ML19289D695
| ML19289D695 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/16/1979 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Niav Hughes TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 7903140142 | |
| Download: ML19289D695 (7) | |
Text
' S, UNITED STATES y q.
,yS NUCLEAR REGULATORY COMMISSION l
WASHINCTON, D. C. 20555 fkf./
FEB 161979 Docket Nos:
50-327 50-328 Mr. N. B. Hughes Manager of Power Tennessee Valley Authority 830 Power Building Chattanooga, Tennessee 37401
Dear Mr. Hughes:
SUBJECT:
CONTENTS OF THE OFFSITE DOSE CALCULATION MANUAL (Sequoyah Nuclear Plant, Units 1 4 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 Specificaticas implementing 10 CFR 50.36a and other Federal Regulations.
The enclosure to this letter describes the staff's recommendations for the general con-tents of the ODCM.
The format for the ODCM is left to your discretion.
Si erely
)
[h td jSteven A. Varga,\\ Chief Light Water Reaqt\\ ors Branch No. 4 Division of ProjVct Management
Enclosure:
General Contents of the ODCM cc:
See next page 7903140 8 %
FEB 161979 Tenness e Valley Authority CCs:
Herbert S.' Sanger, Jr. Esq.
General Counsel Tennessee Valley Authority 400 Commerce Avenue E 118 33 Xnoxville, Tennessee 37902 Mr. E. G. Beasley Tennessee Valley Authority W90135 400 Commerce Avenue Knoxville, Tennessee 37902 Mr. Michael Harding Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. David Lambert Tennessee Valley Authority 303 Power Building Chattanooga, Tennessee 37401
\\
t
GEf4ERAL C0tlTEt!TS OF THE OXM*
Section 1 - Set Points provide the ecuations ano rethoddiocy to be used at the station or unit for each slarm and trip set point on each effluent release point accordine 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, 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 enuation to be used to predetermine the set point val.ue 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, in-cluding any administrative controls applicable at the station or unit.
Th9 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 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-matic termination of r21 eases shoul. be provided.
For batch releases, the calculational methods, ecuations and assumptions used, together with the pre-release and post-release analyses should be provided.
Other features, such as surveillance requirenents, sampling and analysis program, 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 Consider each gaseous release point according to Specification 3.11.2.1.
the various pathways, 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 Provide the dose factors to be used for the identified radio-receptor. age.
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
, reasured and used, the receptor incation by direction and distance, and the nethod of estir.ating and updating cumulative doses due to liouid releases.
The dose factors, pathway transfer factors, oathway usace factors, and dilution factors for the points of pathw / oricin, etc., should be given, as well as receptor age group, water and food consumption r ate and other factors assumed or neasured.
Provide the nethod of detemining the dilu-tion factor at the discharge during any liquid effluent release and any site specific paraneters used in these deteminations.
Other features vch 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 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 t'ime and other factors assumed nr measured.
Provide the method of detemining dispersion values (X/Q and D/Q) for short-tem and long-term releases and any site specific parameters
4 and release paint elevations used in these deteminations.
Al so, provide the criteri.: for detemining short and long term releases.
Othe-features such as surveillance reauirements, sarplina and analysis progra", detection limitations and representative sarpling should be addressed.
Section 6 - Projected Doses For liquid and gaseous radwaste treatment systems, provide the method of projectino doses due to effluent releases for the nomal and alternate path-ways of treatment according to the specifications, describing the components and subsystems to be used.
Section 7 - Operability of Eauioment 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 pemit applications were filed prior to January 2,1971, the flow diagram (s) shall be consistent with the infomation provided in conformance with Section V.B.1 of Appendix I to 10 CFR Part 50.
For 01. applications whose construction pemits were filed after January 2,1971, the flow diagram (s) shall be consistent with the information provided in Chapter 11
^ of the Final Safety Analysis Report (FSAR) or amendments ti er~eto.
. Sfection 8 - Sa.cle Location:
Frovide a r.ao of the Radiological Envirort ertal !!cnitoring.-arple Locations indicating the nunbered sarpling locations given in Table 3.12-1.
Further clarification on these nu:.bered sanpling 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 purposes.
O e
@