Federal emergency management agency fema rep-2, rev. 2 / June 1990



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1.1Scope of This Report


The measurement systems that are recommended in this report are state-of-the-art instrumentation and techniques for monitoring exposures from radioactive releases from light water nuclear power reactors. Comments from other government agency reviews of this report have been taken into consideration in developing this guidance. The basis for omission from the report of other systems and techniques that would be of equal quality for this type monitoring is that the FRPCC Subcommittee was constrained by the need to keep the report content within reasonable bounds in order to promote workable guidance.

The FRPCC Subcommittee Phase 2 and Phase 3 guidance address the offsite Emergency Radiation Measurement Systems needed to implement protective actions for the milk and the water and non-dairy food exposure pathways, respectively. A future Phase 4 document will address guidance on recovery and reentry.

Two offsite emergency radiation detection and measurement systems are defined for use in collecting data to be used in determining protective actions against direct exposure to the plume or airborne release from a nuclear accident. One system is to provide offsite measurement to confirm and supplement the data provided by the facility in its notification of a nuclear incident to the State and/or local EOC. This system is the Plume Exposure Rate Verification System, which is discussed in Section 4. The information provided to the EOC by the facility's nuclear incident notification process is described in Section 3. The second system is for measuring the accrued exposure from the plume to emergency workers. This Emergency Worker Exposure Monitoring System is discussed in Section 5.

These offsite emergency radiation measurement systems operated by State and/or local organizations together with the emergency plans of the nuclear facility and Federal agencies are designed for implementing offsite protective actions for accidents requiring such action, as conceived in the guidance provided by NUREG-0396.xii It is believed that these radiation measurement systems and emergency plans will also be adequate for those less severe incidents that may require offsite protective actions as well as design basis accidents.


1.2Conceptual Guidance


Protective actions, as used in this document, are those actions taken to avoid or reduce the projected dose from a nuclear accident when the benefits derived from such actions are sufficient to offset any undesirable features, e.g., risk of traveling in adverse weather, unreasonable cost or hardship on participants, of the protective actions. A Protection Action Guide (PAG) is the projected dose, from exposure to airborne radioactive materials, to individuals in the population which warrants taking protective action. Projected dose is defined as that dose that would be received by the population if no protective action were taken.

For PAGs, the projected dose does not include dose that may have been received prior to the time of estimating the projected dose.xiii A PAG does not imply an acceptable dose. (See Section 4.0 for a discussion of PAGs).

Protective Action Guides and guidance on the implementation of protective actions are being developed cooperatively by various Federal agenciesxiv for use by State planners to develop State radiological emergency preparedness plans. The PAGs are projected whole body or thyroid dose limit ranges which require protective actions. Since the PAGs are related only to whole body or thyroid doses, skin dose limitation will not be addressed in this document.

The FRPCC efforts in their development of radiological emergency preparedness guidance have been directed first towards light water nuclear power reactor accidents. If additional guidance on other types of radiological emergencies becomes necessary, it will become the subject of a separate guidance document.

The guidance reports on offsite emergency radiation measurement systems to be written by the FRPCC Subcommittee will usually follow the issuance of guidance on the implementation of protective actions. However, the recommendations of the original FEMA REP-2 report on Phase 1 of the Airborne Release were developed concurrently with the Federal interagency effort on development of PAGs and guidance on the implementation of protective actions.xv

Insofar as possible, the FRPCC Subcommittee strives to define measurement systems that use instrumentation readily available to the States and/or local organizations at little cost, and which are useful in other normal and emergency radiation measurements. In this respect, it is important that each State or local organization review the adequacy and availability of its equipment for emergency monitoring. This is not intended to imply that more expensive and/or sophisticated equipment can not be used, if available.

Conceivably, the aggregation of the available instrument resources recommended for individual emergency radiation measurement systems may not be the most cost-effective mix of instrument resources for the emergency radiation measurement systems as a whole, i.e., the total system.

The generic instruments and equipment requirements and other resources recommended by the Subcommittee for use in offsite emergency radiation measurement systems are as follows:



  1. Plume Exposure Pathway.

  • Direct exposure measurements - calibrated low-range (0-50 mR/h) and high-range (0-100 R/h) survey instruments. GM or sealed ion chamber type instruments with moveable beta shields on the low-range instruments to provide open and closed window measurement capabilities.

  • Radioiodine measurements - calibrated air pumps with appropriate particulate filters, cartridge type adsorber filters (such as silver zeolite) for selective collection of radioiodine in the presence of noble gases. A thin window (1.5-2.0 mg/cm2) pancake type GM detector or a 1" x 1" or 2" x 2" NaI(Tl) detector with either a single channel or dual channel analyzer may be used to measure the radioiodine activity on the adsorber cartridge.

  • Personal dosimetry - calibrated direct reading dosimeters and permanent record dosimeters (see emergency worker exposure instrumentation).

  • Dose projection capability - a hand-held calculator is adequate for making thyroid dose rate projections in the field based on the field measurement data. However, a more sophisticated computer program may be desirable at the Emergency Operations Center (EOC). This program should have the capability of making dose projections based on release measurements obtained from the plant operators as well as the capability of accepting field measurement data as input for fine tuning the dose projections.

  • Communications – direct and, ideally, continuous communications ability is necessary between the field monitoring teams and the EOC or Forward Command Post. This is best accomplished by means of radio with backup systems, such as additional radios or public telephones, available in the event of equipment failure.

  1. Ingestion Pathway (see References 11 and 12).

  2. Other Resources.

  • Utility - the utility offsite field monitoring teams will be able to mobilize and respond to a potential offsite release of radioactivity more quickly than the State or local field monitoring teams. The offsite measurements made by the utility field monitoring teams should be used for early delineation of the plume boundaries and verification of initial dose projections. The combined measurement data from the utility and State or local monitoring teams will provide a better overall characterization of the plume. The utility may also be a resource for additional monitoring team personnel and monitoring instruments or equipment.

  • Federal Agencies - several Federal agencies have the capability of providing personnel and equipment resources for additional field monitoring and sample collection teams and radiological laboratory facilities (both mobile and fixed facilities). In addition, the Department of Energy (DOE) has the Aerial Measuring System program which should be used following releases of radioiodine or particulate radioactivity to determine the areal extent of ground surface radiological contamination caused by the deposition of radioactivity from the plume. During the course of an airborne release of radioactivity, dose projections, and predictions of ingestion pathway concentrations from DOE's Atmospheric Release Advisory Capability, an atmospheric modeling system based at Lawrence Livermore National Laboratory, may be available to State and local authorities.


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