RSICC CODE PACKAGE CCC-506



1. NAME AND TITLE

GALE86: Calculation of Routine Radioactive Releases in Gaseous and Liquid Effluents from Boiling Water and Pressurized Water Reactors.



2. CONTRIBUTOR

U.S. Nuclear Regulatory Commission, Washington, D.C.



3. CODING LANGUAGE AND COMPUTER

Fortran IV; CDC (C00506C000001).



4. NATURE OF PROBLEM SOLVED

GALE is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from boiling water reactors (BWRs) and pressurized water reactors (PWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment. The CCC-506/GALE86 code package was developed as a newer tool based on more recent information published in NUREG-017, Rev. 1. RSICC retains the CCC-335/GALE package for use with plants licensed with the earlier technology.



5. METHOD OF SOLUTION

GALE calculates expected releases based on 1) standardized coolant activities derived from ANS Standards 18.1 Working Group recommendations, 2) release and transport mechanisms that result in the appearance of radioactive material in liquid and gaseous waste streams, 3) plant-specific design features used to reduce the quantities of radioactive materials ultimately released to the environs, and 4) information received on the operation of nuclear power plants.



6. RESTRICTIONS OR LIMITATIONS

The liquid release portion of GALE uses subroutines taken from the ORIGEN program (CCC-217) to calculate radionuclide buildup and decay during collection, processing, and storage of liquid radwaste. Memory requirements for this part of the program are determined by the large nuclear data base accessed by these subroutines.



7. TYPICAL RUNNING TIME

None available.



8. COMPUTER HARDWARE REQUIREMENTS

GALE is operable on the CDC 7600.



9. COMPUTER SOFTWARE REQUIREMENTS

A Fortran IV compiler is required. GALE uses standard I/O with 3 additional data sets for the Liquid Effluent Code. GALE was operable under SCOPE 2.1 (CDC7600) and NOS 2.4 (CDC CYBER170). The codes were tested at the NESC at Argonne National Lab in December 1986 on a CDC CYBER170/875. They were neither tested nor modified when they were transferred to RSICC in April 2002. The only significant change between RSICC release C00506C000000 and C00506C000001 is the addition of sample problem output.



10. REFERENCES

P. A. Bell, Changes/Errata for GALE BWR (NUREG-016, Rev. 1) and GALE PWR (NUREG-017, Rev. 1), Memo 1986.

F. P. Cardile and R. R. Bellamy, Eds., "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR-GALE Code)," NUREG-0016, Rev. 1 (January 1979).

T. Chandrasekaran, J. Y. Lee, and C. A. Willis, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code)," NUREG-0017, Rev. 1 (April 1985).



11. CONTENTS OF CODE PACKAGE

Included are the referenced documents and one DOS diskette which contains the source codes, data library and sample problem input and output.



12. DATE OF ABSTRACT

January 1982; updated March 1983, July 1986, January 1987, April 2002.



KEYWORDS: RADIOLOGICAL SAFETY; NUCLIDE TRANSPORT; ENVIRONMENTAL DOSE; FISSION PRODUCT INVENTORY; RADIOACTIVITY RELEASE