ML19269C981
| ML19269C981 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/23/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 7902260008 | |
| Download: ML19269C981 (7) | |
Text
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b UNITED STATES g
y4 NUCLEAR REGULATORY COMMISSION
,j WASHINGTON, D. C. 20555
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Docket Nos. 50-325 and 50-324 Mr. J. A. Jones Executive Vice President Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602
Dear Mr. Jones:
The Draft Radiological Effluent Technical Specifications for BWR facilities (NUREG-0473) were foniarded to you by letter dated November 15, 1978.
You were requested to include the equations for dose calculations, setpoint determinations, and meterological dispersion factors in an Offsite Dose Calculation Manual (ODCM) which was to be provided to the NRC along with your proposed Technical Specifications.
To assist you in preparing the ODCM, we have enclosed our guidance for the general contents of the ODCM.
The format of the ODCM is at your discretion and may be simplified by tables and grid printout.
We hope that this information will be helpful in preparing your submittal.
Please contact us if you have further questions.
Sincerely, i
Thomas
. Ippo ito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Enclosure:
General Contents of the ODCM cc w/ enclosure:
See next page 7902260008
Carolina Power & Light Company January 23, 1979 cc:
Richard E. Jones, Esquire Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 George F. Trowbridge, Esquire Shaw, Pittman, Potts & Trowbridge 1800 M Street, NW Washington, D. C.
20036 John J. Burney, Jr., Esquire Burney, Burney, Sperry & Barefoot 110 North Fifth Avenue Wilmington, North Carolina 28401 Southport - Brunswick County Library 109 W. Moore Street Southport, North Carolina 28461 O
GENEPAL CONTENTS OF THE ODCM*
Section 1 - Set Points Provide the equations and methodology to be used at the station or unit for each' alarm an'd trip set point on e;Jc 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, power source, scale, rance 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 ecuation 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 procress.
If dilution or dispersion is used, describe the on-site ecuipment and measurement method used during release, the site related parameters and the set pcints used to assure that the Specification is met at each release point, in-cluding 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 - Licuid 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 fonnat for 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 auto-natic tennination 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, sanpling and analysis program, detection limitations and representative sampling should be addressed.
Section 3 - Gaseous Effluent Dose P. ate Provide the equations and methocology 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 paraneters and radionuclide contribution to the dose inpact limit Provide the ecua tions and assumptions used, stipulating the pathway, receptor location and receptor age.
Provide the dose factors to be used for the identified radio-nuclides released.
Provide the annual average dispersion values (X/0 and D/Q), the site specific parameters and release point elevations. 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 Speci-fications 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, n d the method of estinating 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 dilu-tion factor at the discharge during any liouid effluent release and any site specific parameters used in these deterninations.
Al so, provide the criteria for deternining short and long term releases.
Other features such as surveillance requirenents, sampling and analysis progran, 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 Speci-fications 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 para-meters to be measured and used, the receptor location by direction and dis-tance, 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 fac_ tors assumed or measured.
Provide the method of determining dispersion values (X/Q and D/Q) for short-term and long-term releases and any site specific parameters
and release point elevations used in these determinations.
Other features such as surveillance reauirements, sampling and analysis program, detection limitations and representative sanpling should be addressed.
Section 6 - Projected Doses For liquid and gaseous radwaste treatment systems, provide the method of projecting doses due to effluent releases for the normal and alternate path-ways of treatment according to the specifications, describing the components and subsystems to be used.
Section 7 - Ocerability of Ecuiement 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 con-struction pennit applications were filed prior to January 2,1971, the flow 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 2,1971, the flow diagran(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 Enviromental 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 discriptive name for identification purooses.
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