GB/T 17680.11-2008 (GB/T17680.11-2008, GBT 17680.11-2008, GBT17680.11-2008) & related versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | See Detail | Status | Similar PDF |
| GB/T 17680.11-2008 | English | 90 |
Add to Cart
|
0-9 seconds. Auto delivery.
|
Criteria for emergency planning and preparedness for nuclear power plants -- Part 11: Criteria for the conduct of offsite radiological assessment for emergency response
|
GB/T 17680.11-2008
| Valid |
GBT 17680.11-2008
|
Buy with any currencies (Euro, JPY, KRW...): GB/T 17680.11-2008 Preview this PDF: GB/T 17680.11-2008
GB/T 17680.11-2008: PDF in English (GBT 17680.11-2008)
GB/T 17680.11-2008
GB
NATIONAL STANDARD OF THE
PEOPLE’S REPUBLIC OF CHINA
ICS 27.120.20
F 77
Criteria for emergency planning and
preparedness for nuclear power plants - Part 11.
Criteria for the conduct of offsite radiological
assessment for emergency response
ISSUED ON. MARCH 24, 2008
IMPLEMENTED ON. NOVEMBER 01, 2008
Issued by.
General Administration of Quality Supervision, Inspection
and Quarantine of the People’s Republic of China;
Standardization Administration of the People’s Republic of
China.
Table of Contents
Foreword ... 3
1 Scope ... 4
2 Normative references ... 4
3 Terms and definitions ... 4
4 Dose Assessment ... 6
5 Description of Release Characteristic ... 7
6 Dose Calculation Mode ... 9
7 Application of dose assessment in decision-making of protective actions .. 13
8 Coordination with offsite emergency organization ... 14
9 Dose assessment group and personnel training ... 15
Foreword
GB/T 17680 Criteria for emergency planning and preparedness for nuclear power plants is
divided into 12 parts.
— Part 1. The dividing of emergency planning zone;
— Part 2. Offsite emergency functions and organizations;
— Part 3. Functional and physical characteristics of the offsite emergency facilities;
— Part 4. The offsite emergency planning and implementing procedures;
— Part 5. Maintenance of offsite emergency response capabilities;
— Part 6. On-site emergency response functions and organizations;
— Part 7. Function and physical characteristics of on-site emergency facilities;
— Part 8. On-site emergency planning and implementing procedures;
— Part 9. Maintenance of on-site emergency response capacity;
— Part 10. Criteria for emergency radiological field monitoring, sampling and analysis
conducted by nuclear power plant operating organizations;
— Part 11. Criteria for the conduct of offsite radiological assessment for emergency
response;
— Part 12. Planning, development, conduct and evaluation of nuclear emergency drills
and exercises.
This Part is part 11 of GB/T 17680. It corresponds to ANSI/ANS 3.8.6.1995 “Criteria for the
Conduct of Offsite Radiological Assessment for Emergency Response for Nuclear Power
Plants”. This Part is not equivalent to ANSI/ANS 3.8.6.1995.
This Part was proposed by China National Nuclear Corporation.
This Part shall be under the jurisdiction of National Nuclear Energy Standardization
Technology Committee.
Drafting organization of this Part. Institute of Nuclear Energy Technology Design of
Tsinghua University.
Main drafter of this Part. Liu Yuanzhong.
Criteria for Emergency Planning and Preparedness for Nuclear Power
Plants – Part 11. Criteria for the Conduct of Offsite Radiological
Assessment for Emergency Response
1 Scope
This Part of GB/T 17680 specifies the criteria for radiation dose assessment (abbreviated
as dose assessment) adopted when nuclear power plant has or may have the accident of
releasing radioactive substance to environment.
This Part applies to the assessment for offsite radiation dose caused by nuclear power
plant accident, including anticipated assessment and follow-up assessment.
2 Normative references
The articles contained in the following documents have become part of this Part of GB/T
17680 when they are quoted herein. For the dated documents so quoted, all the
modifications (excluding corrigendum) or revisions made thereafter shall not be applicable
to this Part. For the undated documents so quoted, the latest editions shall be applicable
to this Part.
GB/T 4960.5 Glossary of terms. Nuclear science and technology - Radiation
protection and safety of radiation sources
GB/T 17680.9 Criteria for emergency planning and preparedness for nuclear power
plants - Maintenance of on-site emergency response capacity
GB 18871 Basic standards for protection against ionizing radiation and for the safety
of radiation sources
3 Terms and definitions
Those established in GB/T 4960.5 AND the following terms and definitions apply to this
Part of GB/T 17680.
3.1 Emergency
A state that some actions exceeding normal working procedure shall be adopted
immediately to avoid the accident or alleviate accident consequence. Meanwhile, it also
refers to immediately adopting actions that is beyond normal working procedure.
4.1.3 For accident with slow progress, a series of emergency PARs proposed by the dose
assessment system can be utilized, so as to provide a method for the initial assessment
for nuclear accident emergency of nuclear power plant and the follow-up dose
assessment throughout the whole emergency process.
4.2 Requirement for emergency response organization
4.2.1 After the accident happened, the emergency response organization of operating unit
of nuclear power plant shall rapidly conduct offsite radiation dose assessment for
radiological release of this accident, so as to assess the dose possibly received by offsite
personnel. The radiation exposure can be from the direct external exposure caused by
radioactive plume and superficial deposit or internal exposure caused by intaking
(inhalation or ingestion) radioactive substance.
4.2.2 The possibly received radiation exposure is very important in early stage
assessment. The local and the emergency response unit of operating organization of
nuclear power plant shall utilize the result of dose assessment to make decisions on
protective action for the public. The emergency unit of operating organization of nuclear
power plant can also utilize these results to make decisions on PAR for onsite workers.
4.3 Contents involved in dose assessment
To better conduct the dose assessment, the content involved in assessment shall include
the following aspects.
a) State of power plant and corresponding symptoms;
b) Type of accident;
c) Radioactive release source term in accident (airborne release source term and liquid
release source term);
d) Current and anticipated meteorological condition;
e) Hydrologic data of riverside or coastal plant;
f) Environmental monitoring data.
5 Description of Release Characteristic
5.1 Overview
5.1.1 One of important parameters that shall be input in any dose assessment is
radioactive release source term. The accident radiological release can be divided into
airborne radiological release and liquid state radiological release.
5.1.2 The release source term shall be quantized in order to conduct dose assessment
6.2.8.1 The output of the mode shall be formatted in order to promptly determine the state
of emergency, make protective action decisions, and implement other emergency
response capabilities.
6.2.8.2 The output data shall give out the assessment time, date and characteristic
symbol, and give a list on the calculated input parameters and the selection of the control
variable to serve as the basis for the calculation results.
6.2.8.3 The output file shall be saved all the calculation results useful for the emergency
grading and protective actions decision.
6.2.9 Description to the meteorological data and basic data, and use restrictions in using
the dose assessment mode shall be given out in the form of documents.
6.2.10 The implementation steps and methods of how to use these modes during the
emergency response period shall be provided.
6.2.11 The mode that is used by the government agencies and the results obtained from
implementing these modes may be different from the mode that is used by the nuclear
power plant and results. Through comparing these modes and the calculated results and
finding the differences between them, analyze the causes of these differences and explain
the reasonability of these difference, organize these into a corresponding file in order to
be able to coordinate these key issues with differences during the emergency period.
6.3 Atmospheric transmission and diffusion assessment mode
6.3.1 The atmospheric transmission and diffusion assessment mode shall have the ability
to calculate the current situation of radioactive dispersion after the release of the airborne
radioactive material according to the current weather data, and estimate the prospective
situation of dispersion according to the prospective weather data.
6.3.2 The application scope of the release height (such as ground release, high level
release or mixing release) and release characteristics (such as gas, particle, chemical
morphology and reactions, heat release, air outlet speed, etc.) of the mode to the accident
source term of the nuclear power plant shall be explained.
6.3.3 The application scope of the mode to the meteorological characteristics,
topographical features of the plant site and the construction (structures) of the power plant,
as well as the characteristics that may affect the smoke plume transmission shall be
explained and make the necessary amendments to these effects.
6.3.4 The mode shall have the ability to provide estimation to the size, position and
trajectory of the representative smoke plume.
6.3.5 The mode shall give out the boundaries of field area, boundaries of plume
emergency planning zone, dose r...
......
| Standard ID | GB/T 17680.11-2008 (GB/T17680.11-2008) | | Description (Translated English) | Criteria for emergency planning and preparedness for nuclear power plants - Part 11: Criteria for the conduct of offsite radiological assessment for emergency response | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F77 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 11,151 | | Date of Issue | 2008-03-24 | | Date of Implementation | 2008-11-01 | | Quoted Standard | Announcement of Newly Approved National Standards No. 5, 2008 (No. 118 overall) | | Adopted Standard | ANSIANS 3.8.6-1995, NEQ | | Drafting Organization | Institute of Nuclear Energy Technology, Tsinghua University | | Administrative Organization | National Standardization Technical Committee of Nuclear Energy | | Regulation (derived from) | National Standard Approval Release Bulletin No. 5 of 2008 (No. 118) | | Proposing organization | China National Nuclear Corporation | | Issuing agency(ies) | Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China; Standardization Administration of China | | Summary | This standard specifies the nuclear power plant occurred or may occur in the release of radioactive material to the environment when the incident radiation dose used in evaluation (referred Dose Assessment) guidelines. This section applies to the nuclear power plant accident caused by the evaluation of off-site radiation doses, including the expected evaluation and follow-up evaluation. |
|