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HomeMy WebLinkAboutDRC-2018-003873 - 0901a068807fcab2Div of Waste Management and Radiation Control CLIVE SITE APR 2 4 2018 LETTER OF TRANSMITTAL -19-ge-Z0/0-003e73 DATE: 04/24/2018 ATTN: Don Verbica — DWMRC CC; Treesa Parker Karen Kirkwood RE: Transmittal 18013 Description of Documents Transmitted Qty See attached for an update to Radiation Safety; CL-RS-PR-130 Rev 6, Radiological Control Please replace your current procedure revisions with the documents with in this Transmittal. You are not required to sign any documents to verify receipt of this distribution. However, you should make every effort to ensure that your copy of the License is current. FROM: EnergySolutions Document Control Clive Facility ENERGYSOLUTIONS CL-RS-PR-130 Radiological Control Revision 6 Authored By: z/JA Mark White Apr 23 2018 5:54 PM Mark White, Radiation Safety Specialist Date Reviewed By: Oa- 14, Dale Thome Apr 23 2018 5:56 PM Dale Thorne, Lead, Health Physics/ARSO Date Approved By Stephen J. Long Apr 23 2018 6:01 PM cosign Stephen Long, Lead, Health Physics/ARSO Date Thomas Brown Apr 23 2018 6:46 PM Approved By Thomas A. Brown, Radiation Safety Officer (RSO) Date Z Non-Proprietary fl Proprietary O Restricted Information O Safeguards Information 0 Sensitive Security Information O New O Title Change Z Revision 0 Rewrite O Cancellation Electronic documents, once printed, are uncontrolled and may become outdated. Refer to the Intranet or the Document Control authority for the correct revlsion. CL-RS-PR-130 Radiological Control Revision 6 Table of Contents 1 PURPOSE AND SCOPE 3 1.1 Purpose 3 1.2 Scope 3 2 REFERENCES 3 3 GENERAL 3 3.1 Definitions 3 3 .2 Responsibilities 4 3.3 Precautions and Limitations 4 4 REQUIREMENTS AND GUIDANCE 4 5 ATTACHMENTS AND FORMS 7 Non-Proprietary Page 2 of 9 CL-RS-PR-130 Radiological Control Revision 6 1 PURPOSE AND SCOPE 1.1 Purpose The purpose of this procedure is to define the methods used for controlling radioactive material and radiological contamination. 1.2 Scope This procedure applies to all personnel normally entering and exiting the Restricted Area. This procedure does not apply in emergency situations where other concerns supersede the need for immediate monitoring of radiological conditions. 2 REFERENCES 2.1 11e.(2) Material License, UT 2300478 including the Application 2.2 Radioactive Material License, UT 2300249 including the Application 2.3 CL-RS-PR-140, Radiation Work Permit 2.4 CL-RS-PR-120, Access Control Points 2.5 CL-RS-PR-160, Radioactive Source Inventory and Leak Test 2.6 CL-RS-PR-210, Personnel External Radiation Monitoring 2.7 CL-SR-PR-041, Incoming Radioactive Waste Shipment Acceptance 2.8 CL-SR-PR-060, Shipment of Radioactive Material 3 GENERAL 3.1 Definitions 3.1.1 Radioactive Material (RAM) — Any material or combination of materials that spontaneously emits ionizing radiation. 3.1.2 Survey — An evaluation of the radiological conditions and potential hazards associated with the object being evaluated. When appropriate, such an evaluation includes a physical survey of the location of radioactive material and measurements or calculations of levels of radiation, or concentrations or quantities of radioactive material present. 3.1.3 Contact Dose Rate — A measurement of the radiation exposure per unit time at a distance of no greater than 1 cm from the object being measured. 3.1.4 Restricted Area (RA) — The area within the controlled area that requires control of access and occupancy for radiation protection purposes. The RA boundary is posted "Caution, Radioactive Material" and is bordered by a 6-foot high fence except in buildings where a lockable door or other device to prevent unauthorized or inadvertent entry is present. A security badge and dosimetry is required for entrance into the RA. Non-Proprietary Page 3 of 9 CL-RS-PR-130 Radiological Control Revision 6 3.1.5 Radiological Contamination — The presence of RAM in contact with an object that does not benefit from the presence of the RAM. 3.1.6 Personal Protective Equipment (PPE) — Garments or accessories used by an individual to reduce exposure to hazardous materials. 3.2 Responsibilities 3.2.1 The Radiation Safety Officer (RSO) is responsible for overall radiation safety, contamination control, and compliance with state and federal regulations and for daily oversight of the radiation protection program in accordance with the Clive Radiation Protection Program. 3.2.2 Radiation Safety Technicians (RSTs) are responsible for ensuring that all activities at the site are carried out in accordance with all applicable procedures. 3.3 Precautions and Limitations None. 4 REQUIREMENTS AND GUIDANCE 4.1 General Requirements 4.1.1 Personnel performing any RAM handling operations, including incoming acceptance inspections and surveys shall perform work in accordance with CL-RS-PR-140, Radiation Work Permits (RWP). 4.1.2 At a minimum, a Radiation Safety Technician shall be on site when personnel are working within the RA. 4.1.3 All personnel and items that enter the Energysolutions' RA shall comply with CL-RS-PR-120, Access Control Points. 4.1.4 Regardless of quantity, all contact with RAM and radiological contamination shall be minimized. Appropriate PPE shall be used whenever personnel handle RAM or radiologically contaminated objects. 4.1.5 All personnel issued a dosimeter shall use it in accordance with the CL- RS-PR-210, Personnel External Radiation Monitoring procedure, to monitor exposure to RAM. This requirement applies both inside and outside the RA. 4.1.6 All Radiological Controls are implemented in order to keep exposures as low as reasonably achievable (ALARA). 4.2 Identification of Radioactive Material 4.2.1 RAM such as Hepa Vacuums, Hepa Units, "Mud Boxes", Bag Houses, and Frac Tanks should be identified by a label that displays at least the following information: • The standard trefoil radiation symbol Non-Proprietary Page 4 of 9 CL-RS-PR-130 Radiological Control Revision 6 • The words, "Caution, Radioactive Material" • The contact dose rate • The date that the contact dose rate was measured • The initials of the RST who obtained the contact dose rate Note: An example of an acceptable RAM label is included in this procedure in the Examples of Labels, Attachment 5.1. 4.2.2 Radioactive Check Sources and Nuclear Gauges shall be identified by a label that displays at least the following information: • The standard trefoil radiation symbol • The radionuclide(s) • The activity of the Source Material • A reference date for the recorded activity 4.2.3 Waste packages shall be identified by the labels required by CL-SR-PR- 041, Incoming Radioactive Waste Shipment Acceptance 4.2.4 Outgoing RAM shipments shall be identified by the labels required by the CL-SR-PR-060, Shipment of Radioactive Material. 4.3 Control of RAM 4.3.1 Check Sources and Nuclear Gauges shall be stored in a secure location and an inventory shall be taken on all sources every 6 months. Sources shall be tested for leaks in accordance with CL-RS-PR-160, Radioactive Source Inventory and Leak Test. 4.3.2 All RAM arriving at EnergySolutions shall receive a survey by a RST either at acceptance or during unloading. 4.3.2.1 All waste packages 4 mrem/hr or greater at 30cm placed in temporary storage shall have the highest 30 cm dose rate recorded by the RST on the required label. Note: Shipments that arrive by rail are excluded from the requirement of 4.3.2.1 4.3.2.2 When the 30 cm dose rate exceeds 4 mrem/hr, the RAM shall be posted as a Radiation Area in accordance with the CL-RS-PR-150, Posting Requirements for Radiological Hazards, or an RST shall be present to ensure exposure is minimized. 4.3.2.3 When the 30 cm dose rate exceeds 80 mrem/hr, the RAM shall be posted as a High Radiation Area in accordance the CL-RS-PR-150, Posting Requirements for Radiological Non-Proprietary Page 5 of 9 CL-RS-PR-130 Radiological Control Revision 6 Hazards. In addition, the RAM shall be stored in a locked location that prevents inadvertent exposure to >80 mrem/hr. Whenever the RAM is not in locked storage, an RST II shall accompany the RAM to ensure exposure is minimized. 4.3.3 All RAM shall be stored inside the RA. When it is necessary for RAM to be brought outside the RA, it shall be done so under the cognizance of an RST and approved procedures. 4.4 Control of Radiological Contamination 4.4.1 Personnel inside the contaminated portion of the RA shall minimize the spread of contamination. 4.4.2 Personnel shall practice good housekeeping. 4.4.3 When a Personnel Contamination event is suspected, personnel shall contact a RST for survey in order to determine its levels and further action. 4.4.4 Waste shall be stored in a secure container. 4.4.5 Dust suppression shall be employed at the Rollover, IUF, Disposal Cells, haul roads, shredder and any other facility when called for by any employee or contractor of EnergySolutions . 4.4.6 Disposable PPE designated for training purposes shall be marked "For Training Use Only". 4.4.7 Newly purchased PPE designated for use in the Restricted Area, which has not been used may be stored outside of the Restricted Area. 4.4.8 Tools shall not be brought into the Radiologically Contaminated portion of the RA unless an adequate tool is not available in the Radiologically Contaminated portion of the RA. 4.4.9 When special tools or equipment are required for work in the Restricted Area, which are not available in the Restricted Area, wrapping/sleeving shall be considered to minimize the potential for contaminating the object. 4.4.10 Prior to any type of maintenance/repairs on vehicles or equipment in the Radiologically Contaminated portion of the RA, Radiation Safety shall be notified for survey. 4.4.11 The individual performing the maintenance/repairs shall contact a RST for survey. • The RST shall survey the part of the vehicle or equipment to be worked on, including the work area. • The RST shall consult with the applicable Site Manager and the individual who shall be performing the work to determine the Non-Proprietary Page 6 of 9 CL-RS-PR-130 Radiological Control Revision 6 additional Radiological Controls required for work, if any, or if decontamination is required. • The RST shall authorize the maintenance/repairs when he/she is satisfied that the Radiological Controls are sufficient to allow the work to be completed ALARA. 5 ATTACHMENTS AND FORMS 5.1 Example Radioactive Material Label Non-Proprietary Page 7 of 9 aution z CL-RS-PR-130 Radiological Control Revision 6 Attachment 5.1 - Radioactive Material Label (Example) RADMACTWE MATERIAL, 463, __,....- m R it u - , 40 ilk) Tt. Ilt; _ R e In 1701. a t4p.c4n t inn in :loon ..-- , on , A 0 Item - 4 :!... - . 1 '', 41 p i tt t Pt1 VI* t a int Hilt t i 0 111, 1:74r Pe il'e -, AVIV! i 04t 471W' 0. • '' . e 1;14.,' dp113 Milt-, • ) m at ell t •*,..V-T ....., -- .. a tO - f. Tl 0 • ..• :. , Non-Proprietary Page 8 of 9 CL-RS-PR-130 Radiological Control Revision 6 DOCUMENT SUMMARY FORM Please provide the following information for new/revised documents. Forward the completed form, review comment forms, approved document, and electronic file, to Document Control. Document No.: CL-RS-PR-130 Revision No.: 6 , Title: Radiological Control Special Status (i.e. Restricted; SSI; etc.): NA If special status is applicable, please note any special distribution/handling requirements: NA Summary of changes (if this is a revision):. - Deleted definition 3.1.7 to Visibly Clean. Dyes VI No 0 Yes 5( No This document requires evaluation per the requirements of a license. If yes, attach evaluation results. This document requires regulatory agency approval before implementation. If yes, contact Document Control. Type of revision: 0 Contains technical changes T Contains only administrative changes Distribution (or changes to distribution) for controlled copies of this document. NA Non-Proprietary Page 9 of 9