NRC Generic Letter 79-06, Contents of the Offsite Dose Calculation Manual

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GL79006

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

FEB 14 1979

Docket No. 50-311

Mr. R. L. Mittl, General Manager Licensing and Environment Engineering and Construction Department Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101

Dear Mr. Mittl:

SUBJECT: CONTENTS OF THE OFFSITE DOSE CALCULATION MANUAL (Salem Nuclear Generating Station, Unit 2)

The Radiological Effluent Technical Specifications for PWR and BWR facilities issued in November 1978, require you to provide an Offsite Dose Calculation Manual (ODCM) with your proposed Technical Specifi-

cations implementing 10 CFR 50.36a and other Federal Regulations. The enclosure to this letter describes the staff's recommendations for the general contents of the ODCM. The format for the ODCM is left to your discretion.

Sincerely,

Olan D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management

Enclosure:

General Contents of the ODCM

cc w/enclosure:

See next pagecc: Richard Fryling, Jr., Esq. Assistant General Counsel Public Service Electric & Gas Company 80 Park Place Newark, New Jersey 07100

Mark Wetterhahn, Esq. Conner, Moore & Cober 1747 Pennsylvania Avenue, N.W. Suite 1050 Washington, D.C. 20006

Mr. Leif J. Norrholm U. S. Nuclear Regulatory Commission Region I Drawer I Hancocks Bridge, New Jersey 08038

.

GENERAL CONTENTS OF THE ODCM*

Section 1 - Set Points

Provide the equations and methodology to be used at the station or unit for each alarm and trip set point on each effluent release point according to the Specifications 3.3.3.8 and 3.3.3.9. Provide the alarm and control location, the monitor description, location, vower source, scale, range and identification number, and the effluent isolation control device, its location, power source and identification number. If the set point value is variable, provide the equation to be used to predetermine the set point value that will assure that the Specification is met at each release point and the value to be used when releases are not in progress. If dilution or dispersion is used, describe the on-site equipment and measurement method used during release, the site related parameters and the set points used to assure that the Specification is met at each release point, including any administrative controls applicable at the station or unit. The fixed and predetermined set points should consider the radioactive effluent to have a radionuclide distribution represented by normal and anticipated operational occurrences. Other features, such as surveillance requirements and the calibration method, should be addressed.

Section 2 - Liquid Effluent Concentration

Provide the equations and methodology to be used at the station or unit for each liquid release point according to the Specification 3.11.1.1. For

• The format or the ODCM is left up to the licensee and may be simplified by tables and grid printout. Each page should be numbered and indicate the facility approval and effective date.

.continuous and/or batch releases, the assumptions used for manual and automatic termination of releases should be provided. For batch releases, the calculational methods, equations and assumptions used, together with the pre-release and post-release analyses should be provided. Other features, such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.

Section 3 - Gaseous Effluent Dose Rate

Provide the equations and methodology to be used at the station or unit for each gaseous release point according to Specification 3.11.2.1. Consider the various pathways, release point elevations, site related parameters and radionuclide contribution to the dose impact limitation. Provide the equations and assumptions used, stipulating the pathway, receptor location and receptor age. Provide the dose factors to be used for the identified radionuclides released. Provide the annual average dispersion values (X/Q and D/Q), the site specific parameters and release point elevation. Other features, such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.

Section 4 - Liquid Effluent Dose

Provide the equations and methodology to be used at the station or unit for each liquid release point according to the dose objectives given in Specifications 3.11.1.2. The section should describe how the dose contributions are to be calculated for the various pathways and release points, the equations and assumptions to be used, the site specific parameters to be

.measured and used, the receptor location by direction and distance, and the method of estimating and updating cumulative doses due to liquid releases. The dose factors, pathway transfer factors, pathway usage factors, and dilution factors for the points of pathway origin, etc., should be given, as well as receptor age group, water and food consumption rate and other factors assumed or measured. Provide the method of determining the dilution factor at the discharge during any liquid effluent release and any site specific parameters used in these determinations. Other features such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.

Section 5 - Gaseous Effluent Dose

Provide the equations and methodology to be used at the station or unit for each gaseous release point according to. the dose objectives given in Specifications 3.11.2.2 and 3.11.2.3. The section should describe how the dose contributions are to be calculated for the various pathways and release points, the equations and assumptions to be used, the site specific parameters to be measured and used, the receptor location by direction and distance, and the method estimating and updating cumulative doses due to gaseous releases, the location direction and distance to the nearest residence, cow, goat, meat animal, garden, etc., should be given, as well as receptor age group, crop yield, grazing time and other factors assumed or measured. Provide the method of determining dispersion values (X/Q and D/Q)

for short-tenn and long-term releases and any site specific parameters

.and release point elevations used in these determinations. Also, provide the criteria for determining short and long term releases. Other features such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.

Section 6 - Projected Doses

For liquid and gaseous radwaste treatment systems, provide the method of protecting doses due to effluent releases for the normal and alternate pathways of treatment according to the specifications, describing the components and subsystems to be used.

Section 7 - Operability of Equipment

Provide a flow diagram(s) defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management systems that are to be maintained and used, pursuant to 10 CFR 50.36a, to meet Technical Specifications 3.11.1.3, 3.11.2.4 and 3.11.3.1. Subcomponents of packaged equipment can be identified by a list. For operating reactors whose construction permit applications were filed prior to January 2, 1971, the now diagram(s) shall be consistent with the information provided in conformance with Section V.B.1 of Appendix I to 10 CFR Part 50. For OL applications whose construction permits were filed after January 2, 1973, the flow diagram(s) shall be consistent with the information provided in Chapter 11 of the Final Safety Analysis Report (FSAR) or amendments thereto.

.Section 8 - Sample Locations

Provide a map of the Radiological Environmental Monitoring sample locations indicating the numbered sampling locations given in Table 3.12-1. Further clarification on these numbered sampling locations can be provided by a list, indicating the direction and distance from the center of the building complex of the unit or station, and may include a descriptive name for identification purposes.