ML16257A089
| ML16257A089 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/25/2016 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16256A115 | List:
|
| References | |
| W3F1-2016-0053 | |
| Download: ML16257A089 (18) | |
Text
WSES-FSAR-UNIT-3 12.5-1 Revision 307 (07/13) 12.5 HEALTH PHYSICS PROGRAM 12.5.1 ORGANIZATION
12.5.1.1 Program and Staff Organization (DRN 02-110, R12)
The health physics program specifies guidelines for hand ling all radioactive materials at Waterford 3, including those being received and those in preparation fo r shipment offsite. Guidelines cover special nuclear, source, and byproduct materials. The progr am assures that the st ation operation meets the radiation protection and training requirements of 10CFR19, 10CFR20, 10CFR50 Appendix I, and NRC
Regulatory Guides 8.2, February 1973; 8.3, Febr uary 1973; 8.4, February 1973; 8.7, June 1992; 8.8, March 1977; 8.9, September 1973; 8.10, September 1975; 8.15, Oc tober 1976; 1.16, August 1975, and 1.39, September 1977. The program assures that radiation protection training is provided to workers, that personnel and inplant radiation monitoring is performed, and records of training, exposure, and surveys are maintained. It also assures a commitm ent to maintain exposur es as low as reasonably achievable (ALARA) is fulfilled. (DRN 02-110, R12) (DRN 03-1135, R13; LBDCR 13-005, R307)
The Waterford 3 organization, including the health physics organization, is discussed in Section 13.1. The General Manager-Plant Operations is responsible for the overall performance of the health physics
program. He delegates the administration of the program to the Radiation Protection Manager. The Radiation Protection Manager is equivalent to t he radiation protection manager referred to in NRC regulatory guides. He is responsible for administering the station radiation protection program, with
support from the Chemistry Superint endent who is responsible for certain aspects of the health physics program including radioactive effluent releases, radiological environmental monitoring, and some
radioactivity measurements in support of plant health physics activities. (LBDCR 13-005, R307)
Reporting to the Radiation Protection Manager are personnel functionally responsible for the areas of
personnel dosimetry, ALARA, HP job coverage, in strument and respiratory protection program and radiological engineering. (DRN 03-1135, R13)
Reporting to the Chemistry Superintendent are supervisory personnel functionally responsible for the areas of primary chemistry, secondary/auxiliary chemistry, e ffluent releases and environmental monitoring. Also reporting to the Chemistry Superin tendent are technical personnel providing expertise in the areas of radiochemis try/chemical engineering.
Personnel assigned to the health physics organization, as designated by adminis trative procedures, will perform various radiation protection activities. They observe work in progress and ensure that radiation safety guidelines are followed.
12.5.1.2 Program Objectives
The objectives of the health physics program are:
a) to provide radiation protection cont rols for personnel and operations onsite, b) to ensure that personnel expos ures to radiation and radioactive materials are within the guidelines of 10CFR20 and that such exposure is kept ALARA,
c) to ensure that all radioactive effluent releas es and waste shipments meet guidelines established in plant procedures, and
d) to ensure that radioactive e ffluent releases are within Offsite Dose Calculation and Technical Requirements Manual requirements and kept ALARA.
WSES-FSAR-UNIT-3 12.5-2 Revision 305 (11/11) 12.5.1.3 Health Physics Program The station health physics program was implemented when radioactive material under the Waterford 3
license was initially brought onsite, and will be mainta ined throughout the life of the plant. The program includes management and worker philosophies, practice s, guidelines, and procedures to ensure that the program objectives stated above are fulfilled in a reasonable manner.
The health physics program ensures that:
a) all radiation workers receive radiation protec tion training commensurate with their respective responsibilities, (DRN 99-2362, R11) b) respiratory protection equipment training is provided to radiation workers who may use the equipment, (DRN 99-2362, R11) c) emergency plan training is provided as nec essary for personnel who may be assigned to radiation emergency teams, d) appropriate personnel dosimetry is available,
e) internal and external dose assessment is provided for monitored workers,
f) personnel contamination monitoring equipment is used to assess personnel contamination's, g) respiratory protection equipment is provided if necessary to keep internal exposure ALARA, (DRN 99-2362, R11; EC-27665, R305) h) Radiologically Controlled Areas (RCA) are segr egated to control potential radiological exposures, (EC-27665, R305) i) access to radiologically controlled areas is proceduralized to control potential radiological exposures, j) radiological instrumentation is provided and maintained to assess potential exposure, (DRN 99-2362, R11) k) incoming shipments of radioactive material are received and surveyed properly, l) outgoing shipments of radioactive material are packaged, surveyed, and labeled properly, and
m) necessary measures are taken and guidelines followed to keep exposures and effluents ALARA while safely supplying a reliable source of power to the public.
WSES-FSAR-UNIT-3 12.5-3 Revision 305 (11/11) 12.5.2 EQUIPMENT, INST RUMENTATION, AND FACILITIES 12.5.2.1 Health Physics Facilities (EC-27665, R305)
Access control to the Radiologically Controlled Area (RCA) may be through the Westside Facility or the
-4 elevation of the Reactor Auxiliary Building. The preferred entry point is t he Westside Access. Other control points are established as necessary. Acce ss control points contain necessary equipment (i.e., access and egress terminals, personnel and tool contami nation monitors, etc.) to prevent the spread of contamination. (EC-27665, R305)
Space is reserved for personnel at the -4 elevation control point for health physics/chemistry personnel.
It provides for equipment, records and supply storage.
Space for instrumentation issue and storage may be provided near the Westside Access or the -4 Control Point.
The counting room located in the -4 elevation RAB c ontrol point area provides facilities for analysis of samples. Portable sample counting instrumentation will be utilized at other control points as necessary.
Limited personnel decontaminations may be performed in the Westside Access. The -4 control point decon facility will be used on a case basis, for exam ple in the event personnel showering is needed.
Contaminated equipment will normally be decontaminated in the decontam ination facility located on the
+21.00 ft. west wing area. Other equipment decon lo cations may be approved by health physics. The decontamination facility is de scribed in Subsection 12.1.2.
(EC-27665, R305)
Personnel contamination monitors, tool and personnel contamination friskers are located at the -4 and Westside access control points. All personnel exiting the RCA will be monitored. Respiratory protection equipment is available and will be maintained, inspec ted, and used in accordance with Regulatory Guide 8.15, October 1976. Portal monitors are also located at the Primary Access Point in the administration building. (EC-27665, R305)
(DRN 99-2362, R11)
Other control points inside the plant may be establis hed as applicable to ensure positive radiation control and provide protective equipment and supplies. (DRN 99-2362, R11)
(DRN 99-1051, R11; 03-1429, R13)
Storage space in the Radioactive Material Storage Bu ilding (RMSB) is provided to allow the storage of reusable radioactive material such as tool s, previously contaminated PC's, etc. (DRN 99-1051, R11)
(DRN 99-1697, R11-A)
The Radioactive Material Storage Building (RMSB) is a pre-engineered, prefabricated sheet metal building. The entire building is constructed on a reinfo rced concrete slab with curbing such that water is kept from entering the building. The RMSB fac ility will be used for storage of radiation protection consumables and for storage and main tenance of refueling tools. (DRN 99-1697, R11-A; 03-1429, R13) 12.5.2.2 Health Physics Instrumentation 12.5.2.2.1 Laboratory Instrumentation Laboratory instrumentation allows plant personnel to asce rtain the radioactive material present in survey samples. Typical samples would be contaminated su rvey smears, airborne surv ey filter, and charcoal cartridges; tritium surveys and other samples may be processed using radioc hemistry counting room WSES-FSAR-UNIT-3 12.5-4 Revision 305 (11/11) equipment. The health physics counting instrumentation is listed in Table 12.5-1. Instrumentation with equivalent or better sensitivity may be used in lieu of those listed. The criteria for selection of these various counters was to obtain instrumentation t hat could reliably and quickly count samples; could provide the necessary low backgrounds and sensitivit ies and that could, to some extent, analyze the counting data to provide information in a more easily used form. Each laboratory counting system is checked and calibrated at regular intervals with standard radioactive sources traceable to a National Institute of Standards & Technology (NIST) source. Counting efficiency, background count rates, and high voltage settings are checked by plant per sonnel in accordance with plant procedures.
12.5.2.2.2 Portable Su rvey Instrumentation (DRN 99-2362, R11)
Portable survey instruments are lo cated near the access control points and other control points inside the plant. This equipment will allow plant personnel to perform alpha, beta, gamma, and neutron surveys for radiation, airborne, and surface contamination control. (DRN 99-2362, R11)
The criteria for selection of thes e instruments was to obtain accurate and reliable instrumentation that could be easily serviced and that would cover the entire spectrum of radiation measurements expected to be made at the station during normal operat ion, shutdown, and accident conditions.
(EC-27665, R305)
Each portable survey instrument w ill be calibrated, when in use. Dose rate meters will be calibrated using a multi source gamma calibrator as described in section 12.5.2.2.4 or in accordance with the instrument manufacture's approved calibration method.
Instruments will be source checked to verify proper operation in accordance with plant procedures.
Sufficient quantities of each type of instrument will be available to permit calibration, maintenance, and repair without causing a shortage in operational instrumentation. Portable radiologi cal survey instrumentation is list ed in Table 12.5-2. Instrumentation with equivalent or better sensitivity may be used in lieu of those listed. (EC-27665, R305) 12.5.2.2.3 Personnel Monitoring Instruments (DRN 06-625, R15; EC-14865, R303, EC -27665, R305)
Personnel monitoring will be provided by use of dosimet ers of legal record (DLRs), direct-reading pocket dosimeters and survey instrumentation. The criteria for selection of the DLR for a dose measuring device was to have a device accepted as a legal re cord and that could be evaluated within a reasonable time by dosimetry personnel. The criteria for sele ction of (direct reading dosimeters) was to have a device that could be read immediately by exposed personnel. All personnel, with the exception of visitors that do not enter a high radiation, contaminated or airborne radioactivity area, entering the Radiologically Control Area (RCA) will be issued DLR badges which will be used to measure exposure to beta-gamma and Neutron radiation, or to measure only beta-gamma radiation when neutron radiat ion is not expected.
These badges contain suitable filters to allow deter mination of penetrating vs. non-penetrating radiation. DLRs under normal conditions, will be processed periodically based on the fade test results. This will
provide the official record of personnel ex posure to beta, neutron and gamma radiation. (DRN 06-625, R15, EC-27665, R305)
Direct reading dosimeters will be worn by personnel in the Radiologically Control Area (RCA). These dosimeters will provide a day-to-day estimate of personnel exposure. (EC-14865, R303, EC-27665, R305)
(DRN 06-625, R15, EC-27665, R305)
Direct-reading dosimeters will be tested for proper re sponse. DLR chips will be checked for matched response periodically. Quality control of DLR performance is proceduralized. (DRN 06-625, R15)
Personnel survey instrumentation will consist of Personnel Contamination Monitors (PCM), G-M countrate meters (contamination friskers), porta l monitors, and whole body counting capability. The criteria for selection of external contamination measuring equipment was to have devices available at checkpoints and other areas that could be used to det ermine the location of cont amination (friskers), and to have devices that require minimum action by per sonnel being checked (PCM's). The criteria for selection of the whole body counti ng system was to have a system r eadily available to quickly supply information concerning internal contamination levels.
WSES-FSAR-UNIT-3 12.5-5 Revision 305 (11/11)
These instruments will be calibrated and source check ed at a frequency specified by plant procedures.
Personnel monitoring instrumentation is listed in Table 12.5-3. Instrumentation with equivalent or better sensitivity may be used in lieu of those listed.
12.5.2.2.4 Health Physics Equipment (EC-27665, R305)
Portable air samplers are used to survey airborne radioactive material concentrations. Mass flow calibrations for air samples are performed when in use. Surveys may be performed for radioactive particulate and radioiodine airborne concentrations.
Portable continuous air monitors may be used to monitor airborne concentrations at s pecific work locations. Local i ndication will be provided as well as trend information. Alarm setpoints are vari able and visual, and audible alarms are provided.
(DRN 99-2362, R11)
Respiratory protection equipment must be avail able and can be easily accessed. Self-contained breathing apparatus are available at the emergenc y equipment storage lockers. Equipment will be maintained in accordance with Regulatory Guide 8.15, October 1976.
(DRN 99-2362, R11; EC-27665, R305)
An instrument calibrator will be used for calibrating gamma dose rate instrumentation. This will be a self-contained, heavily shielded, multiple source calibra tor or an open air calibration source. Beta and alpha radiation sources will also be available for instrum ent calibration. Sources are traceable to a NIST source. Neutron sources will be available for proper response checks with actual calibration of neutron instrumentation performed by an outside vendor.
Protective clothing will be supplied for personnel working in contamination areas. The clothing required
for a particular instance will be prescribed by health physics personnel on a radiation work permit (see Subsection 12-5.3.4), based on actual or potential radiological conditions.
An adequate inventory of protective clothing will be maintained on hand as necessary to support plant operations and maintenance activities.
Additional contamination control consumables will be available to assist in identifying, deconning and barricading contamination areas.
A listing of health physics equipment is shown in Table 12.5-1
12.5.2.2.5 Other Health Physics Instrumentation
The Area Radiation Monitoring System will be installed in areas where it is des irable to have constant dose rate information. Monitors will indicate dose ra te locally and/or in the main control room. Fixed continuous airborne radioactivity monitors are also provided at strategic locations where personnel exposure to airborne radionuclides is likely. More information on thes e fixed instruments is given in Subsection 12.3.4.
WSES-FSAR-UNIT-3 12.5-6 Revision 309 (06/16) 12.5.3 PROCEDURES (DRN 99-2362, R11)
Procedures will be developed to cover all necessary ar eas of plant operations and maintenance activities and to control potential exposures.
ALARA considerations will be em bodied in applicable procedures, as Section 12.1 herein describes. In addition, certai n methods that will be proceduralized to maintain radiological control over plant operations and maintenance activities are discussed below. (DRN 99-2362, R11)
The Waterford 3 commitment to regulatory guides w ill be incorporated into pr ocedures as appropriate.
12.5.3.1 Radiation Surveys
Health physics and health physics qualified personnel norma lly perform radiation surveys, the techniques are delineated in plant health physics procedures. Su rveys are performed on frequencies that vary with the potential radiological hazards associated with a given area. Frequencies are also delineated in plant health physics procedures.
(LBDCR 16-016, R309)
Surveys are normally performed to ascertain radiati on/contamination levels and for airborne radionuclide concentration determination. Records of all surveys are maintained. Cu rrent survey information for some areas within the Radiologically Controlled area are norma lly posted. Survey information is factored into exposure stay time determination and radiation work permit specific ations (see Subsection 12.5.3.4). (LBDCR 16-016, R309)
Radiation surveys may be performed for gamma, beta, and neutron exposure.
Contamination surveys are normally performed to establish gross beta-gamma contamination level, but may be processed for specific types of radiation (beta-alpha-gamma) or specific radionuclides (via gamma spectroscopy). Air samples are normally taken to establish airborne c oncentrations of particulates and/or radioiodine, but specific nuclide information may also be obtained. Ava ilability of current survey information will aid in keeping exposures ALARA.
12.5.3.2 Additional Methods To Maintain Exposures ALARA The Waterford 3 ALARA policy is delineated in Section 12.1. ALARA considerations are incorporated into various plant and health physics procedures. In addi tion, various methods are used to maintain exposures ALARA.
12.5.3.2.1 Refueling
Some examples of methods of maintaini ng exposures ALARA during refueling are:
a) Refueling cavity water is filter ed to remove radioactive material.
b) Refueling cavity water is maintained 140 F, and surface ventilation is provided to minimize airborne radioactive material.
c) Prior to removing the vessel head, the primary system is degassed and sampled to minimize expected airborne levels when the head is removed.
WSES-FSAR-UNIT-3 12.5-7 Revision 305 (11/11) d) Movement of irradiated fuel assemb lies will be accomplished with the assembly maintained under water.
(EC-27665, R305) e) Work performed in the RCA is staged, i.e., wo rkers are briefed on assignments and familiarized with procedures and equipment needed to complete assignments. (EC-27665, R305) f) Current survey information is used.
g) Ventilation is provided to minimi ze airborne radioactive material.
h) The radiation work permit system is us ed to maintain positive radiological control over work in progress.
12.5.3.2.2 In-service Inspection
Some examples of methods of maintaining exposures ALARA during in-service inspections are:
a) Equipment is calibrated and checked pr ior to entry into the radiation area.
b) Portable shielding is used where practicable.
(EC-27665, R305) c) Work performed in the RCA is staged, i.e., workers are briefed on assignments and familiarized with procedures and equipment needed to complete assignments. (EC-27665, R305) d) Current survey information is used.
e) Ventilation is provided to minimi ze airborne radioactive material.
f) The radiation work permit system is used to ma intain positive radiological control over work in progress.
12.5.3.2.3 Radwaste Handling
Some examples of methods of maintaining exposures ALARA during radwaste handling are:
a) The volume of radwaste generation has been minimized by station design.
b) Radwaste systems are heavily shielded and re motely located so that operator and other personnel exposure is minimized.
c) The spent resin collection and transfer sy stem has been redesigned and modified to further reduce personnel exposure during normal operations.
d) Filter changeout will utilize a re motely operated extraction device.
e) Portable shielding is available for use when necessary.
WSES-FSAR-UNIT-3 12.5-8 Revision 306 (05/12) f) Ventilation is provided, where appropriate, to minimize airborne radioactive material during waste handling operations.
g) Extension reach rods will be us ed, where appropriate for hard to reach valves in high radiation areas.
h) Administrative controls will be instituted in radioactive material storage areas to maximize the use of self shielding effects for packaged low-level waste containers such that personnel exposures will be minimized.
i) Current radiological survey information will be used. (EC-14275, R306) 12.5.3.2.4 Spent Fuel H andling, Loading, and Unloading (EC-14275, R306)
Some examples of methods of maintaining ex posures ALARA during spent fuel handling are:
a) The spent fuel pool water is filt ered to remove radioactive material.
b) The spent fuel pool water is cooled and surface air ventilation is provided to minimize airborne radioactive material. (EC-14275, R306) c) Loading of the canister in the transfer cask is performed under water.
d) Fuel handling cranes and extension tools are us ed to handle transfer casks, fuel assemblies, and inserts. (EC-14275, R306) e) Movement of irradiated fuel assemblies not contained in a transfer cask will be accomplished with the assembly maintained under water.
(EC-27665, R305) f) Work performed in the RCA is staged, i.e., wo rkers are briefed on assignments and familiar with procedures and equipment needed to complete assignments. (EC-27665, R305) g) Current survey information is used.
h) The radiation work permit system is used to maintain positive radiological control over work in progress.
i) Ventilation is provided to minimi ze airborne radioactive material. (EC-14275, R306) j) After the transfer cask is loaded, it is decontam inated using a pressurized water washing device.
k) Use of temporary shielding. (EC-14275, R306) 12.5.3.2.5 Normal Operation
Some examples of methods of maintaining exposures ALARA during normal operation are:
a) The station is designed so that significant radiation sources are minimized and shielded.
WSES-FSAR-UNIT-3 12.5-9 Revision 305 (11/11) b) An area radiation monitoring system is available and provides indication of radiation levels and, as applicable, local and/or remote alarms. (EC-27665, R305) c) Work performed in the RCA is staged, i.e., wo rkers are briefed on assignments and familiar with procedures and equipment needed to complete assignments. (EC-27665, R305) d) Current survey information is used.
e) Ventilation is provided to minimi ze airborne radioactive material.
f) The radiation work permit system is used to ma intain positive radiological control over work in progress.
g) During initial start-up, neutron and gamma dose ra te surveys are performed to verify shielding adequacy.
h) Areas are conspicuously post ed in accordance with 10CFR20. (DRN 99-2362, R11) i) Standby low radiation areas are designated fo r ALARA purpose to minimize the radiation worker's exposure. (DRN 99-2362, R11) 12.5.3.2.6 Maintenance
Some examples of methods of maintaini ng exposures ALARA during maintenance are:
a) Equipment is moved to areas with lo wer radiation and contamination levels for maintenance when practicable.
b) Extension tools are used when practical.
c) Portable shielding is used as practical.
(EC-27665, R305) d) Work performed in the RCA is staged, i.e., wo rkers are briefed on assignments and familiar with procedures and equipment needed to complete assignments. (EC-27665, R305) e) Current survey information is used.
f) The radiation work permit system is us ed to maintain positive radiological control over work in progress.
g) Routine maintenance is procedur alized and precautions specified.
h) Required tools are specifically lis ted in procedures where practical.
12.5.3.2.7 Sampling
Some examples of methods of maintain ing exposures ALARA during sampling are:
a) Sampling hoods are provided in the radiochemis try laboratory. Ventilation minimizes airborne radioactive material. The sampling hoods are lo cated to reduce the exposure from sampling of radioactive liquids and gases.
WSES-FSAR-UNIT-3 12.5-10 Revision 305 (11/11) b) Procedures specify proper sampling methods.
c) Radiation levels of samples are checked.
d) Extension tools are used when practicable.
e) The Radiation Work Permit System is used to maintain positive radiological control over work in progress.
12.5.3.2.8 Calibration
Some examples of methods of maintaini ng exposures ALARA during calibration are:
a) The instrument calibrator is heavily shielded.
b) An interlock is provided so that the calibrator door cannot be opened while sources are exposed.
c) Portable sources of a significant hazard used to calibrate fixed instruments are transported and maintained in shielded containers.
d) The radiation work permit system is used, w here applicable, to maintain positive radiological control over calibration.
12.5.3.3 Access Control (EC-27665, R305)
Access to the RCA may be through the Westside Acce ss or the -4 RAB control point. These control points provide positive access control ov er personnel entering controlled areas. (EC-27665, R305)
High radiation areas (as defined in Technical Specificat ions) also have access control features. Controls will be established (barricades, flashi ng lights, signs, etc.). Key control for such areas is delineated in administrative procedures. Access control to high r adiation areas is provided through administrative and physical control features as delineated through plant procedures. These procedures adequately address the section of Technical Specificat ions concerning high radiation areas.
Key control for such areas is delineated in administrative procedures.
12.5.3.4 Radiation Work Permit
All work in radiation, high radiation and other radiological areas (as determined by health physics) requires a Radiation Work Permit. The Radiation Work Permit establishes the minimum radiological requirements for tasks to be performed safely and efficient ly. Violations of the Radiaiton Work Permit's instructions should be documented in accordanc e with station administrative procedures.
WSES-FSAR-UNIT-3 12.5-11 Revision 305 (11/11) 12.5.3.5 Contamination Control Contamination limits for personnel, equipment, and areas are delineated in plant procedures. Surveys for contamination control are performed on a routine basis at various locations in the plant. Non-routine surveys are performed in areas whenever a change in c ontamination levels is likely and may be important for radiation protection. Areas found contaminated are posted, isolated (with ropes, barriers, etc.) and decontaminated as practical. Since the complete re moval of surface contamination from some plant areas is not practical, these areas may be designated as contaminated areas. The level of contamination and number of such areas is minimized. Entrance to such an area normally requires authorization of, and adherence to the specifications of a radiation work permit.
(EC-27665, R305)
Tools and equipment used in contaminated areas are surveyed for removable contamination and contaminated tools are bagged for transportation. If tools or equipment do not meet the clean area limits, they are decontaminated before leav ing the RCA or released for rest ricted use only. Some tools and equipment are for use only in a controlled area.
These items are surveyed and decontaminated as appropriate. (EC-27665, R305)
Personnel are protected from contamination by t he protective clothing and equipment specified in radiation work permits. Personnel survey themselv es for contamination upon exiting a contamination area (if practical). In addition, when personnel pa ss through the access control point (see Subsection 12.5.2), they pass through a Personnel Contamination Monitor. Contaminated personnel are
decontaminated at the dec ontamination facility.
12.5.3.6 Radiation Protection Training
Plant personnel, both permanent and temporary, whose dut ies require such training, will be instructed in the fundamentals of radiation protec tion. Radiation protection training will be given annually as part of general employee retraining. Training is commens urate with the degree of hazard associated with personnel work assignments. Personnel must be acceptably cognizant of fundamentals presented in
training to enter the radiologica lly controlled areas unescorted.
Training topics will include: instructions in applicabl e station and NRC exposure lim its, station procedures, instructions to women concerning prenatal exposure, properties of radiation and radioactivity, biological effects of exposure, techniques of radiation prot ection, ALARA, emergency and fire alarm response, and other topics as pertinent. More detail on the Waterford 3 training program is given in Section 13.2.
Additional training is given to plant personnel w hose duties involve greater degrees of radiological hazard, such as health physics personnel and operators.
12.5.3.7 Personnel Monitoring 12.5.3.7.1 External Radiation Exposure (DRN 06-625, R15, EC-27665, R305)
All personnel with the exception of visitors that do not enter a high radiation, contaminated or airborne radioactivity area, who enter the RCA will wear a DLR badge and a direct-reading dosimeter. (DRN 06-625, R15, (EC-27665, R305)
WSES-FSAR-UNIT-3 12.5-12 Revision 305 (11/11)
(DRN 06-625, R15)
Any individual or group of individuals who enter high radiation areas shall wear DLR badges and a direct-reading dosimeter and shall be provided with or accompanied by one or more of the following: (DRN 06-625, R15) a) A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b) A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate leve l in the area has been established and personnel have been made knowledgeable of them.
c) A health physics qualified individual (i.e., qualif ied in radiation protection procedures) with a radiation dose rate monitoring device who is res ponsible for providing positive control over the activities within the area and shall perform periodic radiation surveys.
(DRN 06-625, R15, EC-27665, R305)
DLR badges are processed periodically. A permanent exposure record is kept for all badged personnel, in accordance with Regulatory Guide 8.7, J une, 1992, and 10CFR20.2106. Di rect-reading dosimeters provide a daily estimate of personnel exposure. (DRN 06-625, R15; EC-27665, R305)
(EC-14865, R303)
If a high dosimeter reading indicates potential unexpec ted exposure or overexpos ure, the individual's DLR badge may be processed to verify exposure. (EC-14865, R303) 12.5.3.7.2 Internal Exposure
(DRN 03-1135, R13)
A bioassay program will be performed in accordance with Regulatory Guide 8.9, and the portions of ANSI N343-1978 directly applicable to nuclear power plants.
The Health Physics procedures are the vehicle by which the bioassay program is implemented. A ll personnel who may regularly enter an airborne radioactivity area and any other area where unencapsulated radioactive mate rial is present in a form and quantity such that the area has a significant potentia l for becoming an airborne radioactivity area will be included in the bioassay program. The need for bioassays for some individuals will be based on the
Radiation Protection Manager's judgement as to the probability and potential magnitude of internal exposure. An excreta bioassay will be performed as deemed appropriate by the Radiation Protection Manager. Internal exposure assessments and results will be recorded in accordance with Regulatory
Guide 8.7, June, 1992. (DRN 03-1135, R13) 12.5.3.8 Airborne Radionuclide Control, Assessment, and Personnel
The plant ventilation systems (refe r to Subsection 6.5.1 and Section 9.4) provides the means for removing airborne radioactive material from t he in-plant atmosphere. Airborne radionuclide concentrations are controlled by minimizing loose surface contamination levels and providing
containment of sources.
WSES-FSAR-UNIT-3 12.5-13 Revision 305 (11/11)
Concentrations of airborne radionuclides are routinely assessed by fixed and portable continuous air monitors and air sample surveys. Air sample surveys are taken routinely at specified frequencies and nonroutinely when the potential for personnel expos ure exists (as determined by health physics personnel).
Radiation work permits may specify air sampling prior to the start of work in a given area. Continuous air monitors alarm when airborne radio-nuclide concentra tions exceed preset values in a given area.
Internal exposures are minimized by this assessment and follow up control.
There may exist areas in which airborne radionuclide concentrations cannot be maintained below
applicable station limits (normally, t hese are the Derived Air Concentra tion limits, as found in 10CFR20, Appendix B). Controls are established in plant procedures to maintain exposures ALARA if personnel entry into those areas is required.
(EC-27665, R305)
Respiratory protection equipment is available and can be easily accessed. Equipment will be maintained, inspected and used in accordance with Regulatory Guide 8.15, October 1976. (EC-27665, R305)
To assure an adequate program for respiratory protection, the following controls are incorporated into the program:
a) Each respirator user is advised that he may leave an airborne radioactivity area for psychological or physical relief from respirator use. Each user must leave the area in the case of respirator
malfunction or any other condition that might caus e reduction in the protection afforded the user.
b) Sufficient air samples and surveys are made to identify the various radionuclides present and to estimate the individual exposures so that sele ction of appropriate respiratory equipment can be made in accordance with 10CFR20.1703.
c) Procedures are established to assure correct fitting, use, maintenance, and cleaning of the various types of respiratory equipment.
d) Bioassays, will be performed in accordance with plant procedures and, as required, to evaluate individual internal intake of radionuclides and to assess the overall effectiveness of the respiratory protection program.
12.5.3.9 Radioactive Material Safety Program
Radioactive material may be used by station pers onnel for calibration and other purposes. This will include both sealed sources and unsealed materials (gaseous, liquid, or solid). Calibration of radiochemistry counting, fixed monitoring, and portabl e survey instrumentation is the most common use of such material. Exempt quantities or exempt c oncentrations of radioactive material do not require special handling for radiation protection purposes.
WSES-FSAR-UNIT-312.5-14Revision 11 (05/01)Recognized methods for the safe handling of radioactive materials, such as those recommended by theNational Council of Radiation Protection and Measurement, will be proceduralized to ensure proper usage.
Procedures specify handling techniques, storage, and other safety considerations, as listed below:a)proper labeling of all radioactive material (per 10CFR20),
b)inventorying of licensed sealed radioactive sources in accordance with plant procedures, c)leak testing of sealed sources at six month intervals in accordance with license conditions, and d)monitoring of all packages received containing radioactive material in accordance with 10CFR20.1906.
WSES-FSAR-UNIT-3 TABLE 12.5-1 Revision 305 (11/11)
COUNTING INSTRUMENTATION Instrument
Sensitivity
Range Quantity
Remarks (DRN 99-1034, R11, EC-27665, R305)
Alpha Counter : 0.4 pCi 0-10 7cpm 1 For contamination levels on survey samples. (EC-27665, R305)
GM Counter 200 pCi 0-10 5cpm 2 May be portable and used at inplant control points.
Liquid Scintil-
lation Counter ~1x10-6 Ci/ml 0-10 7cpm 1 For low energy counting.
Maintenance by Chemistry
Department and kept in
chemistry counting area. (EC-27665, R305)
(EC-27665, R305)
Ge (Li) Detector Particulate ~1x10-11 Ci/ml liquid ~1x10-7 Ci/ml N/A 1 With associated electronics and spectrum-stripping computer for isotopic
analysis. (EC-27665, R305)
(EC-27665, R305)
(EC-27665, R305)
Note: Instrument accuracies, ranges, and quantitie s may vary depending upon station and ERO specific needs. Radiological instrumentation that is equiva lent or better may be substituted to meet the specific monitoring function. (DRN 99-1034, R11, EC-27665, R305)
WSES-FSAR-UNIT-3 TABLE 12.5-2 Revision 305 (11/11)
PORTABLE RADIOLOGICAL SURVEY INSTRUMENTATION Instrument
Accuracy
Range Quantity
Remarks (DRN 99-1034, R11)
Alpha Survey
Meter 10% 0-10 5 counts 2 Scintillation (EC-27665, R305)
Neutron Survey
Meter 15% 0-100 Rem/hr 2 Capable of detecting neutron over the range of
.025 eV to 10 MeV. (EC-27665, R305)
GM Survey Meter 10% 0-10 3 Rem/hr 2 E-Plan 3 Normal ops Telescoping probe.
GM Survey Meter 10% 0-200 mRem/hr 2 E-Plan 2 Normal ops Energy Compensated
hand held probe. (EC-27665, R305)
GM Survey Meter 10% 0-10 5 cpm 20 E-Plan 20 Normal ops Pancake probes.
Ion Chamber Survey Meter 10% 0-5000 mRem/hr 4 E-Plan 10 Normal ops Dose rate air filled
chamber capable of detecting both and radiation. Ion Chamber Survey Meter 10% 0-50,000 mRem/hr 6 E-Plan 10 Normal ops Dose rate air filled
chamber capable of detecting both and radiation. (EC-27665, R305)
Ion Chamber Survey Meter
20% 0-10 4 Rem/hr 1 High range, remote probe.
Energy compensated. (DRN 99-1034, R11)
(EC-27665, R305)
Note: Instrument accuracies, ranges, and quantit ies may vary depending upon station and ERO specific needs. Radiological instrumentation that is equiva lent or better may be substituted to meet the specified monitoring function. (EC-27665, R305)
WSES-FSAR-UNIT-3 TABLE 12.5-3 Revision 309 (06/16)
PERSONNEL MONITORING INSTRUMENTATION
Instrument
Sensitivity Range Quantity Remarks (DRN 99-1034, R11) (DRN 99-1034, R11)
Portal Monitors 1.0 ci Cs-137 NA 2 Scintillation type (DRN 99-1034, R11; EC-14865, R303)
Whole Body Counter .2% of most nuclide ALI 0-several nCi ALI 2 NaI Detector system (EC-14865, R303)
(EC-27665, R305; LBDCR 16-016, R309)
Direct Reading Dosimeters 50mr 0-1500 mr 40 E-Plan (EC-27665, R305; LBDCR 16-016, R309)
Direct Reading Dosimeters 500 mr 0-10,000 mr 10 Normal ops 27 E-Plan (EC-27665, R305)
Direct Reading Dosimeters 10 mr 0-200 mr 300 E-Plan (EC-27665, R305) Dosimeter
Chargers
--- --- 4 (DRN 99-1034, R11)
(EC-27665, R305)
Note: Instrument accuracies, ranges, and quantitie s may vary depending upon station and ERO specific needs. Radiological instrumentation that is equiva lent or better may be substituted to meet the specified monitoring function. (EC-27665, R305)
WSES-FSAR-UNIT-3 TABLE 12.5-4 Revision 305 (11/11)
HEALTH PHYSICS EQUIPMENT Equipment
Quantity
Range
Remarks (DRN 99-1034, R11; EC-27665, R305)
High Volume
Air Sampler 6 E-Plan 5 Normal ops 1 to 5 ft 3/min Used for rapid assessment of airborne levels. (EC-27665, R305)
Low Volume
Air Sampler 1 E-Plan 15 Normal ops 10 to 100 lpm Used for long duration sampling and trending. (EC-27665, R305)
Air-Purifying
Respirators 67 E-Plan
25 Normal ops N/A Full face, negative pressure. (EC-27665, R305)
Airline Respirators 19 E-Plan N/A Full face constant flow Self-Contained
Breathing Apparatus E-Plan 18 TSC 15 Security OSC (10)
Fire Brigade 5 Locker #1 5 Locker #2 5 Locker #3 6 Normal ops
5 Training N/A
N/A
N/A
N/A Full face pressure demand
Full face pressure demand
Full face pressure demand
Full face pressure demand Portable Continuous
Air Monitors 1 E-Plan 5 Normal ops 0 - 100,000 cpm Monitoring of work areas.
Instrument
Calibrator
1 .002-500 rem/hr Multiple source shielded self-contained calibrator. (DRN 99-1034, R11)
(EC-27665, R305)
Note: Instrument accuracies, ranges, and quantitie s may vary depending upon station and ERO specific needs. Radiological instrumentation that is equiva lent or better may be substituted to meet the specified monitoring function. (EC-27665, R305)