RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection
Text
QUAD CITIES - UFSAR Revision 4, April 1997 12.1-1 12.0 RADIATION PROTECTION The protection of plant personnel from ra diation emanating from process equipment, radioactive materials present on equipment externals in work areas, airborne
radioactive material particles, and gases is accomplished by combinations of measures such as design of shielding structures, selection and use of appropriate radiation monitoring instrumentation, and develop ment and implementation of control standards and procedures. The following subsections provide a brief summary of these radiation protection techniques for Quad Cities Station.
Shielding design is described in Section 12.3. The area radiation monitoring system is also addressed in Section 12.3. Process ra diation monitoring instrumentation is addressed in Section 11.5. The high radiatio n sampling system (HRSS) is described in Section 9.3 and the containment atmosphere monitoring (CAM) system is described in Section 6.2. The radiation sources generate d in the reactor core and transported by the reactor coolant system are addressed in Section 11.1. Radiation sources from components of the radioactive waste manage ment systems are described in Sections 11.2, 11.3, and 11.4. The Heal th Physics Program and its implementation of as low as reasonably achievable (ALARA) radiation ex posure control are addressed in Section 12.5.
12.1 Ensuring That Occupational Exposur es Are As Low As Reasonably Achievable
This subsection addresses the management polic y and organizational structure related to implementation of the policy ensuring that occupational radiation exposures for operating personnel and contractor personnel are maintained ALARA.
12.1.1 Policy Considerations
12.1.1.1 Management Policies
It is the policy of ComEd to maintain occu pational dose equivalents to the individual and the sum of dose equivalents received by all exposed workers to levels that are as low as reasonably achievable (ALARA). Th is ALARA philosophy is implemented in a manner consistent with station operat ing, maintenance, and modification requirements, taking into account the state of technology, the economics of improvements in relation to the state of technology, the economics of improvements in relation to benefits to the public he alth and safety, and other societal and socioeconomic considerations, and in rela tion to utilization of nuclear energy and licensed materials in the public interest.
It is the policy of ComEd to have all l evels of management strongly committed to radiation protection and, specifically, to ma intain occupational radiation exposures ALARA. Also, it is recognized that each worker must take pers onal responsibility for actions necessary to implement successful dose reduction measures.
ComEd's commitment to this policy is reflect ed in the ongoing station design, in the careful preparation and review of station operating and maintena nce procedures, and in the review of equipment design to inco rporate the results of operating experience.
QUAD CITIES - UFSAR Revision 4, April 1997 12.1-212.1.1.2 Management Respon sibilities and Organization
12.1.1.2.1 Corporat e ALARA Management Responsibilities and Organization This section has been deleted.
12.1.1.2.2 Station ALARA Management Responsibilities and Organization Commonwealth Edison Company has authoriz ed the creation of a Nuclear Station ALARA Committee which guides station ALARA activities. The Nuclear Station ALARA Committee approves ALARA decisions an d evaluations at the station.
12.1.1.3 Policy Implementation The management ALARA policy is implemented at the Quad Cities Station by the RPM and subordinates. The policy implementation is actualized via incorporation of ALARA policy considerations into the controlled station procedures.
12.1.2 Design Considerations This subsection discusses the methods and features by which the policy considerations of Subsection 12.1.1 ar e applied to ongoing station design.
Quad Cities Station radiation protection d esign objectives establish a direction for maintaining radiation exposure ALARA. Th e maintenance of ALARA considerations is accomplished by identifying problems and concerns associated with the plant and equipment, implementing desired modificati ons, and applying design objectives to effect improvements where appropriate.
The Quad Cities Station radiation protect ion design objectives utilized in the specification of facility design objectives (Subsection 12.1.2.2) and equipment design objectives (Subsection 12.1.2.3) to inco rporate ALARA policy philosophy can be generally stated as:
A. Minimizing the amount of time personnel spend in radiation areas; and
B. Minimizing radiation levels in routinely occupied plant areas and in the vicinity of plant equipment requiring attention.
These radiation protection design objectives are implemented in order to maintain exposures ALARA during normal plant condit ions, maintenance and repair activities, calibrations, refueling and waste handling operations, and other events of moderate frequency.
QUAD CITIES - UFSAR Revision 4, April 1997 12.1-312.1.2.1 Radiation Protectio n Design Considerations Quad Cities Station radiation protection desi gn objectives are directed to meet ALARA policy objectives and to ensure compliance wi th the standards for radiation protection specified in 10 CFR 20. Typical ALARA desi gn considerations include the following:
A. Establish design dose rates fo r general access areas based upon ComEd experience and 10 CFR 20 requirements;
B. Determine the most severe mode of operation for equipment and piping;
C. Determine the equipment or piping source (see Sections 11.1, 11.2, 11.3, and 11.4 for further discussion of source terms);
D. Determine shielding required to ma intain design dose rates (see Section 12.3 for further description of radiation shielding);
E. Determine advantages and disadvanta ges of equipment location, orientation, and segregation;
F. Use predetermined guidelines an d criteria for locating piping and penetrations;
G. Revise design as appropriat e to maintain exposures ALARA.
12.1.2.2 Facility Design Considerations
Quad Cities Station radiation protection design goals are translated into facility design objectives consistent with the ALARA policy.
Attainment of these objectives typically requires that station design take into co nsideration direct radiation and airborne radiation.
The design objectives are coupled with oper ating experience to obtain an improved station design relative to ALARA policy objectives.
12.1.2.2.1 Station Layout
The Quad Cities Station is arranged and desi gned with the following considerations to meet ALARA policy objectives:
A. A sufficient quantity of access path s (general access areas) are furnished to allow personnel attendance to equipment.
B. The radiation levels in general access areas are maintained ALARA.
C. Sufficient shielding is provided to control the amount of direct radiation present in a general access area.
QUAD CITIES - UFSAR Revision 4, April 1997 12.1-4 D. Radiation areas are classified into zones according to expected (maximum) radiation levels.
E. Segregation of radiation zo nes is employed when possible.
F. Shielding is utilized to accommoda te equipment removal and maintenance.
G. The radiation protection design is based upon the design criteria given in Section 12.3.
12.1.2.2.2 Ventilation The station ventilation systems aid in heat removal and control of airborne radioactive material. Ventilation systems are designed to direct potentially airborne radioactive material away from occupied areas and (except for the reacto r building vents) are normally discharged to the 310-foot chimney.
Ventilation systems are described in greater detail in Section 9.4. Other heatin g, ventilation and air conditioning systems have special functions, e.g., containment in erting (Section 6.2), and the standby gas treatment system (Section 6.5). The radiat ion protection aspects of these systems are discussed in Section 12.3.
12.1.2.2.3 Access Control Access to radioactive equipment is design ed so that properly trained radiation protection personnel can maintain radiat ion exposure to station workers ALARA during station operation. Access to ra diation areas is strictly controlled.
12.1.2.2.4 Control of Radioa ctive Fluids and Effluents Radioactive fluids (liquids and gases) are co ntained and controlled to keep the release of radioactive materials to general access areas and the environment ALARA. This
consideration applies to drain liquids, airb orne radioactivity, and process liquids and gases (i.e., reactor water, fuel pool water, radwaste water, drywell purge, off-gas, and turbine seal). The number of release paths are minimized in order to simplify control.
The process liquids and gases are stored and/
or processed within defined boundaries.
Systems which operate at positive or negative gauge pressures have closed boundaries. During normal operation, fluids from such systems escape their boundary only through pressure control eq uipment and by leakage. Some systems which operate at atmospheric pressure may ha ve openings in their boundary (vents).
The resulting airborne contaminants are di rected away from plant high occupancy areas and through particulate filters to the elevated release point. The ventilation systems are discussed in Section 9.4. The resulting liquid contaminants are directed from rooms or areas where the leakage o ccurs to liquid radwaste storage tanks.
QUAD CITIES - UFSAR Revision 5, June 1999 12.1-5The equipment drain system is connected to the liquid collection points attached to most equipment. The collected liquid is di rected to sump pumps which discharge to the liquid radwaste system.
The floor drain system is designed to ha ndle large volumes of liquid. Curbs are provided in component areas as required to prevent radioactive liquid that reaches the floor from contaminating low radiation ar eas, i.e., operating areas, general access areas, and corridors. Liquid radwaste ta nks are located in cubicles/rooms which are provided with sufficient drainage and isolat ion from other plant areas, thus ensuring that tank failure will not result in an unacceptable radiation release.
12.1.2.3 Equipment Design Considerations Radiation protection equipment design cons iderations involve shielding, equipment access, and segregation of radioactive equipment.
These considerations are incorporated in to ongoing station equipment design whenever it is reasonable to do so:
A. Locate equipment in accessible parts of cubicles;
B. Keep equipment that operates infreq uently in accessible areas, i.e., radwaste pumps; C. Provide galleries, gratings, and hatches to enhance accessibility to equipment located high above a floor;
D. Provide access for easy removal of equipment requiring frequent changing;
E. Provide localized shielding or sp ace and adequate structure for localized shielding as part of the shielding design;
F. Locate equipment which processes low radioactivity material in separate cubicles from equipment which processes high radioactivity material;
G. Separate high from low radioactivity lines that connect to a single component;
H. Use removable block walls to mini mize the radiation exposure in gaining access to highly radioactive components when removal is required; and
I. Provide cranes or lifting lugs to aid in equipment servicing, maintenance, and removal.
12.1.2.4 Equipment Selection
The selection of equipment to handle and pr ocess radioactive materials is based upon system requirements and radiation protect ion requirements such as minimizing leakage or spillage. Materials and coatings are selected for ease of decontamination as well as durability. Some components whic h may become contaminated are designed with provisions for flushing or cleaning.
Reduced occupational radiation exposure is attained by utilizing operating experience, and where practical, providing prudent equipment selections.
QUAD CITIES - UFSAR Revision 4, April 1997 12.1-612.1.2.5 Equipment Maintenance
In the operation of the station and its eq uipment, provisions are incorporated to assure that occupational radiation expo sure is maintained ALARA. Facility improvements and equipment selection are aimed toward reducing personnel radiation exposure from equipment maintenance. Fa cility improvements utilize experience that is accumulated from other operating BWR and PWR plants to aid operating personnel in reducing maintenance time when servicing and removing radioactive equipment.
This reduced maintenance time supports the ALARA policy objective of reduced occupational radiation exposure.
12.1.2.6 Servicing of Equipment and Instruments The servicing of equipment that handles, or is associated with radioactive fluids, is considered in the Quad Cities Station ongoing plant design. The types of servicing considered include maintenance, samp ling, inservice inspection, equipment decontamination, instrument calibration, ra diation surveys, and manual operation of equipment.
12.1.3 Operational Considerations This subsection discusses the methods an d features by which the ALARA policy considerations of Subsection 12.1.1 are a pplied to station operational activities.
To assure that individual dose equivalents are kept within the limits of 10 CFR 20 and that occupational radiation exposures are maintained ALARA during the operation of the Quad Cities Station, specific activiti es are implemented and governed by station procedures which incorporate oper ational ALARA considerations.
12.1.3.1 Operational Pr ocedure Considerations The ALARA procedures incorp orate ALARA policy considerations via the following:
A. Detailed procedures are prepared and approved for radiation protection during reactor plant operations. These procedures are a part of the station Health Physics Program and are reviewed to ensure incorporation of current ALARA policy.
B. All incoming and outgoing shipments which may contain radioactive material are surveyed to assure compliance with 10 CFR 20, 10 CFR 70, and
C. Any radiological incidents are th oroughly investigated and documented in order to minimize the potential for recu rrence. Reports are made to the NRC in accordance with 10 CFR 20.
QUAD CITIES - UFSAR Revision 5, June 1999 12.1-7 D. Periodic radiation, contaminatio n, and airborne activity surveys are performed and recorded to document radi ological conditions. Records of the surveys are maintained in accordance with 10 CFR 20.
E. Records of occupational radiatio n exposure are maintained and reports are made to the NRC as required by 10 CFR 20, and to individuals as required
by 10 CFR 19.
F. Radiation and high radiation areas are determined, segregated, and identified in accordance with 10 CFR 20.
Airborne activity is determined and posted in accordance with 10 CFR 20.
Positive control is exercised for each individual entry into high radiation areas. Posted radiological signs
and labels meet the requirements of 49 CFR 173 and 10 CFR 20.
G. Personnel are provided with pers onal radiation monitoring equipment in accordance with 10 CFR 20 to measure their external radiation exposure (see Section 12.5).
H. Process radiation, area radiation, portable radiation, and airborne activity monitoring instrumentation is period ically calibrated as required (see Section 11.5).
I. Access control points are establishe d to separate potentially contaminated areas from uncontaminated areas of the station.
J. Protective equipment and clothing (i.
e., respirators, masks, etc.) are used to help prevent personnel contamination an d the spread of contamination from one area to another.
K. All tools and equipment used in controlled areas are surveyed for contamination before removal from a controlled area. Tools and equipment removed from a contaminated area ar e normally packaged to prevent the spread of contamination to other areas.
L. Radiation work permits or equivalent document are issued for certain jobs in accordance with the station radiation pr otection procedures. Jobs involving significant radiation exposure to pe rsonnel are preplanned, evaluated, and approved per applicable station pr ocedures and ALARA considerations (ALARA review). Where conditions dict ate, a mockup is used for practice to reduce exposure time on the actual job. The use of special tools and
temporary shielding to reduce personnel exposure is evaluated on a job-by-job basis. Post-job debriefing is co nducted to enhance ALARA objectives for future tasks.
M. A bioassay program is included as part of the Health Physics Program. This program includes whole body counti ng and/or a urinalysis sampling program to measure the uptake of radioactive material (see Section 12.5).
N. An environmental monitoring progra m is in operation to measure any effect of the station on the surrounding environment (see Section 11.5).
O. All significant radioactive effluent pathways from the station are monitored and records maintained (see S ection 11.2, 11.3, and 11.5).
QUAD CITIES - UFSAR Revision 4, April 1997 12.1-8 P. There are sufficient experienced personnel to direct and train other personnel; training is accomplished via on-the-job experience, and by
completing a required employee tr aining course (see Section 13.2).
12.1.3.2 Operating Experience The Radiation Work Permit or equivale nt document process described in Section 12.1.3.1 provides a mechanism for collectio n and evaluation of data relating to personnel exposure. Information sorted by systems and/or components and job function assists in evaluating design or procedure changes intended to minimize future radiation exposures.
12.1.3.3 Exposure Reduction Exposure reduction techniques employed at Quad Cities Station are described in Subsection 12.5.3. Procedures assure that applicable station activities are completed with adequate preparation and planning; work is performed with appropriate health physics recommendations and support; and r esults of post job data evaluation are applied to implement improvements.
QUAD CITIES - UFSAR 12.2-1 12.2 RADIATION SOURCES
The initial licensing of Quad Cities Station predated issuance of Regulatory Guide 1.70, Revision 3. Therefore, the identification of radiation sources (beyond those in radwaste
systems) was not developed as part of the PSAR or FSAR. The purpose of identifying
radiation sources is to permit evaluation of radi ation protection design features described in Section 12.3 in order to provide reasonable a ssurance that radiation exposure of plant personnel will be within allowable limits. Ra diation surveys within the plant are made and evaluated as part of the ongoing ALARA program at Quad Cities.
Radiation sources generated in the reactor core and transpo rted by the reactor coolant system are described in Section 11.1. Radiatio n sources from components of the radioactive waste management systems are described in Sections 11.2, 11.3, and 11.4.
Radioactivity is also present in the fuel p ool cooling and cleanup systems described in Section 9.1.3, the reactor water cleanup sy stem described in Section 5.4.8, and the condensate cleanup system described in Section 10.4.6.
QUAD CITIES - UFSAR Revision 9, October 2007 12.3-1 12.3 RADIATION PROTECTION DESIGN FEATURES This section describes plant design features used to ensure that occupational radiation exposures resulting from the radiation sou rces within the plant meet the As Low As Reasonably Achievable (ALARA) cri teria described in Section 12.1. These features include shielding, ventilation systems, and radiatio n monitoring instruments. Supplemental procedures to control access to radiation area s and to control personnel exposure serve to limit radiation exposure to acceptable levels.
As a result of recommendations from the NRC's Three Mile Island Unit 2 (TMI-2)
Lessons Learned Task Force, Reference 1 documented a design review of plant sh ielding for areas requiring post-accident accessibility in response to Item 2.1.6.b of NUREG-0578 (TMI-2 Lessons Learned Task Force Status Report and Sho rt-Term Recommendations).
[12.3-1] 12.3.1 Facility Design Features
Radiation sources within Quad Cities Station differ appreciably with respect to location, intensity, and characteristics. The magnitud e of the dose rates that result from these sources is dependent on many factors includ ing the facility and equipment design, layout, mode and length of operation, and radiat ion source strength and characteristics.
Additional information on the design features of Quad Cities Station that protect personnel from radiation exposure and minimize radiat ion damage to plant equipment can be found in the following:
A. Section 12.1.2 explains how the statio n layout is used to minimize radiation exposure;
B. Section 12.1 addresses control of access to radiation areas;
C. Section 11.5 addresses process and effluent radiation monitoring;
D. Section 11.1 through 11.4 des cribe radioactive waste processing;
E. Section 12.5 describes the radi ochemical laboratory facilities; and
F. Section 12.1 addresses equipment se lection to minimize exposure during operation and maintenance.
12.3.2 Shielding
Normal operating conditions determine the ma jor portion of the shielding requirements.
Two notable exceptions to this are the contro l room where shielding is determined by the radiation levels produced during a loss-o f-coolant accident, and the shutdown cooling system where shielding is determined by shutdown conditions.
QUAD CITIES - UFSAR Revision 4, April 1997 12.3-2 12.3.2.1 Design Objectives
The basis for the design of the radiation shielding is in compliance with the requirements of
10 CFR 20 which describes the limits of occupati onal radiation exposure. Compliance with these regulations is achieved in part through shield design which is based upon occupancy requirements in various areas. A list of ge neralized occupancy requirements and attendant radiation dose-rates is presented in Table 12.3-1. The duration of expected operating
personnel occupancy in various areas of each unit was obtained from experience during operation of Dresden Unit 1 and ot her similar nuclear-powered units.
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Radiation areas with dose rates in excess of those listed in Table 12.3-1 are entered on a
controlled time basis. Radiation areas in excess of 100 mrem/hr whole body dose are
equipped with warning signs in compliance with 10 CFR 20.
The primary objective of the radiation shieldin g is to protect personnel against radiation emanating from the reactor, the turbine, and their auxiliary systems.
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The secondary objective of the radiation shieldin g is to limit radiation damage to operating equipment. Specific fabrication materials are given individual consideration. Of principal concern are organic materials used in the equi pment; e.g., insulation, rubber tank linings, and gaskets.
In general, it is sufficient to limit the radiation exposure to 10 6 rads for materials of concern over the expected service life of the equipment or of individual parts. For certain materials the exposure must be less, or can be greater, without significantly affecting serviceability; e.g., a limit of 10 4 rads for teflon and about 10 8 rads for polyurethane.
The shielding materials required to meet the preceding objectives are primarily concrete, water, and steel. High density concrete, lead , and neutron-absorbing material are used as alternates in special applications. The design dose rate in most areas outside of the drywell in the reactor building is one mrem/hr. Co nsequently, the drywell and its contents are shielded so that most areas outside the dr ywell and outside the pressure suppression chamber are accessible. Actual dose rate increases resulting from crud buildup are evaluated as part of the station ALARA program.
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12.3.2.1.1 Control Room
The dose rate in the control room is limited to 0.5 rem in any 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period following a design basis accident in either Unit 1 or Un it 2. Including shielding by structures other than that associated with the reactor building, the total shielding provided for the control room is sufficient to limit the transmission of radiation from the reactor building during normal operation of either Unit 1 or Unit 2 to less than 0.1% of the above limit. A discussion of control room habitability is contained in Section 6.4.
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QUAD CITIES - UFSAR Revision 10, October 2009 12.3-3 12.3.2.1.2 Reactor Building
Within the reactor building, but outside the primary containment, some of the regions
where the radiation level may exceed one mrem/hr are:
A. Fuel storage pool;
B. Reactor water cleanup system;
C. Residual heat removal (RHR) system;
D. The operating floor directly over th e drywell shielding plugs above the reactor vessel (estimate about 6 mrem/hr);
E. The region housing the suppression c hamber portion of the pressure suppression system; F. Miscellaneous equipment (e.g., fu el pool heat exchanger, cleanup heat exchangers, etc.);
G. High pressure coolant injection system;
H. Reactor building crane cab;
I. Reactor core isolation cooling system; and
J. Core Spray System.
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12.3.2.1.3 Turbine Building
Within the turbine building, where the major radiation source is N-16, shielding is provided
for the following areas:
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A. Main condenser - hotwell;
C. Air ejector and the gland seal exhauster;
D. Condensate demineralizer tanks;
E. Steam piping - moisture separators; and
F. Steam turbine.
Most of the turbine operating floor is accessible and the turbine building crane can be
operated remotely as required.
QUAD CITIES - UFSAR 12.3-4 Table 12.3-2 provides a listing of design radi ation levels outside shielded areas of the turbine building. When the hydrogen injection system is operated, the resulting increase in N-16 activity can cause these levels to increase.
Any new high radiation areas created as a result of operating the hydrogen injection syst em are controlled in accordance with existing plant procedures implementing the ALARA Prog ram. The hydrogen injection system is part of the hydrogen water chemistry (HWC) sy stem and is described in Section 5.4.3.
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12.3.2.1.4 Off-Gas System
The shielding for the off-gas air ejector, reco mbiner room, and off gas condenser is based upon N-16 and the noble gases as principal radiation sources. Hydrogen injection has
increased the original N-16 levels. The addi tional dose rates resulting from hydrogen injection are controlled as part of the ALARA program. The noble gas component of the
combined radiation source is based upon an average annual release rate of 0.45Ci/s.
Shielding for the off-gas filters is based upon the accumulation of particulate radionuclides
that are produced by the decay of the no ble gases during a 30-minute holdup time.
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12.3.2.1.5 Radwaste Building
The radwaste building shielding is designed to limit the dose rate in the building control room to approximately one mrem/hr. Regi ons where pumps and valves are located have higher radiation levels. The solid waste prep aration area is shielded and provides for remote operation of equipment. Ample shieldin g has been provided in the radwaste system design to maintain personnel exposure well be low established limits. Sumps, tanks, and other high activity vessels are housed in limit ed-access areas or concrete cells. Piping which would contribute significant radiation dose ra tes is shielded or kept out of normally frequented areas.
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12.3.2.2 Description
This subsection describes the design of the radiation shielding for the reactor vessel, the drywell, the RHR system components, the control room, the turbine and main steam
system, and the condensate demineralizers.
12.3.2.2.1 Reactor Shield Wall
Within the drywell a shield wall of concrete is provided between the reactor vessel and the drywell walls to limit gamma heating in the drywell concrete, provide shielding for access in the drywell during shutdown, and limit activa tion of drywell materials by neutrons from the core.
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QUAD CITIES - UFSAR Revision 6, October 2001 12.3-5 The reactor shield wall consists of a 24-foot diameter circular cylinder attached to the vessel support pedestal which extends upward approximately 45 feet. The reactor shield wall is 27 inches thick. The steel plates are increased in thickness for extra shielding
opposite the elevation of the core. This shell is filled with concrete to provide shielding capability. See Section 3.6.2.3 for additional information on the construction of the shield wall.
The pipes leaving the vessel at elevations belo w the top of the reactor shield penetrate the shield. The penetrations in the vicinity of th e core use removable shield plugs which fit around each pipe penetrating the shield wall.
The plugs allow access to the pipe welds for inservice inspections. These removable plugs ar e covered by two 9-inch-thick steel plates attached to the shield wall by two 1 1/2-inch diameter vertical hinges, with both halves locked in place by a 1-inch diameter lockin g pin. Recirculation piping penetrates this annular shield wall around the reactor vesse
- l. These penetrations also have removable shielding sections at the annular shield so that access is available for inspection of the
connections between the recirculation piping and the reactor vessel. The region that houses the control rod drives is shielded against ra diation from the recirculation piping. This piping constitutes a radiation source during s hutdown as a result of deposited activation products.
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During reactor operation, the reactor shield wa ll serves as a thermal shield to protect the containment shield wall outside the drywell from thermal damage. During shutdown, this shield also serves to protect personnel in th e drywell from gamma radiation from the core and the reactor vessel. The shield wall is cooled on both surfaces by circulating air from the drywell cooling system.
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12.3.2.2.2 Containment Shield Wall
The primary containment vessel for each reacto r is completely enclosed in a reinforced concrete structure (an integral part of the re actor building) having a variable thickness of from 4 - 6 feet (see P&IDs M-3 and M-9). In addition to serving as the basic shielding for the reactor system, this concrete structure al so provides a major mechanical barrier for the protection of the containment vessel and th e reactor system against potential missiles generated external to the primary containment.
It also serves as a backup for the drywell wall in resisting jet forces. Additional inform ation on missile protection is contained in Section 3.5. Jet forces and other effects of pipe breaks are described in Section 3.6.
The main support for the containment shield wa ll (which is structurally designed to handle the loads of floors, equipment, and the higher elevations of the shield itself) is the reactor building foundation which is set on bedrock.
Penetrations through the containment shield wall are designed so that they are not aligned directly with the core or major items of equi pment in the drywell. In addition, they are either terminated in shielded cubicles or are shielded with steel flanges to reduce radiation levels in accessible areas.
QUAD CITIES - UFSAR Revision 7, January 2003 12.3-6 12.3.2.2.3 Residual Heat Removal System The heat exchangers and pumps of the RHR sy stem are located in separate, shielded cubicles. Gamma radiation from the equipment in these cubicles is reduced to a designed dose-rate of about 2 mrem/hr or less at the time the system was initially placed in operation.
12.3.2.2.4 Control Room
The shielding for the control room consists of poured-in-place reinforced concrete. The floor and ceiling slabs are 6 inch thick ordinary con crete whereas the walls range in thickness from 18 inches of ordinary concrete to 27 inches of magnetite concrete.
Shadow shielding offered by other structures is used to reduce shielding thicknesses and to locate penetrations. The control room shielding is described more fully in Section 6.4.2.5.
12.3.2.2.5 Turbine Steam Handling Equipment
The steam handling equipment associated with th e turbine-generator unit is shielded with concrete to reduce the radiation levels in accessible areas, as shown in Table 12.3-2.
12.3.2.2.6 Condensate Demineralizer System
For each reactor, the demineralizer vessels are located in a shielded enclosure. The radiation penetrating the concrete shielding of this enclosure was initially less than 1 mr/hr exclusive of radiation shine (streaming). Recycle pumps, valves, some piping,and instrumentation associated with the deminera lizer vessels are located in the operating aisle. Piping carrying condensate or deminera lized condensate does not require shielding.
12.3.2.3 Performance Analysis
Visual inspections of the shielding were cond ucted during the construction phase to locate major defects. Upon initiation of reactor oper ation, radiation surveys were performed at various power levels. The purpose of these surveys was to assure that:
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A. There were no defects or inadequacies in the shielding, equipment or operating procedures that could result in unacceptabl e levels of radiation exposure to the public, the operators, or the equipment.
B. Radiation areas are posted. In addition to posting, high radiation areas are controlled by 10 CFR 20 requirements.
QUAD CITIES - UFSAR Revision 13, October 2015 12.3-7 These surveys consisted of both gamma and ne utron monitoring with appropriate portable instrumentation. Gamma surveys were performe d on all shielding, while neutron surveys were conducted around the containment sh ield wall and associated penetrations.
The radiation protection department routinely conducts surveys of dose rates throughout the plant during the course of plant operation, and additional shielding is added when and where the need arises.
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12.3.3 Ventilation
Quad Cities Station has separate ventilation systems for the control room, reactor building, turbine building, and radwaste building. Each of these systems provides personnel
protection from airborne radioactive contaminant s by filtering inlet air and routing filtered air to areas of progressively greater contami nation potential. Pressure differentials are maintained to prevent backflow of potentially contaminated air. Additionally, the control room ventilation system is capable of isolatio n from the outside air during a radioactivity release. The plant ventilation systems are addressed in Section 9.4. Control room habitability is addressed in Section 6.4.
12.3.4 Area Radiation and Airborne Ra dioactivity Monitoring Instrumentation The area radiation monitoring system conti nuously monitors and records the radiation level in accessible work areas of the plant.
Monitors are provided in four different sensitivity ranges chosen to match the expecte d radiation level of the area in which the monitor is installed. If the radiation level in any area exceeds that determined by site health-physics requirements, an alarm is annunciated to alert personnel to the hazard potential. A description of the use of the area radiation monitors to detect radioactive water leakage is presented in Section 5.2.6.2. The hi gh radiation sample system is described in Section 9.3.2.
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The area radiation monitors (ARM) constitute a fixed in-place network encompassing 70 stations, reporting alarm conditions to the control room for Unit 1 and 2 ARMs and, in areas where high radiation is most likely to occur, also actuating a local alarm.
The Unit 1/2 ARMs provide local indication and alarm conditions only.
Areas (stations) monitored by the area radiat ion monitoring system are listed in Tables 12.3-3, 12.3-4 and 12.3-5 which also identify expected background radiation and those
stations with local auxiliary units (local al arms). Typical monitoring channels with and without local auxiliary units are shown in Figure 12.3-1. Each channel consists of a sensor, a converter (detector) unit with a corresponding indicator and trip unit. Each Unit has a common multipoint recorder in the main contro l room that is shared by the channels. The channels also share common power supplies, each of which can supply up to 10 channels.
The power supplies are mounted on the same control room panel [901(2)-11] as the
indicator and trip units. The only controls us ed during operation of the area radiation monitoring system are reset switches on the indicator and trip units. Actuation of an alarm requires manual resetting of the alarm circuit in the corresponding indicator and trip unit.
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QUAD CITIES - UFSAR Revision 5, June 1999 12.3-8 The sensor in each channel is a Geiger-Mueller (G-M) tube, polarized by high voltage from the power supply. Pulses produced in the t ube by radiation are converted to dc output signals by the converter, and applied to th e indicator and trip unit to drive a back panel meter and the multipoint recorder. Trip ci rcuits in the indicator and trip unit actuate control room alarms which denote high or lo w radiation. Downscale trips share a common malfunction annunciator. Station 31 in Unit 1 and Station 25 in Unit 2 have individual downscale alarms in panel 901(2)-54. Upscale trips are applied to one of six high radiation
During exposure to higher-than-rated exposu re levels, a G-M tube will operate with increasing output (to at least 10
^4^ R/hr). The G-M tube circuitry is designed utilizing both the pulse and dc G-M modes with the outputs summed into the indicator and trip units.
Additionally, a special circuit has been included to prevent meter fall-off at exposure levels considerably in excess of full scale. The circuit output continues to increase until the
amplifier saturates, and then remains at that level for further increases in flux. Under extended periods of operation at high levels , the detector could be subject to failure by deterioration of the ionization gas or by heat induced mechanical failure.
[12.3-19]
In channels provided with local auxiliary units, these units are located near the sensor and converter (detector). High radi ation trips in these channels result in the sounding of a local audio alarm (Klaxon horn) as well as the control room annunciation.
[12.3-20]
Area radiation monitor detectors are distributed (see Tables 12.3-3, 12.3-4 and 12.3-5) in
such a way that radiation dete ction coverage is provided in any areas where personnel may be required to work for extended periods. Th e ranges and sensitivities of the equipment are sufficient to detect increases in radiat ion level and annunciate an alarm above a preselected level. All monitors annunciate an alarm on failure.
The ARMs in the vicinity of the spent fuel pool are part of the reactor building ventilation
radiation monitoring subsystem described in Section 11.5.2.4 and have the capability of shutting down the reactor building HVAC syst em and starting the standby gas treatment system (SBGTS) in the event of a refueling acci dent. The refueling accident is analyzed in Section 15.7.2.4.
Eight ARMs also serve for satisfying the re quirements of the Station's Exemption to 10 CFR 70.24, "Criticality accident requirement s." Four of these ARMs are part of the ARM System, and are Unit 1 ARM Stations 1, 3, & 4, and Unit 2 Station 1, which are described in more detail in UFSAR Table 12.3-3 or 12.3-4. The other four ARMs are the
four Refuel Floor Radiation Monitors shown on UFSAR Figure 11.5-3, which are part of the Reactor Building Ventilation Radiation Monitori ng Subsystem, and are described in more detail in UFSAR Section 11.5.2.4. These eight ARMs are provided in fuel storage and
handling areas to detect excessive radiation levels and to either initiate, or allow initiation of, appropriate safety actions. The Exempt ion from 10 CFR 70.24 is described in more detail in UFSAR Section 9.1.1.4.
QUAD CITIES - UFSAR Revision 5, June 1999 12.3-9 12.3.5 Reactor Building Crane Monitoring Subsystem The purpose of this subsystem is to prevent the crane operator from causing accidental exposure to radioactive material by raising i rradiated material above the level of the water and exposing the operator and other personnel to radiation. The reactor building crane is described in Section 9.1.
[12.3-21]
As shown in Figure 12.3-2, a sensor and conv erter (detector) unit is mounted on the crane in a position to monitor the crane work area. A four-decade indicator and trip unit mounted in the crane cab displays the radiation level si gnaled by the sensor and converter unit. The indicator and trip unit provides trip function s for upscale and downscale radiation level changes. The trip points may be preset to tri p at any desired level. The trips operate inhibit/permissive relays in the crane control circuits to prevent the crane hook from being raised in the event of a high radiation (upscale) or malfunction (downscale) signal from the
indicator and trip unit. Signal power is prov ided by a cab-mounted power supply and line cord, which draws 120-Vac from the crane power ac circuit breaker.
A keylock switch is installed in the crane c ab to bypass the ARM trip unit. This bypass is used when moving highly radioactive material with the crane. Bypassing the trip unit will allow the crane hoist to operate in a high radi ation field while still allowing the operator to read the ambient radiation level from the ARM indicator.
[12.3-22]
QUAD CITIES - UFSAR Revision 9, October 2007 12.3-10 12.3.6 References
- 1. Post-Accident Radiation Levels Report (A Review of the Quad Cities Station in Response to Item 2.1.6.b of NUREG-0578).
(Sheet 1 of 1)
QUAD CITIES - UFSAR
Table 12.3-1
RADIATION AREAS OCCUPANCY REQUIREMENTS AND DESIGN RADIATION DOSE RATES (Note 1)
Degree of Access Required Design Radiation Dose Rate, at Shield Wall -- mrem/hr
- 1. Continuous Occupancy
- a. Outside controlled areas 0.5 b. Inside controlled areas 1 2. Limited Occupancy a. Occupancy up to 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />s/week 6 b. Occupancy up to 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />s/week 12
- 1. Plant radiation levels are routinely surveyed to determine boundaries of controlled areas. Due to plant operations, dose rates inside and outside controlled areas may
vary from those listed above. These area s are controlled by 10 CFR 20 requirements.
(Sheet 1 of 1)
Revision 6, October 2001 QUAD CITIES - UFSAR
Table 12.3-2 SHIELDED TURBINE STEAM HANDLING EQUIPMENT AND DESIGN RADIATION DOSE RATES Equipment Design Radiation Level Outside Shield Radiation Level Outside Shield with Hydrogen Injection System Operating (Note 1 and 2)
Radiation Level Outside Shield with Noble Metal Chemical Addition and Hydrogen Injection System Operating (Note 4) Turbine-Generator, Stop-Intercept
Valves, Piping 5 mrem/hr in regions beyond the turbine shield wall at the operating floor level at elevation 639 ft. 80 mrem/hr (Note 3) 0.2-1 mrem/hr in regions beyond the turbine shield wall at the operating floor level at elevation 639 ft.
Moisture Separators and Piping 1 mrem/hr through walls 0.6 mrem/hr 0.1 mrem/hr Stop Valves and Piping 1 mrem/hr through building operating floor 1.8 mrem/hr No data available Air Ejectors, Steam Packing Exhausters, and Piping
5 mrem/hr through walls 0.2 mrem/hr 0.2 mrem/hr Low Pressure Feedwater Heaters 1 mrem/hr through walls 1.0 mrem/hr 0.1 mrem/hr
- 1. Surveys have measured levels similar to those listed, primarily due to hydrogen injection system increase of N-16 levels above the original design dose rates. Access to radiation areas created in this manner is controlled by ALARA considerations.
- 2. Dose rates obtained from "Hydrogen Injection Test, Quad Cities Nuclear Power Station, Radiation Protection Report, September 1990."
- 3. Survey Points taken at gates in the turbine shield wall that provide access to the turbine-generator. These do not impact safety due to the rapid decline in dose rate with respect to distance from the gates. 4. Dose rates taken from surveys on Unit 1 after noble metal chemical addition and hydrogen injection system operating at 11 scfm.
(Sheet 1 of 4)
Revision 6, October 2001 QUAD CITIES - UFSAR
Table 12.3-3
QUAD CITIES UNIT 1 AREA RADIATION MONITORING SYSTEM SENSOR LOCATION AND RANGE
Station Floor Elevation Column Row Area Range (mR/hr) Expected Background (mR/hr) Local Auxiliary Unit and Alarm 1 690 ft 6 in. H-15 Reactor Building Refueling Floor - Low Range 0.01-100 1 X 2 690 ft 6 in. H-15 Reactor Building Refueling Floor - High Range 10-10
^6^ 1 3 690 ft 6 in. N-14 Reactor Building Refueling Floor - Equipment Hatch 0.01-100 1 4 666 ft 6 in. M-14 New Fuel Storage Vault Access 0.1-1,000 1 (10 in vault) 5 666 ft 6 in. L-18 Contaminated Equipment Storage 0.01-100 6 6 647 ft 6 in. M-15 Fuel Pool Pump and Heat Exchanger Area 0.01-10,000 1 7 647 ft 6 in. M-18 CRD Storage and Repair Room 0.1-1,000 6 8 647 ft 6 in. J-17 Cleanup Instrument Rack Area 0.01-10,000 1 9 623 ft 0 in. J-18 Cleanup Pump Area 0.01-10,000 1 10 623 ft 0 in. M-13 Mezzanine Floor Access 0.01-100 1 (Sheet 2 of 4)
Revision 12, October 2013 QUAD CITIES - UFSAR
Table 12.3-3
QUAD CITIES UNIT 1 AREA RADIATION MONITORING SYSTEM SENSOR LOCATION AND RANGE
Station Floor Elevation Column Row Area Range (mR/hr) Expected Background (mR/hr) Local Auxiliary Unit and Alarm 11 595 ft 0 in. K-19 CRD Hydraulic Control Units - South 0.01-10,000 1 12 595 ft 0 in. K-13 CRD Hydraulic Control Units - North 0.01-10,000 1 13 595 ft 0 in. H-13 TIP Drive Machinery 0.01-10,000 1 X 14 595 ft 0 in. H-15 TIP Cubicle 1-10,000 1000 (wire withdrawn)
X 15 554 ft 0 in. N-17 Suppression Chamber Access 1-10,000 15 (200 at contact) 16 554 ft 0 in. G-15 HPCI Cubicle 1-10,000 30 (operating) 1 (normal) 17 554 ft 0 in. G-14 RCIC Cubicle 1-10,000 6 (operating) 1 (normal)
(Sheet 3 of 4)
Revision 12, October 2013 QUAD CITIES - UFSAR
Table 12.3-3
QUAD CITIES UNIT 1 AREA RADIATION MONITORING SYSTEM SENSOR LOCATION AND RANGE
Station Floor Elevation Column Row Area Range (mR/hr) Expected Background (mR/hr) Local Auxiliary Unit and Alarm 18 639 ft 0 in. E-25 Turbine Building Operating Floor Access - South 0.01-100 1 19 639 ft 0 in. D-14 Turbine Building Operating Floor Elevator Area 0.01-100 1 20 626 ft 0 in. C-21 Air Ejector Access - 1B 0.01-100 1 X 21 626 ft 0 in. C-18 Air Ejector Access - 1A 0.01-100 1 X 22 623 ft 0 in. G-25 Control Room 0.01-100 0.5 23 595 ft 0 in. C-19 Feedwater Heater Access 0.1-1,000 1 24 595 ft 0 in. G-21 Feedwater Pump 0.01v100 1 25 572 ft 6 in. D-18 CRD Feed Pump Access 0.1-1,000 1 26 547 ft 0 in. E-19 Condensate/Booster Pump 0.01-100 10 27 595 ft 0 in. C-14 Radwaste Control Room 0.01-100 0.5 X (Sheet 4 of 4)
Revision 7, January 2003 QUAD CITIES - UFSAR
Table 12.3-3
QUAD CITIES UNIT 1 AREA RADIATION MONITORING SYSTEM SENSOR LOCATION AND RANGE
Station Floor Elevation Column Row Area Range (mR/hr) Expected Background (mR/hr) Local Auxiliary Unit and Alarm 28 595 ft 0 in. B-13 Radwaste Operating Area - South Wall 0.01-100 1 X 29 571 ft 0 in. B-12 Radwaste Pump Room Access 0.01-100 6 X 30 622 ft 0 in. B-12 Radwaste Centrifuge Access 0.01-100 1 X 31 561 ft 0 in. - Filter Building Charcoal Bed Vault 1-10 6 1000 X 32 648 ft 6 in. - Recombiner Area Level 1 0.01-100 5 33 668 ft 0 in. - Recombiner Area Level 2 0.01-100 5 34 35 591 ft 0 in. E. Wall Max. Recycle Building 1-10,000 10 X 36 596 ft 11 in. SW Corner Radwaste Tank Room 0.1-1,000 2 X
NOTE: Unit 1 SBGTS is monitored by Unit 2 ARM Station 16.
(Sheet 1 of 3)
Revision 12, October 2013 QUAD CITIES - UFSAR
Table 12.3-4
QUAD CITIES UNIT 2 AREA RADIATION MONITORING SYSTEM SENSOR LOCATION AND RANGE
Station Floor Elevation Column Row Area Range (mR/hr) Expected Background (mR/hr) Local Auxiliary Unit and Alarm 1 690 ft 6 in. H-11 Reactor Building Refueling Floor - Low Range 0.01-100 1 X 2 690 ft 6 in. H-11 Reactor Building Refueling Floor - High Range 10-10
^6^ 1 3 647 ft 6 in. M-11 Fuel Pool Pump and Heat Exchanger Area 0.01-10,000 1 4 647 ft 6 in. J-9 Cleanup Instrument Rack Area 0.01-10,000 1 5 623 ft 0 in. J-8 Cleanup Pump Area 0.01-10,000 1 6 595 ft 0 in. K-13 CRD Hydraulic Control Units - South 0.01-10,000 1 7 595 ft 0 in. K-7 CRD Hydraulic Control Units - North 0.01-10,000 1 8 595 ft 0 in. H-13 TIP Drive Machinery 0.01-10,000 1 X 9 595 ft 0 in. H-11 TIP Cubicle 1-10,000 1000 (wire withdrawn)
X 10 554 ft 0 in. N-9 Suppression Chamber Access 1-10,000 15 (200 at contact)
(Sheet 2 of 3)
Revision 12, October 2013 QUAD CITIES - UFSAR
Table 12.3-4
QUAD CITIES UNIT 2 AREA RADIATION MONITORING SYSTEM SENSOR LOCATION AND RANGE 11 554 ft 0 in. G-11 HPCI Cubicle 1-10,000 20 (operating) 2 (normal) 12 554 ft 0 in. G-11 RCIC Cubicle 1-10,000 8 (operating) 1 (normal) 13 639 ft 0 in. F-1 Turbine Building Operating Floor 0.01-100 1 14 626 ft 6 in. C-5 Air Ejector Access 0.01-100 1 X 15 626 ft 6 in. C-8 Air Ejector Access 0.01-100 1 X 16 666 ft 6 in. N-17 Standby Gas Treatment - Unit 1 0.01-10,000 6 (operating) 1 (normal)
X 17 595 ft 0 in. C-7 Feedwater Heater Area 0.1-1000 1 18 595 ft 0 in. G-5 Feedwater Pump Area 0.01-100 1 19 595 ft 0 in. D-13 Condensate Demineralizer Control Panel 0.01-100 1 X (Sheet 3 of 3)
Revision 7, January 2003 QUAD CITIES - UFSAR
Table 12.3-4
QUAD CITIES UNIT 2 AREA RADIATION MONITORING SYSTEM SENSOR LOCATION AND RANGE 20 595 ft 0 in. G-11 Safe Shutdown Pump Area 0.1-1000 1 21 572 ft 6 in. D-8 CRD Feedwater Pump Access Area 0.1-1000 1 22 547 ft 0 in. E-7 Condensate/Booster Pump Area 0.01-100 10 23 666 ft 6 in. N-9 Standby Gas Treatment - Unit 2 0.01-10,000 6 (operating) 1 (normal)
X (No local alarm.) 24 - 25 561 ft 0 in. - Filter Building Charcoal Bed Vault 1-10
^6^ 2000 X 26 648 ft 6 in. - Recombiner Area Level 1 0.01-100 5 27 668 ft 0 in. - Recombiner Area Level 2 0.01-100 5 28 561ft 0 in. - Off-Gas Filter Building Level 1 0.01-100 5 X 29 574 ft 6 in. - Off-Gas Filter Building Level 2 0.01-100 1 X 30 594ft 6 in. - Off-Gas Filter Building Level 3 0.01-100 1 X
(Sheet 1 of 1)
Revision 7, January 2003 QUAD CITIES -- UFSAR
Table 12.3-5
QUAD CITIES UNIT 1/2 AREA RADIATION MONITORING SYSTEM SENSOR LOCATION AND RANGE
Station Floor Elevation Column-Row Detector Location Range (MR/HR) Expected Background (mR/hr) Local Unit Auxilliary and Alarm 1 690 ft 6 in Reactor Building Crane 0.1-1,000 2 X 2 605 ft 0 in Radwaste Bldg. Catwalk Shield - East Wall 1-10,000 2 X 3 595 ft 0 in Radwaste Bldg. North Truckbay - North Wall 0.1-1,000 2 X 4 5 Radwaste Bldg. Mixing Tank 10-100,000 Varies 6 Radwaste Bldg. Mixing Tank Room 10-100,000 Varies 7 Radwaste Bldg. Valve Room on Decant Line 1-10,000 Varies
QUAD CITIES - UFSAR 12.4-1 12.4 DOSE ASSESSMENT Dose assessment is a continuing program for the Quad Cities Station as a part of the ALARA program. The station collects and evaluat es radiation dose data in accordance with the ALARA program. Dose assessment inform ation was not developed as a part of the FSAR and its amendments during initial licensi ng. Design radiation dose rates for Quad Cities Station are presented in Table 12.3-1.
[12.4-1]
QUAD CITIES - UFSAR Revision 13, October 2015 12.5-1 12.5 HEALTH PHYSICS PROGRAM
12.5.1 Organization
The station organization provides the Radiat ion Protection Technical Supervisor direct access to the Radiation Protection Manager and Plant Manager to assure uniform support of the Health Physics Program and ALARA policy.
This organization allows the Radiation Protection Manager and Station Manager direct involvement in the review and approval of specific ALARA goals and objectives as well as review of data and dissemination of information related to ALARA policy implementation.
[12.5-1]
12.5.2 Equipment, Instrumentation, and Facilities
Refer to Section 12.3 for a discussion of fa cility design features to ensure radiation exposures are maintained as low as reasonably achievable (ALARA).
12.5.2.1 Monitoring
Contamination monitors are provided at the ex its from potentially contaminated areas. A portal monitor is located in the security build ing, where each person leaving the plant is required to pass and check through this monitor when operational.
12.5.2.2 Laboratories
The following instrument list is intended to be typical of in-service instrumentation:
For ALPHA, monitor type - gross activity with either an ioniza tion or scintillation detector For BETA, monitor type - gross activity with either an ioniza tion or scintillation detector For GAMMA, monitor type - specific activi ty with an Hp Ge ionization detector For TRITIUM, monitor type - specific activity with a scintillation detector
[12.5-2]
12.5.2.3 Health Physics and Laboratory Radiation Measuring Instruments
Battery powered portable radiation survey ins trumentation is provided for use by qualified personnel. Select station personnel are ac quainted with and qualified to operate this instrumentation.
[12.5-3]
QUAD CITIES - UFSAR Revision 14, October 2017 12.5-2 12.5.2.3.1 Design Basis
Radiation survey instruments are available for the measurement of alpha, beta, gamma, and neutron radiation expected in normal operation and emergencies, as needed.
Appropriate instruments and auxiliary equipm ent are available to detect and measure radioactive contamination on surfaces, in air, and in liquids.
[12.5-4]
12.5.2.3.2 Description
Contamination monitors are provided at exit s from potentially contaminated areas.
Personnel dosimeters are provided to and worn by persons in these areas as required by 10 CFR 20 regulations. Laboratory radiation-me asuring instruments are provided for alpha, beta, and gamma radiation, and for gaseous, liquid, and solid samples. Secondary
calibration sources and check-test sources for the various instruments are provided.
12.5.3 Radiation Protection Program
12.5.3.1 General
Radiation Protection Procedures are designed to ensure protection of personnel against exposure to radiation and radioactive materi als in a manner consistent with applicable regulations. Procedures for personnel radi ation protection are consistent with the requirements of 10 CFR 20 and are approved, main tained, and adhered to for all operations involving personnel radiation exposures. It is the policy of Exelon Generation Company to maintain personnel radiation exposure within the regulations, and further reduce such exposure ALARA. Therefore, personnel are in structed to minimize exposure consistent with discharging their duties. Each individ ual is responsible for observing rules adopted for his or her safety and that of others.
[12.5-5]
The R.P.M. evaluates the radiological condit ion of plant operations and establishes the procedures to be followed by all personnel.
This ensures compliance with all applicable regulations and maintenance of the require d radiation protection records.
Training of operators, maintenance personne l, and technical personnel in radiation protection principles and procedures takes place as determined using processes derived from the Systematic Approach to Traini ng. New employees, contractors and other supporting personnel are given orientation training at the beginning of their work assignments.
QUAD CITIES - UFSAR Revision 12, October 2013 12.5-3 12.5.3.2 Personnel Monitoring
The official and permanent records of accumula ted external radiation exposure received by individuals required to be monitored by 10 CFR 20 are obtained from the interpretation of the dosimeter of legal record (DLR) and/or direct reading dosimeters.
12.5.3.3 Dosimeters
Radiation monitoring devices are issued to all personnel as required by 10 CFR 20.
Dosimeter records furnish the exposure data for the administrative control of radiation exposure.
[12.5-6]
Each individual is instructed in the necessity of checking the direct reading dosimeter at frequent intervals while in radiation areas.
12.5.3.4 Monitoring of Visitors
All visitors to the Quad Cities Station who en ter a radiation area are monitored by a direct reading dosimeter and/or a DLR, or are prov ided with an escort having such monitoring devices. Any visitor who enters a high ra diation area is issued a DLR and/or a direct reading dosimeter.
12.5.3.5 Bioassay and Medical Examination Program
Exelon Generation Company provides whol e-body radiation counting service for all regularly assigned personnel, contractors, and visitors at Quad Cities Station.
[12.5-7]
Medical examinations are performed on a schedu le consistent with ANSI Z88.6 section 6.1.
The Medical Department reviews these examinat ions to ensure compliance with federal requirements and guidelines.
12.5.3.6 Personnel Protective Equipment
All personnel shall adhere to RWP or equivale nt document requirements when entering the RPA. The nature of the work to be done is th e governing factor in the selection of protective clothing to be worn. The protective appare l available includes shoe covers, head covers, gloves, and coveralls or lab coats. Additional items of specialized apparel such as plastic or rubber suits, face shields, and respirators are available for operations involving high level contamination. Available respiratory protecti ve equipment has been approved for use by the NRC, in accordance with Regulatory Guide 8.15 and 30 CFR 11. (30 CFR 11 has been
relocated to 42 CFR 84) In all cases, radi ation protection personnel shall evaluate the radiological conditions and specify the required items of protective clothing.
[12.5-8]
QUAD CITIES - UFSAR Revision 6, October 2001 12.5-4 12.5.3.7 Radiological Posted Areas Radiological areas are posted as radiation area s, high radiation areas, radioactive materials areas, airborne radioactivity areas, or combi nations thereof. Access to posted areas for all work is authorized in accordance with the Radiation Protection Procedures.
[12.5-9]
12.5.3.8 Access to Radiation Areas
A restricted area is defined by 10 CFR 20 as any area controlled by the licensee for purposes of protection of individuals from expo sure to radiation and radioactive materials.
A radiation area is defined by 10 CFR 20 as any area, accessible to personnel, in which there exists radiation, at such levels that an individual could receive in any one hour a dose equivalent in excess of 5 millirem, at 30 cm fr om the radiation source or from the surface that the radiation penetrates. Radiation prot ection procedures control access to restricted areas and radiation areas to meet the requirements of 10 CFR 20. Personnel who work in
or frequent any portion of a restricted area are trained in accordance with the requirements of 10 CFR 19.
[12.5-10]
12.5.3.9 Access to High Radiation Areas
Areas in which radiation levels meet or exceed the definition of High Radiation Areas per Station Technical Specifications are posted and access controlled per Station Technical Specifications.
[12.5-11] 12.5.3.10 In-Plant Radiation Monitoring This program provides the controls which en sures the capability to accurately determine the airborne iodine concentration in vital ar eas under accident conditions. This program includes the training of personnel, procedur es for monitoring, and provisions for the maintenance of sampling and analysis equipment.
[12.5-12]