ML17117A450
| ML17117A450 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/21/2017 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17117A433 | List:
|
| References | |
| L-17-029 | |
| Download: ML17117A450 (233) | |
Text
BVPS UFSAR UNIT 1 Rev. 26 11.4-1 11.4 RADIOACTIVE MATERIAL SAFETY 11.4.1 Materials Safety Program 11.4.1.1 General Radiation protection procedures document the policies, procedures, guidelines and limits which
are authorized, implemented and enforced as a radiation protection program. All personnel assigned to the site are required to follow these rules and procedures. These radiation protection procedures also establish the detailed program which prescribes the requirements for receipt, marking, handling and storage of all radioactive materials at BVPS. Station procedures govern each of these functions with regard to byproduct, source and special nuclear material. The station Radiation Protection Section controls the receipt, marking, handling and storage of all radioactive materials in accordance with written radiation protection procedures.
All BVPS-1 personnel who handle radioactive materials receive appropriate training and instruction. This training and instruction shall be adequate to assure that such materials are handled in an approved and safe manner. 11.4.1.2 Byproduct Material Except for radioactive calibration sources, radiochemistry standards or material installed in instrumentation as check sources, the only other byproduct materials at BVPS are those generated as a result of reactor operations. All radioactive calibration sources and
radiochemistry standards are retained in secured storage facilities when not in use. The receipt, storage, handling and use of these standards in accordance with radiation protection procedures requires authorization of the Manager, Radiation Protection and is normally limited to the Radiation Protection and Chemistry Sections. The use of unsealed reference byproduct material sources is normally limited to the radiochemistry laboratory as described in 11.4.2. Accountability procedures are established in radiation protection procedures which apply to all radioactive standards and account for any other byproduct materials such as contaminated materials and wastes, irradiated components and materials which are released from radiologically controlled areas.
The receipt possession and use of source, byproduct and special nuclear material as authorized
by the Operating License will be in accordance with NRC regulations in 10 CFR Parts 30, 40 and 70, including 10 CFR Sections 30.33, 40.32, 70.23 and 70.31. 11.4.1.3 Special Nuclear Material The use of Special Nuclear Materials at BVPS-1 is limited to the nuclear fuel, to fulfill core and reactor coolant system monitoring and surveillance requirements and as neutron sources. The initial receipt and storage of Special Nuclear Material is governed by a Special Nuclear Material license in accordance with 10 CFR 70.21 and will utilize the fuel storage building facilities for storage. Security and accountability practices consistent with NRC requirements are established and maintained in accordance with a BVPS-1 manual developed specifically for this purpose. Initial core loading and all subsequent handling of Special Nuclear Material will be in accordance with current and approved written procedures. Except for possible use of the
BVPS UFSAR UNIT 1 Rev. 26 11.5-1 11.5 PERSONNEL RADIATION PROTECTION 11.5.1 Radiation Protection Program Organization, Objectives and Responsibilities The Radiation Protection Program organization, objectives and responsibilities for Unit 1 are as provided in the Unit 2 UFSAR.
11.5.2 Dose Control
The basic criterion used for control of airborne radioactivity is that internal radiation exposure resulting from inhalation of airborne activity should be minimized to such an extent that monitoring to determine internal exposure should not be necessary consistent with maintaining Total Effective Dose Equivalent (TEDE) ALARA. Radioactivity may become airborne through operations such as welding or grinding a contaminated component, decontamination of such components, leakage from a system containing radioactive fluids or gases, or disturbing the deposited activity in various areas of the plant. An airborne sampling location is selected on the basis of potential for airborne activity within the work area.
The first defense against inhalation exposure is in the design of the ventilation system in the Radiologically Controlled Area. The design philosophy of the various ventilation systems includes consideration for minimization of airborne contamination. In addition, other steps are
taken to maintain the inhalation exposure and TEDE ALARA. The first of these steps is to minimize the sources of potential airborne radioactivity. Since area or equipment contamination can become airborne, such contamination can be a significant source. This source is minimized by proper contamination control procedures. Such procedures are spelled out in the radiation protection procedures. However, a general outline is as follows:
- 1. Establish allowable limits for plant areas and maintain the major portion of the plant within these limits.
- 2. Limit the number of contaminated areas and decontaminate these periodically as warranted to maintain contamination levels in these areas as low as practicable.
- 3. Control all work which involves or potentially involves significant quantities of radioactive contamination, with the objective of maintaining levels as low as practicable and preventing the material from becoming airborne. Containment (enclosures around work area, glove box arrangements, etc.) will be considered
for work with very high contamination.
- 4. Perform routine contamination surveys, checks, and work surveillance to ascertain status of areas and equipment.
- 5. Properly package, handle, and/or store radioactively contaminated materials.
- 6. Maintain stringent personnel frisking (contamination monitoring) requirements.
BVPS UFSAR UNIT 1 Rev. 26 11.5-3 3. All Radiation Areas of the plant, as defined by 10 CFR 20, shall be maintained within a radiologically controlled area. It is expected that areas in the plant where radiation levels may exceed one mrem per hour will normally be within the Radiologically Controlled Area.
Radiation areas are posted in accordance with 10 CFR 20. Radiation protection procedures define the specific posting and access requirements.
- 4. High Radiation Areas and Very High Radiation Areas, as defined by 10 CFR 20, will be posted in accordance with 10 CFR 20 and access to these areas will be controlled in accordance with Technical Specification 5.7 and radiation protection procedures.
- 5. During reactor operation, high radiation areas may result in certain areas which otherwise would not be high radiation areas. Operational, radiological, and administrative controls are in place to preclude unauthorized entry to these areas.
Entries into the Reactor Containment Building or the Volume Control Tank Area during reactor operations will require authorization of the Nuclear Shift Supervisor
of the applicable unit. The procedures for authorization to enter these areas are contained in the site administrative procedures and radiation protection procedures.
- 6. Process piping which may carry radioactive materials through habitable areas of the site are placed as shown on engineering drawings. Radiation exposure to
plant personnel is minimized to as low as reasonably achievable (ALARA) by providing specifically designed radioactive pipe trenches, pipe tunnels and shielded areas for this radioactive piping and equipment. In addition, radiation exposure to plant personnel is limited by compliance with OSHA Section 1910.96, 10 CFR 20 and radiation protection procedures.
- 7. Dose control criteria are utilized to establish administrative control and check on the accumulated exposure of each individual. Their purpose is to ensure that all exposures are kept within 10 CFR 20 limits and as low as reasonably achievable (ALARA). These criteria are detailed in radiation protection procedures. Some of
the provisions are:
- a. Each individual is authorized to receive exposure based on administrative controls prescribed in radiation protection procedures, or as required by 10 CFR 20.
- b. The individual's exposure status will be made available to the individual and his/her supervisor.
- c. Additional exposure authorizations may be granted after the thermoluminescent dosimeter (TLD) badges are processed or as
prescribed in radiation protection procedures.
BVPS UFSAR UNIT 1 Rev. 26 11.5-8 An exposure tracking system provides supervision with individual current radiation exposure status and/or exposure authorization. These are factored into job assignments and assist in maintaining exposures to as low as reasonably achievable (ALARA).
Occupational radiation exposure monitoring is performed as described in Sections 11.5.2 and
11.5.4.9. Radiation levels in all accessible areas are maintained as low as reasonably
achievable (ALARA).
A comprehensive radiation protection program has been developed to monitor the radiation exposure received by persons working in, or making visits to the BVPS-1. This program meets all requirements established by the Code of Federal Regulations, the Commonwealth of Pennsylvania, the Department of Health and the Occupational Safety and Health Act of 1970.
An extensive environmental survey program was conducted by the NUS Corporation, Rockville, Maryland, prior to commercial operation. After commercial operation of the BVPS-1 was initiated, this program was assumed by the licensee, utilizing the services of other technical consultants.
A radiation protection program was established to survey various station areas to determine the amount and type of radiation and radioactive contamination that exists during all plant conditions. This information is used to establish working areas and type of clothing and equipment required as well as to contain radioactive materials.
Structures and systems are arranged and designed to minimize external exposures to plant personnel. Permanent and temporary shielding, individual cubicles for redundant components, physical separation of radioactive sources, adequate outdoor air supply ventilation and individual exhaust ventilation ducts for cubicles are some of the methods used to reduce the potential exposure of operating personnel.
Access to radiologically controlled areas is regulated by Administrative and radiation protection procedures which permit only authorized personnel to enter. These procedures include a Radiological Work Permit System. All work on systems or components where exposure to radiological or radioactive contamination is involved requires a Radiological Work Permit. The
radiological hazards associated with the job are determined and evaluated. Radiological controls are listed on the permit as well as any other pertinent radiological data. Entry into a High Radiation Area or Very High Radiation Area is controlled in accordance with Technical Specification 5.7 and radiation protection procedures.
In the auxiliary building and service building, ventilation supply is directed to areas with the
lowest potential level of contamination. Ventilation exhaust is provided at individual areas and cubicles where a higher potential for leaks or contamination exists. In this way, air flow is from areas of lower activity levels to areas of higher activity. Any leakage is exhausted from the immediate area of the leak. Flex connections are provided on ventilation ducts near filter banks and components. When these systems are opened for maintenance, hoses may be connected to the ventilation flex connections so that air may be exhausted from the areas that are opened.
BVPS UFSAR UNIT 1 Rev. 26 11.5-10 4. Reduction of Sources by Discharging, Flushing, Etc.
When significant reductions in radiation levels can be achieved by flushing systems, discharging, etc., these methods shall be used where practicable.
- 5. Radiological Work Permit and Surveys Radiation surveys will be conducted prior to the start of maintenance jobs in radiation areas. The necessary radiological information will be identified on the
Radiological Work Permit. Location of hot spots in the work area should be
identified and marked. The permit will also specify all radiological exposure control methods which must be used during the performance of the specific assignment.
- 6. Work Practices Work practices will be specified in radiation protection procedures and followed by all personnel working in radiologically controlled areas.
- 7. Radiological Training
All personnel who perform work in radiologically controlled areas will receive training in radiological control practices commensurate with their assigned task.
Competency in this area will be verified for individuals granted unescorted access.
Special training may be required prior to operations involving complex radiological control problems or procedures. This training will be conducted on an as-needed
basis.
- 8. Job Debriefing
Debriefing of involved personnel will be conducted following jobs involving new or complex problems, and a critique prepared to improve future methods of
performing the job. Feedback to improve procedures will also be obtained through job supervisor and periodic general safety meetings. 11.5.4.2 Personnel Monitoring Systems Personnel monitoring systems, as described in Unit 2 UFSAR Section 12.5.3.3, are used at Unit 1.
BVPS UFSAR UNIT 1 Rev. 26 11.5-11 11.5.4.3 Personnel Protection Equipment 11.5.4.3.1 Protective Clothing Clean Anti-contamination (Anti-C) clothing consisting of such items as underclothing, coveralls, shoe covers, cloth and rubber gloves, and hoods will be available at the access point to
radiologically controlled areas. It will be worn as required by posted instructions in the work area and/or by the Radiological Work Permit which specifies radiological conditions and controls
for maintenance and testing involving potential radioactive contamination. In general, unless this clothing is excessively contaminated, it will be laundered, monitored, and reused. The use of Anti-C clothing is restricted to radiologically controlled areas, unless other use is approved by radiation protection supervision. It is mandatory that all persons remove all Anti-C clothing prior to exiting radiologically controlled areas of the plant.
Additional clothing such as plastic suits (wet suits), respiratory equipment, plastic air hoods, face shields, goggles, etc., may be provided as warranted by the work to be performed. 11.5.4.3.2 Respiratory Equipment Whenever the potential for high airborne particulate activity exists, full-face high-efficiency filter masks, supplied air masks, self-contained breathing apparatus, or evacuation of the area (if no suitable protective devices are immediately available) may be exercised. Use of respiratory protection is based on TEDE ALARA considerations.
All respiratory protective devices used for radiological purposes at the site are the full-face
design sealed about the face and neck, or the completely enclosed hood type. Most types may be supplied with positive pressure of breathing quality air.
Personnel will be trained in the proper use of respiratory equipment. They will be cautioned as to the limitations of the respirators and instructed in methods to ensure a proper fit. Special pairs of spectacles designed specifically for use with the particular respiratory equipment shall be provided as required. The respirators will be handled and inspected in accordance with the requirements of Department of Labor, Occupational Safety and Health Administration rule set forth in 29 CFR 1910.134 Chapter XVII.
11.5.4.4 Change Room Area A change room has been provided so that personnel may obtain the clean protective clothing when required prior to entry into radiologically controlled areas of the station. Facilities are also provided for personnel decontamination. These areas are routinely surveyed for contamination.
BVPS UFSAR UNIT 1 Rev. 26 11.5-12 11.5.4.5 Decontamination Facility A decontamination facility is provided at the station for decontamination of equipment and tools. No equipment or tools are shipped from the site that have not been surveyed and decontaminated to the Department of Transportation Standards as a minimum. 11.5.4.6 Access Control In order to protect personnel from accidental ingress to high radiation areas, warning signs, audible and visual indicators, barricades, and locked doors are used as required. Administrative procedures are established to control access to radiation, high radiation, and very high radiation areas. 11.5.4.7 Laboratory Facilities BVPS-1 includes a laboratory with adequate equipment for detecting, analyzing, and measuring the types of radiation of concern, and for evaluating radiological problems which may be anticipated. Counting equipment including Geiger-Muiller, scintillation, and scalers are provided in an appropriately designed counting room for detecting and measuring radiation as well as equipment to identify the specific energy level(s) that are present in a particular sample.
Equipment and facilities to prepare and analyze certain bioassay samples are provided.
11.5.4.8 Instrumentation Portable radiation survey instruments are provided for use by radiation protection, operating, and maintenance personnel. A sufficient number are available to allow for use, calibration, maintenance, and repair. The types of instruments used include those for detecting and measuring alpha, beta, gamma, and neutron radiation. Personnel and tool monitoring instruments are located at exits from the Radiologically Controlled Area. These instruments assist operating personnel in detecti ng and preventing the spread of contamination.
Permanently installed area radiation monitoring equipment is included in the facility. These
detectors continuously monitor radiation levels within certain areas as discussed in Section 11.3.4. These monitors will have an indicator readout in the main control room and present an audible alarm both in the area of concern and the main control room. 11.5.4.9 Bioassay Program The bioassay program, as described in Unit 2 UFSAR Section 12.5.3.5.1.2, is applicable at
Unit 1.
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