Nuclear Fuel Cycle Facility Accident Analysis Handbook.

562 Pages·2011·39.6 MB·English

NUREG-1320
Nuclear Fuel Cycle Facility
Accident Analysis Handbook
U.S. Nuclear Regulatory
Commission
Office of Nuclear Material Safety and Safeguards
J.E. Ayer, A.T. Clark, P. Loysen, M.Y. Ballinger,
J. Mishima, P.C. Owczarski, W.S. Gregory, B.D. Nichols

NUREG-1320
Nuclear Fuel Cycle Facility
Accident Analysis Handbook
Manuscript Completed: April 1988
Date Published: May 1988
J.E. Ayer, A.T. Clark, P. Loysen, M.Y. Ballinger*,
J. Mishima*, P.C. Owczarski*, W.S. Gregory**, B.D. Nichols**
*Pacific Northwest Laboratory
Los Alamos National Laboratory
Division of Industrial and Medical Nuclear Safety
Office of Nuclear Material Safety and Safeguards
U.S. Nuclear Regulatory Commission
Washington, DC 20555
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EXECUTIVE SUMMARY
This Accident Analysis Handbook (AAH) was prepared jointly by Pacific
Northwest Laboratory, Los Alamos National Laboratory, and the United States
Nuclear Regulatory Commission (NRC). The NRC Office of Nuclear Material
Safety and Safeguards, Division of Industrial and Medical Nuclear Safety,
sponsored this work in a program to develop improved methods of evaluating the
consequences of major accidents in fuel cycle facilities. This handbook will
be used by NRC licensing staff and applicants for an NRC fuel cycle facility
license or license amendment.
The AAH covers four generic facilities: fuel manufacturing, fuel repro
cessing, waste storage/solidification, and spent fuel storage; and six accident
types: fire, explosion, tornado, criticality, spill, and equipment failure.
These are the accident types considered to make major contributions to the
radiological risk from accidents in nuclear fuel cycle facility operations.
The AAH will enable the user to calculate source term releases from
accident scenarios manually or by computer. A major feature of the AAH is
development of accident sample problems using information from Chapters 2 and 3
to provide input to source term analysis methods in Chapter 4 and transport
computer codes in Chapter 5. Sample problems and illustrative examples for
different accident types are included in the AAH.
Chapter 2 covers the facility description. Section 2.7 introduces the
sample problem. Here the facility descriptors required for input are itemized.
Processes within the facility are described in Chapter 3. Section 3.5 is the
continuing sample problem - here process parameters required for accident
computer codes or hand calculation are detailed. They are added to the input
from Section 2.7.
Chapter 4 develops the scenario and radioactive source terms for the
continuing sample problems. Input from Sections 2.7 and 3.5 lead to the source
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term developed in this chapter. Both hand and computer calculation of releases
are illustrated. (
Chapter 5 uses the source term information developed in Chapter 4 to
calculate the transport of mass, energy, and material throughout the facility.
The accident consequence assessment is determined by computer codes, which
calculate the radioactive release to the environment and the spread of radio
activity throughout the facility.
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CONTENTS
Page
EXECUTIVE SUMMARY i i i
1.0 INTRODUCTION 1.1
1.1 PURPOSE 1.1
1.2 SCOPE 1.2
1. 2.1 Facilities ........................................... . 1.2
1. 2. 2 Ace i dents ............................................ . 1.2
1.2.3 Limitations .......................................... . 1.2
1. 3 USERS 1.3
2.0 FACILITY/ACCIDENT DESCRIPTORS..................................... 2.1
2.1 GENERAL CONSTRUCTION AND PROCESS FEATURES . .. .. ... .. .. . . . .. . .. 2.1
2.1.1 Description of the Accident Compartment............... 2.2
2.1.2 Description of Vessels in the Accident Compartment . . . . 2.3
2.1.3 Description of the Ventilation System................. 2.5
2.1.4 Description of Alternate Flow Paths . . . . . . . . . . . . . . . . . . . 2.8,
2.2 SUMMARY OF FACILITY PARAMETERS............................... 2.9
2.3 FUEL MANUFACTURING FACILITY DESCRIPTION...................... 2.9
2.3.1 Mixed Oxide Facilities................................ 2.9
2.3.2 Uranium Oxide Facilities ... .. ..... .. ... .. .... ... ... .. . 2.11
2.4 REPROCESSING FACILITY DESCRIPTION............................ 2.12
2.5 WASTE STORAGE/SOLIDIFICATION FACILITY DESCRIPTION............ 2.13
2.6 SPENT FUEL STORAGE FACILITY DESCRIPTION...................... 2.14
2. 7 SAMPLE PROBLEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.15
2.7.1 Primary Sample Problems . .. . .. .. .. . .. .. . .... .. . .. .. .. .. 2.16
2.7.2 Secondary Sample Problems . ... .. ....... ....... ..... .. .. 2.21
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CONTENTS (Continued)
Page
2. 8 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2. 23
3. 0 PROCESS ACCIDENT DESCRIPTORS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.1
3.1 FUEL MANUFACTURING .. .. . . . . . . . .. . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . 3. 2
3.1.1 Process Description 3.2
3.1. 2 Potential Accidents 3.6
3.1.3 Inventories and Process Descriptors . . .. . . . . . .. ... . . . .. 3.6
3.1.4 Summary of Fuel Manufacturing Process Parameters .. .. .. 3.16
3.2 FUEL REPROCESSING 3.16
3.2.1 Process Description 3.19
3.2.2 Potential Accidents 3.21
3.2.3 Inventories and Process Descriptors................... 3.21
3.2.4 Summary of Fuel Reprocessing Process Parameters....... 3.34
3.3 WASTE STORAGE AND SOLIDIFICATION............................. 3.34
3.3.1 Process Description 3.34
3.3.2 Potential Accidents 3.38
3.3.3 Inventories and Process Descriptors . .. . .. . . . .... .. .. .. 3.38
3.3.4 Summary of Waste Storage/Solidification Process
Parameters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 44
3. 4 SPENT FUEL STORAGE .. . . . .. . . .. .. .. . . . .. . . . . . . . . . . .. . . . .. .. . . . . 3.44
3.4.1 Process Description 3.44
3.4.2 Potential Accidents 3.47
3.4.3 Inventories and Process Descriptors .. . . ... .. ..... ..... 3.47
3.4.4 Summary of Spent Fuel Storage Process Parameters...... 3.50
3.5 SAMPLE PROBLEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.51
3.5.1 Primary Sample Problems............................... 3.51
3. 5. 2 Secondary Sample Problems 3.56
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CONTENTS (Continued)
Page
3. 6 REFERENCES .................................................. . 3.58
4.0 SCENARIO AND SOURCE TERM DEFINITION .............................. . 4.1
4.1 GENERIC DESCRIPTION OF SOURCE TERMS ......................... . 4.1
4.1.1 Scenario Cons ide rations .............................. . 4.2
4.1. 2 Energy Cons ide rations ................................ . 4.2
4.1 3 Airborne Materials ................................... . 4.3
4.2 FIRES 4.5
4.2.1 Scenario Cons ide rations .............................. . 4.6
4.2.2 Calculational Techniques Illustrated ................. . 4.8
4.2.3 Samp 1e Prob 1e ms ...................................... . 4.23
4. 3 EXPLOSIONS .................................................. . 4.41
4.3.1 Scenario Considerations .............................. . 4.42
4.3.2 Calculational Techniques Illustrated ................. . 4.45
4.3.3 Samp 1e Prob 1e ms ...................................... . 4.61
4.4 SPILLS 4.68
4.4.1 Scenario Considerations .............................. . 4.69
4.4.2 Calculational Techniques Illustrated ................. . 4.70
4.4.3 Samp 1e Prob 1e ms ...................................... . 4.76
4. 5 TORNADOES ................................................... . 4.81
4.5.1 Scenario Considerations . . ...... .... .. .. . . . .. . . ... .. .. . 4.82
4.5.2 Calculational Techniques Illustrated.................. 4.83
4.5.3 Sample Problems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.96
4. 6 NUCLEAR CRITICALITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.103
4.6.1 Scenario Considerations............................... 4.104
4.6.2 Calculational Techniques Illustrated.................. 4.105
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CONTENTS (Continued)
Page
4.6.3 Sample Problems ...................................... . 4.113
4. 7 EQUIPMENT FAILURES .......................................... . 4.118
4.7.1 Scenario Considerations . .. ... .. .. . . . . . . . . . . . . .. . .. .. .. 4.119
4.7.2 Calculational Techniques Illustrated.................. 4.119
4. 8 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4.119
5.0 FUEL CYCLE FACILITIES ACCIDENT CONSEQUENCE ASSESSMENT . . . . . . . ... .. . 5.1
5.1 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.1
5.2 ANALYSIS STRATEGIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.2
5.2.1 Single-Compartment/Single-Duct Analysis . . .. . . . .. . . .. . . 5.2
5.2.2 General Analysis...................................... 5.3
5. 3 ANALYSIS CODES .. .. .. .. .. .. .. .. .. .. .. . .. . .. . .. .. .. .. . .. . .. .. .. 5. 5
5.4 GENERAL ANALYSIS PROCEDURE . . .. .. .. .. . .. .. . .. . . . . . .. .. . . .. . . . . 5.7
5.4.1 Required Chapter 2 and 3 Information.................. 5.7
5.4.2 Coarse Network Model Development...................... 5.8
5.4.3 Accident Simulation................................... 5.10
5.5 ILLUSTRATIVE PROBLEM SYSTEM DESCRIPTION...................... 5.11
5.6 ILLUSTRATIVE EXAMPLES .. .. .. .. . .. .. .. . .. .. .. .. .. .. .. . .. . .. . .. . 5.12
5.6.1 Fire Sample Problem Consequence Assessment............ 5.13
5.6.2 Explosion Sample Problem Consequence Assessment....... 5.26
5.6.3 Tornado Sample Problem................................ 5.32
5. 7 GENERAL GUIDANCE INFORMATION................................. 5.34
5. 7.1 HEPA Filter Laminar and Turbulent Coefficients......... 5.35
5. 7.2 Filter Plugging Coefficients .. ....... .. . .. .. . .. .. .. .. . 5.35
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