ML19221B098
| ML19221B098 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-11.1, NUREG-75-87, NUREG-75-87 11.1, SRP-11.01, SRP-SRP-11.01, NUDOCS 7907120421 | |
| Download: ML19221B098 (4) | |
Text
p Rio NUREG 75/087
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U.S. NUCLEAR REGULATORY COMMISSION
'g 3rci STANDARD REVIEVil PLAN i
OFFICE OF NUCLEAR REACTOR REGULATION SECTION 11.1 SCURCE TERMS REVIEW RESPONSIBILITIES Primary - Effluent Treatment Systems Branch (ETSB)
Secondary - None 1.
AREAS OF REVIEW ETSB reviews the sources of radioactivity that are input to the radioactive waste manage-ment systems employed for treatment of liquid, gaseous and salid wastes.
1.
Review of radioactive source terms includes consideration of parameters used to deternine the concentration of each isotcpe in the reactcr coolant; fraction of fission product activity released to the reactor coolant; concentrations of all nonfission product radioactive isotopes in the reactor coolant; leakage rates and associated fluid activity for all potentially radioactive water and steam systems; and potential sources of r adioactive materials in ef fluents that are nut considered in the applicant's safety analysis report (SAR) Section 11.2, " Liquid Waste Management Systems," and SAR Section 11.3, " Gaseous Waste Management Systems." The fol'.owing release points are considered in the evaluation of effluent releases:
a.
Boiling water reactor (WR) gaseous wastes (noble gases, radiciodine, and par-ticulatescarbon-14andtritium),consistingofoffgasesfromthemaincondensed evacuation and turbine ] land sealing systems, steam and liquid leakage to l
containment, adwaste, turbine, fuel handling and auxiliary buildings, and ventilation ;ystem exhausts from buildings having the potential for containing [
radioactive materials.
b.
BWR liquid wastes, consisting of leakage to equiprent and floor drains from buildings housing equipmer.t and components that may contain radioactive fluids; contaminated liquids produced by plant operations, such as deminer alize; regener-ants and resin sluice water, filter backwashes, ultrasonic resin cleaning rinies, decontamination solutions, and laborato,: samples and rinses; and detergent wastes.
c.
Pressurized water reactor (PWR) gneces wastes (noble gases, radiciodine, and particulates carbon-14 and tritium), consisting of offgases from the steam generator blowdown flash tank; offgases from the main candenser evacuation j
system; leakage to containment, fuel handling auxilirry, and turbine buildings; n+ 1a cata< etrir w from nn nri-vv ccolant e rina nnrmal nporation and at l
USNRC STANDARD REVIEW PLAN
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shutdown; and cover and vent gases from tanks and equipment containing radio-active material.
d.
PWR liquid wastes, ccnsisting of prirrary coola: t processed to control boron concentration (shim bleed); leakage collected in equipment and floor drains from buildings housing equipment and corrponents that may contain radioactive finids; steam generator bicwdown; condensate demineralizer regenerant sulutions; con-taminated liquids fron anticipated plant operations such as resin sluices, filter backwashes, decontamination solutions, and sample sta'. ion drains; and detergent wastes.
2.
The calculated releases of radioactive materials in liquid and gaseous effluents will be used in SRP Sections 11.2 and 11.3 to evaluate the liquid and gaseous waste systems.
II.
ACCEPTANCE CRITERIA ETSB will accept the source terms used as tne design basis for expected releases if the followinn criteria are met:
1.
The parameters used to calculate primary and secondary (PWR) coolant concentrations are consistent with those given in NUREG-0017, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors," and NUREG-0016, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Eff!uer.ts from Boiling Water Reactors."
2.
All normil and potential release points of radioactive effluent delineated in a b xction 1 are conciderea.
3.
For each scurce of liquid and gaseoJs Waste Considered in subsection II.l.b, the vosames and radioactivity levels given for normal operation and anticipated eperational etcurrences are consistent with those given in NUREG-0016 and NUREG-0017. '
I 4.
Reduction factorc for special design features used to reduce leakage, such as clean sam :.y steam for valve stems and turbine glands, are consistent with those given in NUREC C0lb and NUREG-0017.
5.
Decontaminatien factors for inplant control measures used to reduce releases to the environment, such as iodine removal systems and high efficiency particulate air (HEPA) filters for building ventilation exhaust systems, are consiscent with those given in NUREG-0016 and NURFG-0017.
An acceptable method for satisfying the criteria of subsection II.1 consists of using the gaseous and liquid ef fluent (GALE) Coreputer Code and the scurce term parameters given in NUREG-0016 and NUR[b-0017. A complete Fortran listing of tha PWR and BWR GALE computer l
code is given in these repcrts. The apolicant shocid provide the information listed in Appendix A (BWRs) and Appendix B (PWRs) to Regalatory Guide 1.112 (Ref. 5).
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If the applicant's calculational technique or any source term parameter differs from that given in NUREG-0016 and NUREG-0017, they should be described in detail and the bases for l the methods and parameters used should be provided.
III. REVIEW PROCEDURES The reviewer will select end emphasize material from this revieu plan, as may be appro-priate for a particular case.
1.
In the review of the mathematical models and parameters given in the SAR to calculate primary coolant concentrations, and of the leakage rates to the radioactive waste management systems, ETSB compares parameters and calculations given in the SAR with the models and parameters given in NUREG-0016 and NUREG-0017. If the SAR includes models or parameters to estimate primary coolant concentrations and leakage rates that differ from these reports, the parameters and calculations used need to be f
substantiatec. The preferred method of substantiation is by presentation of operat-ing data from similar reactors.
2.
ETSB performs an independent calculation of the primary and secondary (PWR) coolant concentrations and of the release rates of radioactive materials using the GALE Computer Code, and the " Principal Parameters for Source Term Calculations" given in NUREG-0016 and 0017, and the informction supplied by the applicant in accordance with Appendices A and B of Regulatory Guide 1.112.
3.
In the calculation, ETSB will use the applicant's values as given in the SAR for the following parameters: design core thermal power level, steam flow rate, coolant mass, and coolant purification rates.
4.
ETSB will use the primary coolant cancentrations and leakage rates calculated above as inputs for evaluation of the liquid waste system, under SRP Section 11.2, and the gaseous waste systems, under SRP Se: tion 11.3, to determine if the radioactive waste management s" stems meet the dose desigl objectives of Appendix I to 10 CFR Part 50.
5.
The ETSS source term calculations are used for both the review of the SAR and for the staf f's Environmental Impact Stater ant.
I '/. EVALUATION FINDINGS The tTSB summary statement on the accept uility of source terns used as design parameters for the waste management systens will be made under SRP Section 11.2, " Liquid Waste Systems," and 11.3, " Gaseous Waste Systems. '
V.
REFERENCES 1.
10 CFR Part 20 " Standards for Protection egainst Radiation."
2.
10 CFR Part 50, Apper. dix I, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As tow As Practicable' for Radioactive Paterial in Light-Water-Cooled Nuclear Power Paactor Ef fluents," May 5,1975. V)
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11.1-3 Rev. I
3.
NUREG-0017, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactars (PWRs)."
4.
NUREG-0016, " Calculation of Releases of Ralioactive Paterials in Gaseous and Liquid Effluents from Boiling Water Reactars (3'nRs).
5.
Regulatory Guide 1.112, " Calculation of Releases of Radioactive Mater als in Gaseous and Liquid Effluent from Light-Water-Cooled Power Reactors."
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