ML19276E454
| ML19276E454 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/13/1979 |
| From: | Baer R Office of Nuclear Reactor Regulation |
| To: | Gary R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 7903140125 | |
| Download: ML19276E454 (7) | |
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NUCLEAR REGULATORY COMMISslON F sL
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- FEB 131979 Docket Nos. 50-445 and 50-446 Mr. R. J. Gary Executive Vice President and General Manager Texas Utilities Generating Company 2001 Eryan Towers Dallas, Texas 75201
Dear ft. Gary:
SUBJECT:
C0flTENTS OF THE OFFSITE DOSE CALCULATI0ft MAf!UAL (Comanche Peak Steam Electric Station, Units 1 and 2)
The Radiological Effluent Technical Specifications for PWR ind BWR facil-ities issued in November 1978 require you to provide an Offsite Dose Calculation Manual (00CM) with your proposed Technical Specifications 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 discreticn.
Si ncerely,
./
47 Robert L. Baer, Chief Light Water Reactors Branch ?!o. 2 Division of Project Management
Enclosure:
General Contents of the ODCM ces w/ enclosure:
See next page 7903140195 i
. continuous and/or batch releases, the assunctions used for manual and auto-matic termination of releases should be provided.
For batch releases, the calculational methods, equations and assumptions used, tocether with the pre-release and post-release analyses should be provided.
Other features, such as surveillance requirenents, sampling and analysis progran, detection limitations and representative sampling should be addressed.
Section 3 - Gaseous Effluent Dose Rate Provide the ecuations 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 patha'ays, release point elevations, site related parameters and radionuclide contribution to the dose inpact limitation.
Provide the equa-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 - Liouid 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-fica tions 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
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' Section 8 - Sanole Locations trovice a rac of the Radiological Ensiror.ner.tal 'onitcring Sarole Locations indicating the numbered sarpling locations given in Table 3.12-1.
Further clarification on tnese nunbered sanpling locations can De 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 purposes.
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anc re'. ease point elevations used in these determinations.
Al so, previce cre criteria for deternining short and lonc tarn releases.
Other featuras such as surveillance reouirements, sarplinc and analysis orogran, detection i
limitations and representative sanpling should be addressed.
Section 6 - Projected Doses For licuid and gaseous radwaste treatnent systems, provide the method of projecting deses due to effluent releases for the normal and alternate cath-ways of treatment according to the soecifications, describing the cc'ponents and subsystens to be used.
Section 7 - Operability of Ecuioment Provide a flow diagram (s) defining the treat;ent 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 equipcent can be identified by a list.
For operating reacters 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 diacran(s) shall be consistent with the infon,ation provided in Chapter 11 of the Final Safety Analysis Report (FSAR) or amendments thereto.
. reasured and used, the receptor location by direction and distance, and the nethod of estimating and updating cumulative doses cue to licuic releases.
The dose factors, pathway transfer factors, cathway usage factors, anc dilution factors for the coints of pathway oricin, etc., should be given, as well as receptor age group, water and food consumption rate anc other factors assumed or neasured.
Provide the method of determining the dilu-tion factor at the discharge during any liquid effluent release and any site specific paraneters 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 SIeci-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 factors 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
GENERAL CONTENTS OF THE 030i'?
Section 1 - Set Points Provice the ecuations anc methoddlogy to be used at the staticn or unit for each al ar.T and trio set point on each effluent release ccir.: accordinc to the Specifications 3.3.3.8 and 3.3.3.9.
Provide the alarm and control location, the monitor description, location, oower scurce, scale, range and identification number, and the ef fluent isclation control device, its I
location, power source and identification number.
If the set point value I
is variable, provide the ecuation to be used to predetermine the set Doint value tnat 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 Specificatiori 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 - Liouid 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 nay be sirplified by tables and grid printout.
Each page should be numbered and indicate the facility approval and effective date.
i
Texas Utilities Generating Company ccs:
Nicholas S. Reynolds, Esq.
Debevoise & Liberman 1200 Seventeenth Street Washington, D.C.
20036 Spencer C. Relyea, Esq.
Worsham, Forsythe & Sampels 2001 Bryan Tower Dallas, Texas 75201 Mr. Homer C. Schmidt Project Manager - Nuclear Plants Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Mr. H. R. Rock Gibbs and Hill, Inc.
393 Seventh Avenue New York, New York 10001 Mr. G. L. Hohmann Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230
=..
Richard W. Lowerre, Esq.
Of fice of the Attorney General P. O. Box 12548 Austin, Texas 78711 Ms. Nancy Holdam Jacobson Coordinator, CFUR 1400 Hemphill Street Forth Worth, Texas 76104 Mrs. Juanita Ellis, President CASE P. O. Box 4123 Dallas, Texas 75208 i-
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