ML19289D809
| ML19289D809 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 02/16/1979 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 7903140480 | |
| Download: ML19289D809 (7) | |
Text
UNITED STATES y4 y '4 NUCLEAR RECULATORY COMMISSION g..
I WASHINGTON, D. C. 20555 11 -
' S o
%, '.%s /
FEB 161979 Docket Nos:
50-329 50-330 Mr. S. H. Howell Vice President Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201
Dear Mr. Howell:
SUBJECT:
CONTENTS OF THE OFFSITE DOSE CALCULATION MANUAL (Midland Plant, Units 1 and 2)
The Radiological Effluent Technical Specifications for PNR and BNR facilities issued in November 1978, require you to
. provide an Offsite Dose Calculation Manual (ODCM) 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 con-tents of the ODCM.
The format for the ODCM is left to your discretion.
S' erely 1
/
.\\a hief Light Water Re tors Branch No. 4 Division of Pr ect Management
Enclosure:
General Contents of the ODCM cc:
See nest page
?so31aogg6
,t-
'Consmaers Power Company FEB 16 1979 ces:
Michael 'I. Miller, Esq.
Isham, Lincoln & Beale Suite 4200 One First National Plaza Chicago, Illinois 60670 Judd L. Bacon, Esq.
Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Mr. Paul A. Perry Secretary Consumers Power Company 212 W. Michigan Avenue Jackson, Michigan 49201 Myron M. Cherry, Esq.
One IBM Plaza Chicago, Illinois 60611 Mary Sinclair 5711 Summerset Drive Midland, Michigan 48640 Frank J. Kelley, Esq.
Attorney General State of Michigan Environmental Protection Division 720 Law Building Lansing, Michigan 48913 Mr. Wendell Marshall Route 10 Midland, Michigan 48640 Grant J. Merritt, Esq.
Thompson, Nielsen, Klaverkamp & James 4444 IDS Center 80 South Eighth Street Minneapolis, Minnesota 55402 s
~
GENERAL CONTENTS OF THE 030l?
Section 1 - Set Points Provide the ecuations ano rethoddlocy 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, 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 ecuation 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 ooints 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 format 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.
4
. continuous and/or batch releases, the assumptions used for manual and auto-matic termination of releases shoul be provided.
For batch releases, the calculational methods, ecuations and assumptions used, tocether with the Other features, pre-release and post-release analyses should be provided.
such as surveillance requirenents, sampling and analysis program, detection limitations and representative sampling should be addressed.
Section 3 - Gaseous Effluent Dose Rate Provide the eouations 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 Other D/0), the site specific parameters and release point elevation!..
features, such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling shod 1d be addressed.
Section 4 - Liquid Effluent Dose Provide the equations and methodology to be used at the station or un't 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
_3 reasured and used, the receptor location by direction and distance, and the nethod of estinating and updating cumulative doses due to licuid releases.
The dose factors, pathway transfer factors, oathway usage factors, and dilution factors for the points of pathway oriain, etc., should be given, as well as receptor age group, water and food consumption t ate and other factors assumed or neasured.
Provide the nethod 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 Oose Provide the equations and methodology to be used at the station or unit for each gaseous release point according to the dose objectives gi/en 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 assteed or measured.
Provide the method of detemining dispersion values (X/Q and D/Q) for short-term and long-term releases and any site specific parameters
. and release paint elevations used in these deterninations.
Also, provide the criteria for determining short and long term releases.
Othe-features such as surveillance reouirements, sarpling and analysis progra, detection limitations and representative carpling 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 normal and alternate path-ways of treatment according to the specifications, describing the components and subsystems to be used.
Section 7 - Operability of Eouioment Prov.ide a flow diagram (s) defining the treatnent 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 applicrtions 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 pennits 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.
. Section 8 - Saccle Locations Frovide a r:ao of the Radiological Enviror.mertal f'onitoring arple Locations indicating the nunbered sarpling locations given in Table 3.12-1.
Further clarification on these nur.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.
9 e
N