disposal or radio-active waste meet the requirements of the Department of Transpor-tation Regulations. 6.6.2 MONITORING AND LABELING All final containers of radioactive waste are monitored for removable contamination and direct radiation prior to removal from the controlled area. Removable contamination levels are limited to 9.0 X 10-5 9C1/100 cm2 alpha and 4.5 X 10-8 uti/100 cm2 beta-gamma. Measurements of the gama-neutron levels are taken and recorded on a waste survey data sheet. Other data is recorded on the survey data sheet, such as the dcte, drum number, principle isotope, and activity. The appropriate DOT label is applied, also " Caution - Radioactive l Material" labels are affixed at two points on the container. 6.6.3 STORAGE AND DISPOSAL (A) Properly packaged and labelled containers of radioactive waste are stored in Building 7, on the company premises. All radioactive waste is stored at this location pending shipment for disposal. The building is posted and locked. Only certain predetermined and authorized personnel are allowed entrance. Building 7 details are shown in drawings G-7-1, G-7-8, and G-7-3. (B) A qualified waste disposal company is employed for pick-up and disposal of all radioactive waste materials. Records of radioactive waste disposal are maintained on the forms provided by the waste disposal company. 6.7 MATERIAL AND EQUIPMENT RELEASE LIMITS 6.7.1 MONITORING As a matter of standard practice, the Radiation Safety Officer or an assistant monitors such items as tools, glassware, hardware, gas bottles, containers, etc., prior to authorizing their release from the controlled area. April 1983 MONSANTO RESEARCH CORPOR ATioN e e
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. :......ZG ~.l5: ? GT... l,...... a.~. ? Y C, ..{.. ;.,. ', ~ EQUIPMENT LIST 6.7.2 LIMITS FOR ITEMS RELEASED TO NON-RESTRICTED AREAS Items located in the controlled area require monitoring prior to removal from the controlled areas of the department. Removable activity is limited to not more than 9 X 10-* uti/100 cm2 (20 dpm/100 cm2) for alpha emitters, and 4.5 X 10-5 pC1/100 cm2 (100 dpm/100 cm2 for beta and gamma emitters before release to non-restricted areas. Authorized release of itmes requires the approval of the Radiation Safety Officer or his assistant. 6.8 INSTRUMENTATION 6.8.1 INSTRUMENT PROVISIONS Various types of radiation detecting instruments are provided and are readily available for use by qualified department personnel. Such instrumentation is appropriately used for conducting radiation and contamination surveys, personnel monitoring, and laboratory analyses. Personnel are trained in proper application, limitations, testing, and interpretation of.results. Specifications for the purchase, maintenance, calibration, and use of. all portable, semi-portable or fixed instrumentation are established by the Radiation Safety Officer. Instruments on hand include but are not limited to the following: QTY ITEM Low energy counter (Monsanto Research Corporation, design)' 1 1 Proportional counter converter, NMC, Model PCC 10A 1 Scintillation probe, (Eberline) 7 Alpha air monitors (Eberline Models Alpha-1, 2, 3, 5A) 3 Model R0-2 (Eberline) By survey meter 0-5 R/hr 2 Model 1150D lowBkgd; a, By, automatic sample counting systems (Searale Analytic) used for routine air samples & wipes. All By counting done on these systems. 1 Model TDA-20/TDA4A DOP test equipment 3 Tennelec scaling systems 2 Multichannel annalyzers (Caberra 8000/e:Tracor Nortern TN-1750) 1 Cutie Pie survey meter, Model 470A (Victoreeh) 1 Precision twin differential calorimeter (MRC design) 2 Geiger counter, Model E-510, (Eberline Instrument Corp.) 82 April 1983 i (R@RP@ RATION e
.....: 2. & z.o.. .._~ - - _ 6.8.1 (Cont'd) QTY ITEM 4 Spherical Rem Counters (Neutron), Models PNR-4 and PRS-2P (Eberline) Instrument Corp.) 7 Alpha Survey Meters, RM-15 and AC-3 (Eberline Instrument Corp.) 1 s,y hand monitor RM-19 and HP210 (Eberline Instrument Corp.) 6.8.2 PORTABLE INSTRUMENT SPECIFICATIONS Portable instruments meeting requirements in 7.8.2 (A), (B), and (C) of the License Specifications include: (A) BETA-GAMMA (1) Eberline Instrument Corporation, Model R0-2 (2) Eberline Instrument Corporation, Model E-510 Beta-Gamma portable instruments will be available with a combined capability of monitoring from 0.1 mrem /hr to 5000 mrem /hr. Accuracy will be within 20% of actual value. (B) NEUTRON (1) Eberline Instrument Corporation, Models PNR-4 or PRS-2P Neutron portable survey meters will have a range from 0.5 mrem /hr to 5 rem /hr with an accuracy within 20% of the actual dose rate. (C) ALPHA (1) Eberline Instrument Corporation, Model RM-15 with Ac-3 probe l Alpha survey meters will have an efficiency of at least 25% for alphas above 1 MEV. 6.8.3 LABORATORY INSTRUMENTS Liquid bioassay samples and other samples requiring special instrumentation are sent to a qualified outside laboratory for measurement. The current vendor laboratory is Controls For Environmental Pollution of Santa Fe, New Mexico. i 6.8.4 INSTRUMENT SURVEILLANCE j (A) Portable radiation detection instruments are given routine or special service by an Engineered Products technician trained in electronics on an as-need basis. The type of service provided is limited to repair i or maintenance of electronic components. Instruments requiring major ll 83 April 1983 e MONsANTO RESEARCH CORPORATION e
y s 6.8.4 (Cont'd) i repairs are sent to the manufacturer or other outside repair facility. Routine calibration is required after electronic repair regardless of frequency. 3-(B) Other radio-sensitive laboratory equipment not subject to the handling abuses of portable equipment normally requires less frequent servicing. These instruments are also serviced by an Engineered Products technician trained in electronics. Routine servicing is performed on a semi-annual basis. The type of service provided is limited to repair or maintenance of electronic components. Major repairs are performed by manufacturer or repair facility either on the licensee's site or at the repairer's facility. Routine cali-bration is scheduled quarterly, and in all cases calibration is Certain required after electronic repair regardless of frequency. counting room equipment is calibrated daily, or prior to use as the situation warrents. (C) All instruments are calibrated within the Engineered Products Radioactive s_ources of known strength are used for Department. determining operating voltage plateaus, and instrument detection 2 efficiencies. In addition, an Eberline Instrument Corporation mini-pulser (Model MP-1) is used for aiding the calibration or trouble shooting of pulse counting instruments. All instrument calibration is undertaken in a manner specifically approved of by the Radiation Safety Officer. Calibration procedures l l employed are considered in all cases to be equal to or exceeding'the manufacturer's recommendations. Service stickers, calibration data, and dates are affixed on the instruments, or are otherwise available, l j j 6.9 BI0 ASSAY 6.9.1 GENERAL REQUIREMENT Licensee has established and is maintaining and administering a bio- \\ l assay program for all personnel who handle, process, or are exposed to radioactive materials within the controlled area. 6.9.2 MAXIMUM PERMISSIBLE BODY BURDENS Maximum permissible body burdens are limited in accordance with the " Recommendations of I.C.R.P.. Report of Committee II, on Permissible Dose for Internal Radiation". 6.9.3 ACCEPTABLE PRACTICES (A) Provisions are maintained for routine or special collection and analysis of various bioassay samples, such as urine, feces, or Plastic bottles, metal cans, and plastic bags are maintained sputum. All such supplies are stored in an area for routine or emergency use. 84 April 1983 e MONsANTO REsEARCH CORPORATION e l -
^ w L... ~. A. D :. ;. .a-- ~. a. 6.9.3(A)(Cont'd) outside the controlled area, and in an area known to be free of radioactive contamination. (B) Routine bioassay samples consist of 24-hour urine voids, and are collected off-site. Personnel are given new containers on the last working day before the sampling period. Personnel are instructed to begin obtaining the sample with the first void on Sunday and continue collecting each void until the last Sunday PM. Certain deviations from this established procedure occasionally occur but i in each case, the sample submitted is representative of a 24-hour sample. During the period of collection, the individual will be restricted from working in areas or under conditions in which further exposure may occur. Each sample container is identified by the assigned health physics number and the sample date. (C) Routine Urine Sample Frequency shall be as follows: (1) Radiation Workers - Routine urine sampling is currently requested on a monthly basis for all employees who routinely 4 work with plutonium, chliforium, americium, and polonium. Supervisors and other personnel who frequently enter materials handling areas, but who do not actually perform operations with unsealed forms of materials are submitting routine urine samples once per quarter. i (2) The type and number of samples, type of material analysis, and sampling frequency required for all personnel is determined by the Radiation Safety Officer. I (D) Special bioassay procedures will be employed to evaluate possible disposition from known or suspected accidential exposures. Fecal and/or lung counting will be performed for such exposures, as well as for follow-up evaluation to confirmed routine urinalaysis, if l evidence indicates that the exposure may have been to relatively insoluble forms of radioactive materials. I (E) Action levels and Lower Detectable Limits - The currect commerical l bioassay service, Controls for Environmental Pollution, Santa Fe, New Mexico, meets the lower detectable limit requirements of Section 7.9.3 (E) of the License Specifications. Any organization employed to process bioassay samples will be required to meet the same specifications. L Resampling and investigation as to the possible source, casue and magnitude of the exposure shall be required when action leywls are exceeded: excluded are persons who routinely excrete any of these materials above the applicable action level because of previous l known depositions. Resampling for such persons will be performed if l April 1983 85 l e MoNSANTO REsEARCH CORPORATION e
l i 6.9.3(E)(Cont'd) routine urinalaysis indicates possible additional intake. (F) Licensee has determined where local expert bioassay consultation and assistance may be obtained for cases of known or suspected significant inhalation or deposition. Local bioassay consultation available as listed below: (1) Department of the Air Force Radiological Health Laboratory Wright-Patterson Air Force Base Dayton, Ohio (2) University of Cincinnati Radioisotope Laboratory, College of Medicine Cincinnati General Hospital Cincinnati, Ohio (3) Mound Laboratory Bioassay Department Miamisburg, Ohio (G) Licensee has determined the local facilities available for lung or whole body counting of personnel. These facilities are listed in 6.9.3 (F) above. (H) All bioassay records and reports are maintained in the Health Physics files and are readily available for review by the Comission. 86 April 1983 MONSANTO RESEARCH CORPOR ATION e e _g
. e.. n, v. 7.0 DESIGN FEATURES - AIRBORNE CONTAMINATION CONTROL 7.1. INTER-AREA FLOW DESIGN Ventilation equipment in Engineered Products is designed to provide an air flow from areas of less contamination to areas of potentially higher contamination. Drawings C2608-L-01, A2608-L-02 through -05, 82608-L-06, A2608-L-07, C2608-L-08, A2608-L-09and -10, and D6901-AA-01, sheets 6 and 7 show features of air handling systems and layout of air sample points. An additional air sampling point is located inside Building 7. 7.2 ENCLOSURES The following system of enclosures is used in the handling of materials: Constructed of corrosion resistant sheet metal with (A) Glove Boxes: safety glass windows. All seams are welded or gasketed to retain materials within the enclosures. Glove boxes are held at a negative pressure of s1.0 in. H 0. Entrance into the glove box is made 2 throught a double door air lock system. Boxes are provided with glove ports for working within the enclosures. Where appropriate the The boxes are surrounded with shielding to reduce radiation levels. atmosphere within the box is vented through a closed air filtration Air flow through the box is minimal and results from system. leakage only when the box is closed. However, the box filtration system is designed for an air flow of 50 CFM through an 8" glove All penetrations are designed.such port should the port be opened. that air flow is inward through the box and out the filtration system. Drawings C-938 through C-941 illustrate the design of these boxes. Constructed of corrosion resistant metal with sa.fety Remote Boxes _: (B) glass, leaded glass, water-filled, or oil-filled windows or windows composed of two or more of these types. Remote manipulators are provided for handling high-level sources; all work on such sources is accomplished from behind shielding adequate for attenuating radiation to the operator to 60 mrem /hr or less. Set-up and main-entance operations, and operations involving low-level sources may Remote boxes are operated at a be accomplished through glove ports. Entrance into remote boxes is negative pressure of s1.0 in. H20. made through double door air lock systems. The atmosphere within the All remote boxes is vented through a closed filtration system. penetrations are designed such that air flow is inward through the Drawings C2614-AA00_and C26_20-AA00 box and out the filtration system. illustrate the design of an intermediate-level and high-level remote box, respectively. 81 April 1983 o MONSANTO RESEARCH CORPORATION e . _ _ _ _ _ _ _ _ _ _ -, _ - - - _ _ _ ~..
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.~, 7.2 ENCLOSURES (Cont'd) (C) Filtration: Air exhausted from each glove box or shileded box passes through two absolute filters in series, each with an efficiency of 99.9% for 0.3 micron particles. The systems consists of a primary filter at each box connected by metal and/or vinyl covered flexible ductwork to a secondary filter at the exhaust stack. Filters, gaskets, and fittings on the filter are in compliance with MIL-F-51068C Specification. The ductwork is made up to 90% metal pipe and therefore is quite fire resistant In place testing of the final high _ Replacement limit for filters: (D) efficiency exhaust ventilation system filter shall be performed after each change of the filter and as a minimum annually thereafter using The acceptance efficiency for a filter using the " cold" DOP test. the standard poly-disperse DOP aerosoal (count median diameter of about 0.8 micron) shall be 99.95 percent. When dampers are installed past the primary filters to j (E) Damper _s: facilitate changing of filter, the dampers are completely open in normal operation. (F) Box pressure differential _: In normal operations, the boxes are kept This in a negative pressure differential of 1-inch of water. differential is produced by a fan on the roof that exhausts into a 50-foot high stack. The negative pressure on the boxes is controlled by an air-operated damper, Minneapolis-Honeywell pneumatic modulating motor #MP903B10ll, that bleeds air into the stack fan past the final filter. The control unit Minneapolis-Honeywell, PP904A, static pressure regulator, is set to keep the air differential at a pressure of 1-inch 1/4-inch of water. Exhaust air from dry boxes: Sampled downstream from the final filter (G) at the rate of 20 liters per minute for the entire 24-hours per The filter paper through which the sample is day /7 days per week. pulled is then counted in a proportional counter to determine the concentration of radicactive material in the exhaust air. Records shall be kept of these air samples. The records will be made available upon request by the N.R.C. (H) _ Operational Limitation: The use of volatile, flamable liquids and flammable gases are severely restricted. They may be used only with the approval of the Manager of Manufacturing and the Safety Officer After their use, the enclosure must be purged or their alternates. This action is to remove the chance of with air for 15 minutes. pockets of explosive mixtures being trapped and then ignited inside a closed area. April 1983 nMrfcc12@ OpmAR8H CORPORATION e
7.3 AIRBORNE CONTAMINATION CONTROL The airborne contamination control design features include: (A) Routine Sampling: The licensee is maintaining a routine sampling program which provides for the determination of airborne concentrations of radioactivity to which personnel have or may be exposed. (B) SAMPLING METHODS _: The air sampling system consists of a type 22-AF-Roots Connerville blower to supply the vacuum, and a series of copper tubing to the sampling points. Each sarrpling point has a Gelman sampling head, an accurate flow meter, and flow adjusting valves. Each sample point is individually calibrated to the desired flow rate. The air sampling system is equipped with a timing device for automatic daily start-up and shut-down. This system provides for continuous air sampling as required by 8.3(B) of Specifications. The filters are changed on a daily basis just prior to facility shut-down. Filters are changed for each of the room air samplers. Locations of air samplers are shown in Drawing C2600-L-03. (C) Limits: Licensee, in no case, plans or intends for personnel to be exposed to airborne concentrations in excess of the limits specified in Appendix B. Table 1,10 CFR 20. All general and stack air samples are counted three (3) times on the following schedule: Count Time Action Livel Note 1st end of sample period 1.5 x 10-10 uti/ml (a) (1) 2nd next work day 1/2 applicable MPC for one day () " 1/4 applicable MPC on two successive days The activity recorded in the permanent records is that obtained from thirdcountmadeseven(7)daysaftertheendofthesampleperiod. If a sample exceeds the action level an investigation is made to determine the cause and corrective steps are taken immediately. The concentration determined on the third count is used for air sample records as the actual concentration above natural background (radon andthoron). April 1983 106 nfT;pyynRFLQRnRARCH CoRPoR ATioN e
.a 7.3 AIRBORNE CONTAMINATION CONTROL (Cont'd) Note: 1. This action level includes natural radioactivity up to sl.4 x 10-10, 2. Applicable M.P.C. (Maximum Permissable Concentration) is determined based on the specific isotopes'in the area sampled, and 10 CFR 20.103, 20.106. (D) Records and Reports: Individual exposures to airborne concentrations of radioactive material are determined in accordance with the requirements of 10 CFR 20.103. Reports of over-exposure to personnel are made in accordance with the requirements of 10 CFR 20.405. Management is immediately made aware of any such required report. Permanent records are on file for all daily air samples. i i l l \\ April 1983 107 e MONSANTO RESEARCH CORPORATION e
~ 8.0 RECEIPT AND SHIPMENT OF RADIOACTIVE MATERIALS 8.1 RECEIPT OF PACKAGES CONTAINING RADI0 ACTIVE MATERIALS Packages containing radioactive material are normally delivered to the licensee's site during normal working hours. A guard is present on site at all times; should a carrier arrive at the site to deliver a package containing radioactive materials during other than normal working hours, the guard will call persons appropriate to receive the shipment. In the event that a package containing greater than Type A quantities of radioactive material (as defined by Paragraph 20.205, 10 CFR Part 20) is to be picked up by the licensee at a carrier's terminal, arrangements shall be made to receive notice of the arrival of the package at the time of its arrival, and the package shall be picked up from the terminal expeditiously upon receipt of notification from the carrier of its arrival. Upon receipt of a package containing radioactive material, the external surfaces of the package shall be monitored for radioactive contamination by wipe testing except that packages containing no more than exempt quantities of radioactive materials as specified in Paragraph 20.205 of 10 CFR Part 20, packages containing only radioactive material as gasses or in special form, packages contain-ing only radioactive material in other than liquid form and not exceeding the Type A quantity limit, and packages containing only radionuclides with half-lives less than 30 days and a total quantity of no more than 100 millicuries, are excluded from the external contamination monitoring requirement. If removable radioactive contamination in excess of 0.01 microcuries per 100 square centimeters of package surface is found on the external surfaces, both the final delivering carrier and the appropriate Regional Office of the Nuclear Regulatory Commission as specified in Appendix D of 10 CFR Part 20 shall be immediately notified. Upon receipt of a package containing quantities of radioactive material in excess of Type A quantities (other than those transported by exclusive use vehicle), the radiation levels external to the package shall be monitored. Both gama and neutron radiation shall be measured at the surface of the container and at three feet from the container surface. If the total radiation level at the surfa:e is found to be greater than 200 millirem per hour, or if the total radiation level at three feet from the surface is found to be greater than 10 millirem per hour, both the final delivering carrier and the Director of the appropriate Regional Office of the NRC shall be immediately notified. April 1983 108 e MONSANTO RESEARCH CORPORATION e
~ 4 8.1-RECE1PT OF PACKAGES CONTAINING RADIOACTIVE MATERIALS (cont'd) The monitoring actions required above shall both be performed as soon'as practicable after receipt, but no later than three hours after the package is received en site if received during normal working hours, or eighteen hours if received outside of normal working hours. Required notifications shall be made to the final delivering carrier-by telephone or telegraph, and to the appropriate Regional Office of the NRC by telephone and by telegraph, mailgram or facsimile. Packages containing radioactive material shall be opened following procedures established by the-Radiation Safety Officer. 8.2 SHIPMENT OF RADIOACTIVE MATERIALS Shipments of radioactive materials from Engineered Products shall be made under 10 CFR Part 71, Paragraphs 71.5, 71.5a 71.5b,.71.6, 71.7, 71.9, and 71.12. All shipments from Engineered Products are made in D.O.T. Specification Containers or in packages for which a license. Certificate of Compliance or other approval has been issued by the ~ Nuclear Regulatory Commission. The licensee has a Quality Assurance Program which has been submitted to and approved by the Nuclear Regulatory Commission as satisfying the requirements of Section 71.51 of 10 CFR Part 71 (approval number 0248), and complies with the documentation and notification requirements of Paragraph 71.12 of 10 CFR Part 71. For these conditions of shipment, a special license under 10 CFR Part 71 is not necessary. All sources containing radioactive material shall, prior to removal from the licensee's facilities, have a label permanently marked on the ' source surface, or have a label attached to the source or source holder, which shall identify the radioactive contents and contain the words, " CAUTION RADI0 ACTIVE MATERIAL" or " DANGER RADI0 ACTIVE Methods of marking labels on source surfaces include MATERIAL". but are not limited to engraving, chemical etching, electroetching, vibratool marking, stamping, and embossing. Labels attached to sources or source holders include but are not limited to metal tags attached by means of a wire,' cable, or chain, and metal foil labels attached by means of adhesive. Source holders upon which the label may be marked or to which the label may be attached include but are not limited to devices in which the source will remain during use, and metal containers in which one or more sources are located during shipment (i.e., crimp-sealed metal cans, DOT Specification 2R inner containers, screw-top metal vials). 109 April 1983 e MONSANTO RESEARCH CoR POR ATION e
8.2 SHIPMENT OF RADI0 ACTIVE MATERIALS (Cent'd) The sources prepared to meet 10 CFR 70.39 specification shall be packed in primary containers (typically, screw-top glass jars) which bear labels similar to the following example. CAUTION A ER ,j h ,r, LQu,ie,7,* " "'!K%";EUl"'1 AMOUNT monuno awa cowennon Daft Handling instructions will accompany these sources. A sample is included on the following page. The transportation of NRC-licensed material shall be subject to all applicable regulations of the Department of Transportation and other agencies of the United States having jurisdiction. When Department of Transportation regulations in Title 49, Chapter 1, Code of Regulations, Parts 173-179, are not applicable to shipments by land or NRC-licensed material by reason of the fact that the transportation does not occur in interstate or foreign commerce, l (1) the transportation shall be in accordance with the requirements relating to packaging of radioactive material, marking and labeling of the package, placarding of the transporatation vehicle, and accident reporting set forth in the regulations of the Department of Transportation in 49 CFR Part 173, " Shipper," and 49 CFR Part 177, t " Regulations Applying to Shipments Made by Way of Common, Contract or Private Carriers by Public Highways," and (2) any requests for l modifications or exceptions to those requirements, and any notifi-cations referred to in those requirements shall be filed with, or made to, the Nuclear Regulatory Commission. 1 April 1983 110 e MONSANTO RESEARCH CORPORATION e
PRECAUTIONS IN HANDLING ALPHA PARTICLE STANDARD The enclosed alpha standard should be handled with a reasonable amount of care. Pick up source disk by its edge only. Avoid all contact with the active deposit (the approximately 1/4-inch diameter circular center region) in order to preserve calibration. To remove lint or dust from surface, use only a soft artist's brush. Avoid resting source disk on active side. Always keep source in container provided for that purpose when not actually performing instrument calibration. Directions for removing alpha standard from container. (1) Invert Jar. (2) IJnserev jar with cap (3) Remove silver disk resting on the table. (deposit is on lower face). I Plexiglas tube 5.ijf" ?s J g M \\ l MONSANTO RESEARCH CORPORATION 1515 Nicholas Road, Dayton, Ohio 45407 Area Code 513-268-3411 April 1983 111 1 I o MONSANTO RESEARCH CORPORATION e
9.0 RANGE OF POSTULATED ACCIDENTS The range of accidents postulated for the licensee's facility is detailed in Section 3.3, " Range of Postulated Accidents", of the Radiological Contingency Plan. l l l f ( 1 ( 112 e MONsANTO RESEARCH CCRPORATION e
10.0 STANDARD OPERATING PROCEDURES 10.1 GENERAL RULES OF OPERATION (A) A shoe change must be made when entering or leaving the Engir.aered Products Department controlled area. (B) Change from street clothes to work uniforms as,soon as is practical upon entering the department, or wear a smock (C) Work uniforms should not be worn further than the intersection of east-west and north-south corridors or farther than outside and immediately west of the north wing. The only possible exceptions would be emergency evacuation. (D) When going outside the restricted area (to smoke, to office, etc.) a smock (of a color other than that of smocks used inside the controlled area) must be worn to cover the work uniform. = (E) Pick up and wear film badge upon entering the controlled area. (F) Each day, the first person to work in a room in the hot area shall take random wipes around the room using tissues and checking on a survey meter. Areas found contaminated shall be decontaminated before work proceeds. Decontamination shall be done by the person finding the contaminated area or, if it is an extensive area, by persons assigned by the Manager of Manufacturing or his alternate. (G) The first person entering a room shall also make a survey for penetrating radiation, and post the findings in areas where radiation is found. (H) Persons working with sources of high radiation are required to carry pocket dosimeters and to read and log exposures daily. A log is provided near the charger-reader to record exposures. (I) People working in the hot area or with sources of high radiation shall wear wrist film badges to record hand exposures. In addition, there must be a working survey meter, suitable to the type of radiation involved, immediately available in the room for use during course of work. Every storage container must be labeled with a radiation symbol, the (J) words " Caution Radioactive Material", isotope, amount, and date. Even though this may not apply to the glove and remote boxes, a tag will be made out as the source is made and kept with the source as it is processed. . April 1983 113 o MONSANTO RESEARCH CORPORATION e
4 10.1 GENERAL RULES OF OPERATION (Cont'd) (K) Each sealed source manufactured is leak tested prior to shipping. In addition a wipe test is made and the results are recorded on the work sheet and the source shipment survey sheet in microcuries. (L) Sealed sources having a wipe in excess of 100 dpm alpha are not to be taken from the controlled process area. (H) Any material that has once been in the controlled area must be wiped and have a wipe of less than 9 x 10-6 9C1/100 cm2 (20dpm/cm2) alpha before leaving the department. (N) No person is to work alone in the controlled area with unencapsulated radioactive material. (0) No more than 100 pCi of unsealed radioactive material is to be processed in a fume hood in the hot area. 10.2 TYPICAL PROCESSING PROCEDURES FOR HANDLING RADI0 ISOTOPES IN HOT AREA The following isotope handling and source fabrication procedures are selected as typical. Other procedures may be followed if necessary. { 10.2.1 When radioisotopes are received, the shipping container is taken into the controlled support area. It is wiped to detect the possibility of leaking radioactive caterial. If contamination is found in excess of.005 microcuries, the shipper, the carriers, and the Director of Region III, Division of Compliance U.S.N.R.C. are notified. Disposition of the shipment is determined by mutual agreement between the shipper, the U.S.N.R.C. and Monsanto Research l Corporation. If excessive contamination is not found, the package is carefully opened. Further checks are made for contamination as progress is made into the various stages of packaging. If excessive levels of contamination are found, the unpacking is stopped. The shipper and the Director of P,egion III Division of Compliance, U.S.N.R.C. are notified and mutual agreement is made concerning disposition of the shipment. If the sealed container is reached without finding excessive contamination, the sealed container is then assayed unopened, if possible, by neutron, gamma counting or calorimetry to determine the isotope content to assure that license limits are not exceeded. The decision to accept or reject an apparent improper shipment shall be made by the Manager of Manufacturing. The capsule is then placed in MRC's isotope storage facilities (either an underground well or a shielded metal cabinet depending upon the type of radioactive material) for future use. Upon the need for the isotope, the capsule is withdrawn from storage and placed into a glove box or remote handling box and opened. An amount of isotope not exceeding 75 grams of Am-241 or 20 grams of i April 1983 114 e MONSANTO RESEARCH CORPORATION e
10.2.1 (Cont'd) Pu-233 is placed in a metal vial equipped with a screw cap and re-tained in a glove box for processing into individual sources as needed. Quantities up to 250 Ci of Am-241 or Pu-238 may be placed in the high level remote handling box for processing into individual sources as needed. Small quantities of other isotopes may be stored in glove boxes or remote handling boxes in preparation for processing into sources. However, efforts are made to keep this type storage to a minimum. 10.2.2 HIGH LEVEL BETA AND GAMMA SOURCES All operations, i.e., transfer of isotope, encapsulation, and decontamination, involving high level Beta and Gamma sources, up to a radiation level equivalent to approximately that of one curie of Co-60, are carried out in the remote boxes as shown in drawings C2614-AA00 and C2620-AA00. Isotopes and sources outside the remote boxes are handled in properly shielded containers. When working with a one-curie cobalt source, the calculated gamma dose at the work station is 100 mrem /hr. 10.2.3 POLONIUM-BERYLLIUM SOURCES Polonium-Beryllium sources are processed in glove boxes as shown in Drawing No. C-940. These boxes are shielded with approximctely 4 inches of benelex or polyethlene and lucite. The manufacturing procedure is as follows: (A) Transfer of Po-210 to the inner capsule is done in a glove box. Polonium is received electroplated on platinum gauzes, sealed in glass ampules. The gauzes are removed from the glass ampule and loaded into a vaporization " gun". l Vaporization gun is installed in a vacuum chamber within an l induction heating coil. Inner source capsule is inserted in a previously prepared chill l I block which is then positioned and sealed to the above mentioned vacuum chamber. l Vacuum chamber is evacuated and the vaporization gun is inductively heated to vaporize the polonium which recondenses on the walls of the inner capsule. Assuming a 50-cuire polonium beryllium neutron source capsule is l. in process a worker in front of the glove box would receive about i-9 mrem /hr. l April 1983 115 e MONSANTO RESEARCH CoRPoRATloN e
= Y' 10.2.3 POLONIUM-BERYLLIUMSOURCES(Cont'd) J (B) The Po-210 inner capsule is then sealed in the other half of a connected two box system. The inner capsule containing the Po-210 is removed from the vacuum chamber, withdrawn from the chill block, and the previously prepared beryllium target material is inserted. Capsule end cap is installed in place and a rough assay of the Po-210 content is made by calorimetry. The capsule is then mounted in the 4 welding chill block and placed in the welding rotator. End cap is welded in place using the previously established welding procedure. After visual examination of the weld, a dye penetrant test is perforned, if required by the purchaser, and if thermal conditions of the capsule do not obviate the validity of this test. Handling the above 50-curie source, a worker in front of the glove box would receive about 50 mr/hr. (C) The neutron emission is activated in a glove box. The sealed inner capsule is placed in an induction heater coil and heated to above the vaporization point of polonium. During heating the neutron emission is monitored on a rate meter and heating is stopped when no i further increase in neutron emission can be observed. Capsule is allowed to cool and is then checked for contamination. Neutron counting of the source may be performed either on the completely finished source or on the finished inner copsule, whichever is most practicable. Handling the above 50 curie source,' the worker in front of the glove box would receive 170 mr/hr. (D) Final encapsulation is completed as source dimensions dictate. Outer capsule is mounted in its welding chill block in the welding rotator and the finished inner capsule is inserted into position. Outer end cap is inserted and welded in place using the previously established welding procedure. Finished source is cleaned and final wipe test for alpha contamination is performed. Wipe test must not show sore than 9 x 10-6 uti removable alpha contamination and/or 4.5 x 10-5 pCi ~ t l removable beta-gamma. After final inspection the source is prepared for shipment. 10.2.4 PLUT0NIUM-BERYLLIUM SOURCES Plutonium-beryllium sources are processed in glove or remote boxes. i the manufacturing procedure is as follows: (A) The plutonium assay is done in a glove or remote box. Plutonium-239 metal is crushed into coarse chips using a hydraulic press. The required quantity is then weighed and recorded to the nearest 0.01
- gram, i
116 April 1983 l e MONSANTO RESEARCH CORPOR AT00N e
,. ~. 10.2.4 PLUTONIUM-BERYLLIUM SOURCES (A) (Cont'd) Plutonium-238 oxide is obtained as a powder. The required quantity is then weighed out to the hearest 0.01 gram. Assuming a 50-curie source is in process, whole-body exposures to a worker are about 25 mr/hr,10 mr/hr, and negligible for glove, inter-mediate-level, and high-level boxes, respectively during the isotope weighing step. (B) Plutonium and beryllium are combined in a glove or remote box. For plutonium-239 sources a beryllium cup is fabricated to fit within the tantalum inner container such that the total weight of beryllium is at least 50% of that of the plutonium. A recess is drilled of sufficient size to contain the required plutonium. Weighed quantity of Pu metal is loaded into the beryllium cup which is then inserted into th.e tantalum container. Tantalum plug is fitted into the tantalum container and closure made by TIG fusion weld. Capsule is then leak tested by placing in a pressure chamber and subjected to a minimum of 100 psig helium for at least 15 minutes, quickly removed and immersed in water to observe emission of any bubbles indicating leakage. If a leak is detected, repair is effected by re-welding and the capsule is retested. The sealed tantalum capsule is placed in a vacuum chamber. The tantalum capsule is heated by induction coil to 1300-1500'C to 4 initiate the exothermic reaction: Pu + 13 Be + PuBei3 This will cause the-temperature of the capsule to increase to 1800-2000 C. Induction heating is stopped on visible indication of self-heating. Reaction proceeds to completion and source is allowed to cool naturally to room temperature before being exposed to the atmosphere in order to minimize oxidation of the tantalum. The reacted material is now a neutron emitter and is handled as such. For a plutonium-238 sources, the weighed quantity of oxide is mixed L with approximately one to four times as much beryllium powder by weight. The mixture is packed into a stainless steel or other metal capsule which is closed by welding. Testing is performed as on the 239 sources. The mixture of Pu-238 and beryllium is a neutron emitter and handled as such. A worker handling a 50-curie source would receive 285, 3.4, or 0.35 [ mrem /hr, using glove, intermediate-level, and high level boxes, respectively. When Pu8Be sources containing more than 50-curies are fabricated, only the intermediate-level and high-level boxes are used. While body exposure from a 250 curie source would be 17 mrem /hr and 2 mrem /hr respectively. I i April 1983 117 ( o MONSANTO RESEARCH CORPORATION e
r 10.2.4 PLUT0NIUM-BERYLLIUMSOURCES_(Cont'd) (C) Decontamination of the inner capsule takes place in the same type box lines as where fabricated. The inner capsule is cleaned to a level less than 2000 dpm by scrubbing with solvents, soap, water, etc. The capsule is then removed from the box line. A worker cleaning a 250-curie neutron source capsule would receive 17 or 2 mrem /hr using intermediate-level, or high-level boxes, respectively. (D) Secondary encapsulation of neutron sources up to 50 curies may be done in the fume hood. Secondary encapsulation of PuBBe neutron sources up to 250 curies is conducted behind a 30-inch water shield using manipulators or remote handling devices. Tantalum or stainless steel inner capsules are inserted in the outer stainless container body. The stainless plug is inserted and closure made by TIG welding. Closure is then leak tested by helium pressure bubble test described in the above paragraphs. When working in the fume hood appropriate shielding is interposed between source and worker. When working with a 50-curie source, it would be possible to reduce radiation to below a 100 mr/hr level. When working behind the 30 inch water shield the dose rate from a 250 curie Pu8Be neutron source would be less than 2 mrem /hr. 10.2.5 AMERICIUM-BERYLLIUM SOURCES Americium-beryllium sources are processed in glove or remote boxes. The manufacturing procedure is as follows: (A) The americium assay is done in a glove or remote box. Americium-241 oxide is obtained as a powder. The required quantity is weighed out to at least 1% precision. A worker handling rc.aterial to make a 50-curie source would receive 35 mr/hr,1.0 mr/hr, or negligible radiation using glove, intermediate-level, or high-level boxes, respectively. (B) When combining americium and beryllium, a weighed quantity of oxide is mixed with approximately one to four times as much beryllium powder by weight. The mixture is packed into a stainless steel or other metal capsule which is closed by welding. The capsule is tested by a helium bubble test as described for plutonium source fabrication. A worker handling a 50-curie source after mixing is complete would receive 300, 3.3, or 0.33 mrem /hr using glove, intermediate-level, or high-level boxes, respectively. l l April 1983 118 l e MONSANTO REsEARCH CORPORATION e
I 10.2.5 AMERICIUM-BERYLLIUMSOURCES(Cont'd) (C). The inner capsule is decontamined in a glove or remote box. The inner capsule is cleaned to a level less than 2000 dpm by scrubbing With solvents, soap and water, etc. The capsule is then removed from the box line. (D) The secondary encapsulation is completed in the fume hood or behind a shielded barrier, i.e., in the secondary remote heandling facility described in paragraph 10.2.9(C). The inner capsule is inserted in the outer stainless steel capsule. The plug is inserted and closure made by TIG welding. Closure is leak tested by a helium bubble test described previously. When working in the fume hood, appropriate shielding can be interposed between source and worker. When working with a 50-curie source, it would be possible to reduce radiation to below a 100 mr/hr level. When working in the, shielded barrier facility, the worker would receive less than 30 mrem /hr from a 50-curie source. 10.2.6 REMOVAL OF CALIFORNIUM-252 RAW MATERIAL FROM SHIPPING CONTAINER (A) Intermediate Quantities of Californium-252 (500 pg or less). Shipping containers containing 500 ug or less may be opened and the package containing the isotope may be removed using approximately ~ 30-inch long tongs and immediately placed into a shielded handling i container. Estimated exposure rate is 30 mrem / minute with an estimated working time of 30 seconds. Expected dose is 15 mrem at the 500 pg level. (B) High Level Quantities of Californium-252 (500 pg to 5 mg). Quantities of Californium-252 in excess of 500 pg will be handled 1 using the secondary remote handling facilities described in section i 10.2.9 (C). The shipping container is opened and the isotope is 1 removed using remote handling manipulators. The package is placed directly into the high level remote box using the manipulators. Estimated dose rate is estimated to be 70 mrem /hr at the 5 mg level. In most cases, the shipping container will be located outside the building adjacent to the Room 7 west wall, and the Cf package is removed from the cask, moved through an opening in the building wall directly into the shielded area. This transfer is done remotely using suitable tools and devices. i e i l April 1983 119 I __,_ ___ _ __ _ _o MONS,ANTO RESE ARCH CORPOR ATION e__.__, _ _ _ ~. - -.. ~
r - m 10.2.7 PRIMARY ENCAPSULATION OF CALIFORNIUM-252 Primary capsules containing three types of Californium-252 raw material shall be made. Californium-252 as oxide, cermet pellets or cermet wire may be encapsulated. Primary encapsulation will be accomplished as fo11cws: Source Size Box Line Up to 500 pg Intermediate Remote Box or High Level Remote Box 500 pg to 5 mg High Level Remote Box (A) The primary encapsulation of Californium-252 as oxide shall be as follows: ENCAPSULATION MATERIAL Platinum alloys will be used as the material for the primary ( capsules because of their chemical, mechanical, and nuclear properties. Other metals in the precious metals group, such as rhodium, iridium, or ruthenium, may be alloyed with platinum to provide sufficient hardness for machining during capsule manufacture and to improve the ultimate and yield strength. INSPECTING AND CLEANING OF CAPSULE COMPONENTS All capsule components are carefully inspected for dimensional accuracy and machining flaws. The lower porous metal disk is flow tested after the disk is seated in the primary capsule. All metal components are thoroughly degreased and cleaned to remove cutting oil, grease, fingerprints, and dirt. Presence of these materials could cause pressure build-up during capsule sealing or the formation of undersirable products due to long-term radiolytic degradation inside the source. APPARATUS The apparatus for precipitating and filtering Cf (C 0g) 3 is 2 2 assembled and secured in the capsule loader frame and placed in a horizontal position. The precipitator flask has a cover fitted with a stopcock. The flask has a stainless steel-to-metal transition piece with tapered connection machined to mate with the primary source b capsule which serves as a filter for oxalate filtration. The interior of this transition piece is funnel-shaped to facilitate passage of the precipitate. l l April 1983 120 e MoNSANTO REsEARCH CORPORATION e [.
y r _._.~.m... 10.2.7 PRIMARY ENCAPSULATION OF CALIFORNIUM-252 (A) (Cont'd) The platinum alloy primary capsule is an open-ended tube with tapered surfaces at both ends machined to mate with the tapered connections of the transition pieces. A porous metal disk (316 stainless steel,1/8 inch diameter x 1/8 inch long, to retain 10 to 20 micron particles) is pressed against a chamber inside the primary capsule to filter the oxalate precipitate. A second transition piece connects the primary capsule with the filtrate collection tube (filtrator). A tube extends into the filtrater past a vacuum sideann. PRECIPITATION AND FILTRATION When making sources of less than 500 ug Cf, terbium is used as a carrier for the californium. Terbium was chosen because it does not form undersirable radioisotopes as a result of neutron bombard-ment and is chemically compatible with, and similar to, californium. Approximately 500 pg of terbium as the nitrate in a minimum volume of 0.lM HNO is added to the solution in the precipitator to ensure 3 complete precipitation of the californium for sources containing less than 500 ug Cf. Oxalic acid, either as a solid or in 1M solution, is added in substantial excess from that required to react with the californium. The oxalate starts to precipitate in about 5 minutes. After 30 minutes, approximately 97% of the Cf-252 has precipitated as the oxalate. After preciptiation, the apparatus is lifted to its vertical position to allow the Cf (C 0 )3 slurry to flow into the capsule 2 24 body and be filtered under vacuum through the porous metal disk. The precipitator walls, transition piece, and precipitate are 252Cf (C 0 )3 washed with a minimum volume of distilled water. 2 25 appears to be slightly soluble in cold water, so washes are normally maintained at less than 5 ml. If more than 3% of the Cf-252 introduced to the system is in the filtrate, the apparatus is disassembled and the filtrate is transferrred to a platinum crucible. The filtrate is concentrated by evaporation and transferred to the precipitator. Additional terbium carrier and and oxalic acid are added to precipitate the remainder of the Cf-252, which is then filtered through the same porour metal disk. If the filtrate contains less than 3% of the Cf-252 introduced, it is placed in a collection flask to be reprocessed later as feed for another source. l April 1983 121 e MONSANTO RESEARCH CORPORATION e
10.2.7 PRIMARYENCAPSULATIONOFCALIFORNIUM-252(A)(Cont'd) The apparatus is carefully disassembled and the primary capsule 252Cf (C 0 )3 is placed in a specially designed press. containing 2 2% A second porous metal disk is pressed into the top of the primary capsule so that it retains the 252Cf (C 0u)3 in a cavity approximately 2 2 1/8 inch above the bottom disk during calcination. The primary capsule is placed in a quartz tube and inserted into a small furnace. The temperature is raised slowly to 200'C and held for one hour to dehydrate the precipitate. The temperature is then raised to 700'C for 30 minutes to convert the oxalate to the oxide. Volatile products escape through the porous disks, while the californium oxide is retained in the capsule cavity. The temperatures reached during calcining assure that the oxalate is converted completely to oxide and that all moisture and carbon dioxide have been evolved from the capsule before the final seal is completed. Dose rates for these operations are 57 mrem /hr when handling 5 mg. californium. ENCAPSULATION Tapered end plugs of platinum alloy are pressed into the openings of the primary capsule and are seal welded circumferentially with an argon-shielded, tungsten-inert gas arc. The sealed primary source is pressurized in 100 psi helium for 15 minutes. The capsule is leak tested by immersing in water and inspecting it for bubbles that would indicate a leak. All capsules must show no detectable leaks before secondary encapsulation. Following the leak test, the primary capsule is decontaminated inside the shielded remote handling box. Estimated dose rate: 60 mrem /hr for 5 mg. californium. RADI0 ACTIVE WASTE The radioactive waste from this process will be packaged in drums, and shielded as may be necessary. Any liquids would be solidified, then treated as solid waste. Handling of these wastes will be in accordance with section 6.6. i l (B) The primary encapsulation of Californium-252 as cermet wire and cermet pellets shall be as follows: l ENCAPSULATION MATERIAL l Capsules of 304 L, zircalloy or other corrosion-resistant metal shall be used. l l l April 1983 122 l l t
!; ~. p. ..r - w.m.ww.a.m.v a,,. w;w u..x.. ; n-10.2.7 PRIMARY ENCAPSULATION OF CALIFORNIUM-252 (B) (Cont'd) INSPECTION AND CLEANING 0F CAPSULE COMPONENTS All capsule components are carefully inspected for dimensional accuracy and machining flaws. All components are throuchly degreased and cleaned to remove cutting oil, fingerprints and dirt. Presence of these materials could cause pressure build-up during capsule sealing or fomation of undersirable products due to long term radiolytic degradation inside the source. PREPARATION FOR ENCAPSULATION Cermet pellets normally are encapsulated in the same form as they-are received. The cermet wire may be used as stock for sources varying in neutron output. The wire is of a known concentrat. ion of Cf-252 per unit length and is cut to proper length to give the. proper neutron output. The cermet pellet or cut length of cermet wire is then placed in the capsule. In some cases, cermet pellets may also be cut into smaller pieces prior to insertion into the inner capsule. ENCAPSULATION i The end plug shall be pressed into the opening of the primary l capsule and seal welded with an inert-gas shielded tungsten-fr.ert gas arc. The sealed primary source is pressurized in 100 psi' helium for 15 minutes. The capsule is leak tested by imersing in water and inspecting it for bubbles that would indicate a leak. All capsules must show no detectable leaks before secondary 4 encapsulation. t Following the leak test, the primary capsule is decontaminated I inside the shielded remote handling box. Estimated dose rate: 60 mrem /hr. for 5 mg. californium. RADIOACTIVE WASTE The radioactive waste from this process will be packaged in drums, and shielded as inay be necessary. Any liquids would be solidified, then treated as solid waste. (C) Cf-252 primary capsules fabricated in-house or purchased from an out-of-house supplier shall meet special form requirements as determined by MRC engineering design analysis or be of USDOE Savannah River SR-CF-XX SF-CF-IX, or other designs subsequently approved by the USDOE. The primary source capsule will have passed l a leak test to assure source integrity. t i f April 1983 123 i 5 I... - __.. _ _. ~. _. _e.M. ONSANTO RESE ARCH CoRPoR ATioN e. _.... _.. _... _,... _ - _. _ _ _ _ - _. _ _ _
10.2.8 SECONDARY ENCAPSULATION OF CF-252 This procedure covers the encapsulation of Cf-252 in a secondary capsule. The steps to be followed are as follows: (A) The primary capsule containing the Cf-252 will be passed from the remote handling box directly into a shielded remote handling facility. Any temporary outer secondary enclosures are removed. The primary capsule is visually inspected, and wipe tested. If necessary the primary capsule is cleaned. All operations are carried out remotely. Estimated dose rate: 70 mrem /hr. for 5 mg. californium. (B) Using remote handling devices the capsule is inserted into a secondary capsule and the end cap inserted. Estimated dose rate: 70 mrem /hr. for 5 mg. californium. (C) The secondary capsule containing the primary Cf-252 capsule is then TIG welded. After welding, the completed source is inspected and wipes taken and counted to insure that removable contamination is less than that specified in Section 6.7.2. Estimated dose rate: 70 mrem /hr. for 5 mg. californium. (D) The welded secondary capsule is helium bubble tested and decontaminated to the level specified in Section 6.7.2. Secondary capsules must also show no detectable leaks before calibration and shipment. Estimated dose rate: 70 mrem /hr. for 5 mg. californium. (E) The source content is determined by one of the following methods: (1) For sources containing only cermet wires and/or pellets fabricated by the Department of Energy (D0E), none of which have been altered after assay by DOE, and for which content assays from DOE are available, the source content is taken to be the sum of the individual wire and pellet assays as measured by DOE. (2) For sources containing cermet wires and/or pellets which have been altered following assay by DOE or which have been made by the " wet method", source content is determined by. comparison of the neutron output of the source to that of a neutron source whose output is traceable to the National Bureau of Standards. The comparison may be made using a long counter consisting of a BF3 tube inside a moderator with the source being measured and the NBS-traceable source being individually counted at the same distance from the long counter. Alternately, a tub counter consisting of one or more BF3 or fission counting tubes inside a moderator and a cavity for the source being counted April 1983 124 e MoNSANTO RESEARCH CORPORATION e
( .u~.., m?, .=. - e..- x 10.2.8 SECONDARY ENCAPSULATION OF CF-252 (E) (Cont'd) also inside the moderator may be used, with the source being measured and the NBS-traceable source being individually counted with the same source-countine tube geometry. Estimated dose rate for either method: 70 mrem /hr for 5 mg. californium. (F) The completed sources are shipped in compliance with applicable NRC and DOT regulations. 10.2.9 FACILITY SAFETY ANALYSIS FOR NEUTRON SOURCES UP TO 5 MG CF-252 AND 250 Cl 0F PU-238 OR AM-241 Two distinct facilities are to be used for the handling of radio-active materials having radiation intensity greater than 1.3 x 108 n/sec. A totally enclosed stainless steel remote handling box is employed for handling bulk neutron emitting material and for primary encapsulation. _The second remote handling facility is used for handling encapsulated sources (secondary encapsulation, counting, loading and unloading shipping containers, etc.) and thereby does not require or employ atmospheric control. Both facilities are heavily shielded and served by master-slave manipulators. The two facilities are connected by a remotely operated transfer system. (A) Enclosed remote handling box (Dwg. C2620-AA00). The enclosed remote handling box is constructed of 1/4 inch thick type 304 stainless steel plates welded together with stainless steel channel and angle members welded to the box exterior to provide increased stiffness. It is located in Room 6 (See Dwg. No. A2608-L-02) and is approximately 13 feet long by 31/2 feet deep by 7 feet in height, and is supported by a 38 inch high concrete pedestal. The box is divided into two interconnected cells. The operating position of the facility is shielded by a 22 inch thick water shield. Boric acid or other materials having low-energy capture gammas may be added to the water in the shield. One pair of master slave manipulators is provided for each cell. The side of the facility opposite that of the normal operating location contains a number of glove ports and windows for use in set-up and maintenance operations. This area is only lightly shielded and is used only when permission is granted by the Radiation Safety Officer. April 1983 125 e MONSANTO RESEARCH CORPORATION e
... ~ ......c I 10.2.9 FACILITY SAFETY ANALYSIS FOR NEUTRON SOURCES UP TO 5 MG CF-252 AND 250 CI of PU-238 or AM-241 (A) (Cont'd) Three air-lock type pass boxes provide access of material into and out of the facility. In addition, an air-lock type remotely operated pass box connects with the secondary remote handling facili ty. (B) Safety and Control Features. CONTAINMENT WINDOWS All windows in the containment box are composed of two successive panes of 1/2 inch thick safety plate glass. No escape of material will occur if either pane in a particular window is damaged; design is such that window glass may be replaced with negligible escape of material from the facility. AIR FLOW AND FILTER SYSTEM The facility is maintained at one inch of water negative pressure by attachment to the pressure regulated exhaust system shown in Dwgs. A2608-L-02, A2608-L-04, and B2608-L-06. Exhaust is through four 10-inch diameter absolute filters (Cambridge Model 10E110-0 or equivalent), each of which has a capacity of 85 cfm. The fileters are each housed in a stainless steel canister bolted to the rear wall of the facility, and are replaceable by a push through technique. The cansister air exhaust is through stainless steel ducts and manifolds into the central exhaust system and thence through a second absolute filter to the atmosphere. PASS BOXES All pass boxes are of the double door design and all are provided with a venting system which automatically provides an inward flowing air stream when the outer door is opened with the inner door closed. No air flows when the outer door is closed and the inner door is open. Air drawn into the pass boxes passes into the adjacent cell of the facility. One pass box per cell is so designed as to be operable from either side of the 22 inch shiled allowing the operator to pass hardware, tools, etc. into the box from the low radiation side of the shield. Air velocity into these boxes with the outer door open is in excess of 100 ft/ min. A third pass box is used for the transport of large items into the cell. This box may be decontaminated through a pair of glove ports prior to opening the outer door. April 1983 126 n r$0ZOANTO RESEARCH CORPORATION e
f. 10.2.9 FACILITY SAFETY ANALYSIS FOR NEUTRON SOURCES UP TO 5 MG CF-252 AND 250 Cl 0F PU-238 OR AM-241 (B1 (Cont'd) SHIELD The shield consists of 22 inches of water o'r water solution contained in a tank having 1/4 inch thick steel walls. Shield windows consist of 22 inches of water or water solution contained by one. inch thick Plexiglass plates and a steel frame. All materials in the main shield are non-flammable. MAINTENANCE AND SET-UP AREA Access to this area is through a locking door; such access is controlled by the Radiation Safety Officer. Glove attachement is by double "0" ring and hose clamp. Inner and outer port covers are provided to prevent damage to gloves during periods of non-use. The inner cover has a metal plate entirely covering the port and a rubber gas seal which contacts the inside of the port tube. B0X ATH0 SPHERE The atmosphere within the box may be replaced with inert gas (either heavier or lighter than air). Inert atmospheres are used in certain manufacturing operations and/or operations presenting a fire hazard. FIRE DETECTION An automatic in-cell fire detection and extinguishing system is provided. (C) Secondary Remote Handling Facility This facility is located in Room 7. The facility consists of a 21/2 foot thick x 10 foot long shield tank filled with water or water solution. A water shield window runs essentially the entire length of the shield wall, and forms the upper portion of the. tank wall. A pair of nester slave manipulators are mounted on horizontally movable mounts above the shield window. The wall is located about 5 feet north of the present north wall of Room 6. l Radioactive materials are handled in the space between the room I wall and the shield, with the operator location being just north of the shiled wall. A remotely operated transfer system connects the " radioactive handling area" with the enclosed remote handling box facility. Drawing A2608-L-02 shows the facility layout. l i e 1 i l 1 27 i e MONSANTO RESEARCH CoRPORATHON e
[ ;-. -,. s... ........:.. -.... a..............:......:..,....-... 9 OPERATIONS MANUAL APPENDIX
- 1. -WORK CERTIFICATION FORM 2.
WORK PERMIT 3. MONSANTO ANNUAL REPORT-1982 O 128 600 @@RP@ RATION e
if J L MONSANTO RESEARCH CORPORATION ENGINEERED PRODUCTS DEPARTMENT WORK CERTIFICATION - NUCLEAR Name Page 1 of 6 AREAS OF CERTIFICATION - WORK AUTHORIZATION: I. MANUFACTURING OPERATIONS Initial Date 1. Limited Work Without Supervision a) Support Area b) Hot Area c) Glove Boxes 2. Personal Protection, Decontamination 3. Isotope Powder Handling in Glove Boxes and Hot Cells - Inventory & Control 4. Product Cleanliness - Box & Cell 5. Pass Box Procedures 6. Glove Changes - Box & Cells 7. Hot Trash Removal - Box & Cells 8. Target Material Handling a) Beryllium Metal Powder bl Lithium Hydride Powder c) Calcium Floride Powder d) Boron Metal Powder 9. Isotope Limits - Boxes Cells, Fume Hoods, Hot Area, Support Area 10. Read & Understand Operations Manual Section 10, Standard Operating Procedures. 11. Examination / Marking / Cleaning Capsules Before Use 12. Preparation of Isotope / Target Powder Mixes a) Calculations from M.0. Instructions b) Volume Content Check of Capsule c) Combining & Mixing Powders in Cells & Boxes Rev 2 (2-79) ~
F-s, h Name Page 2 of3 _ AREAS OF CERTIFICATION - WORK AUTHORIZATION: I. MANUFACTURING OPERATIONS (Cont'd) Initial Date
- 13. Source Encapsulation a)
Loading Inners b) Pelletizing Powder Mixes c) Inner Capsule Assembly d) Welding Inner Capsele e) Leak Testing Inner Capsule f) Decontamination of Inner Capsule g) Removal of Inner Capsule from Cells / Boxes h) Loading / Welding Outer Capsules i) Leak Testing Outer Capsules jl Collection / Recording Mfg. Data
- 14. Operation of Hot Area Equipment a)
T.I.G. Welding Facility b) Welding Rotators - Cells & Boxes c) Master-Slave Manipulators d) Shaker Mill & Ball Mills e) Hydraulic Presses f) Rotary Decontamination Scrubber g) Pressure / Vacuum Bubble Test Station hl Electronic Load Cell Balance 1) Torsion Balance j) Electronic Beam Balance k) Hydrostatic Pressure Test Station 1) Manual & Remote Lathes m) Ovens, Furnaces, Hot Plates, etc. n) X-Ray Facility k
l y 11 v L rt.i. - Name s Page_ 3 of 6 - AREAS OF CERTIFICATION - WORK AUTHORIZATION: g-I. MANUFACTURING OPERATIONS (Cont'd) Initial Date
- 15. Use of Radiation Measuring Equipment a)
Alpha Survey Meters b) Gama Survey Meters f~ c) Neutron Survey Meters d) Long-Tube Neutron Counter .e) Tub-Type Neutron Counter l-i f) In-Cell Neutron Counter g) Gama Pulse Height Analyser h) Alpha Pulse Height Analyser i) Beta Spectrum Analyser j) Alpha Single Channel Analyser k) Low Geometry Alpha Counter (LOGAC) 1) Ga' Proportional Alpha Counter s
- 16. Operation of Support Area Equipment a)
L1thes, Grinding Wheels, Drill Press, etc. b) Power Hand Tools (Drills, Saws, Grinders, etc.) c) Plasma-Arc Welder d) Balances e) Ovens & Furnaces
- 17. Operation of Outside Equipment a)
~ Fork Lift' b) W.E.P. Mixer Facility c) Spray Paint Equipment d) Vapor Degreaser
- 18. Preparation / Handling Isotope Solutions a)
In Glove Boxes & Cells b) in Fume Hoods I --__s
3 Name Page 4 o,5 3 AREAS OF CERTIFICATION - WORK AUTHORIZATION: I. MANUFACTURING OPERATIONS (Cont'd)
- 19. Use of Basic Measuring Equipment (i.e., Micrometers, Calipers, Depth Gages, neight Gages, Dial Indicators, etc.)
- 20. Conditional / Limited Work Authorization:
a) b) c) d) II. QUALITY CONTROL 1. Tolerances and Specifications 2. Use of Q.C. Inspection Equipment 3. Inspection of Hardware 4. Leak Test of Seal Welds a) Wipe Test b) Pressure Bubble Test c) Hot Water Bubble Test d) Dye Penetrant Inspection e) He Leak Test Operation f) X-Ray Interpretation g) Vacuum Bubble Test l 1
l O Name Page 5 of 6 a AREAS OF CERTIFICATION - WORK AUTHORIZATION: ~ II. QUALITY CONTROL (Cont'd) Initial Date 5. Metallographic Operations a) Cut and Mount Samples b) Polish Samples c) Use of Met. Microscope 6. Operation of Equipment a) He Leak Detector b) Calorimeter c) Neutron Counter d) Low Geometry Alpha Counter ~ e) Hydrostatic Test Equipment f). Bubble Tests - Pressure & Vacuum 7. Q. C. Paper Work III. HEALTH PHYSICS 1. Contamination Limits 2. Contamination Survey Requirements (Fixed & Transferable) 3. Decontamination Methods 4. Use of Protective Clothing & Equipment 5. Radiation' Survey Requirements 6. Use of Survey Equipment
- 7. ' Control of Personnel Exposure 8.
Use of Radiation Signs 9. Labeling Requirements (Areas & Sources) 10. Film Badge Requirements 11. Understand & Comply with Section 6.0 of Procedure Manual i
r l ) Name Page 6 of 6 AREAS OF CERTIFICATI01 - WORK AUTHORIZATION: s t III. HEALTH PHYSICS (Cont'd) Initial Date 12. Change Line Procedure I-13. Operation of Wipe Counting Equipment 14. Operation of Survey Meters 15. Operation of Automatic Sample Counter 16. Basic Understanding of Types & Effects of Radiation 17. Personal Contamination Survey Method I Employee Signature Date [ Approved by: l Date Radiation Safety Officer Date}}