ML19284A617
| ML19284A617 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 02/16/1979 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Wofford A LONG ISLAND LIGHTING CO. |
| References | |
| NUDOCS 7903150113 | |
| Download: ML19284A617 (7) | |
Text
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S UNITED STATES
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- NUCLEAR REGULATORY tOMMISSION 34
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3.I N WASHINGTON, D. C. 20555 E
FEB i n 1979 Docket No:
50-322
>!r. Andrew W. Wofford Vice President Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801
Dear >!r. Wofford:
SUBJECT:
CONTENTS OF THE OFFSITE DOSE CALCULATION SIANUAL (Shoreham Nuclear Power Station)
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 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.
Singerely, D
I llbefarg 'ic hi f sen,
,Light Water Reactcrs Branch No. 4 Division of Proje : Management
Enclosure:
General Contents of the ODCM cc:
See next page 7903150113
r
. Long Island Lighting Company FEB 161979 Howard L.'Blau Blau and Cbhn, P.C.
380 North Broadway Jericho, New York 11753' Jeffrey Cohen, Esq.
Deputy Commissioner and Counsel
'hw York State Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Energy Research Group, Ir.:.
400-1 Totten Pond Road Waltham, Mass. 02154 Irving Like, Esq.
Reilly, Like and Schnieder 200 West Main Street Babylong, New York 11702 J. P. Novarro Pro. ject Manager Shoreham Nuclear Power Station P. O. Box 518 Wading River, New York 11792 W. Taylor Revoley, III, Esq.
Hunton & Williams P. O. Box 1535 Richmond, VA 232i2 Ralph Shapiro, Esq.
Cammer & Shapiro No. 9 East 40th Street New York, New York 10016 Edward J. Walsh, Esq.
General Attorney Long Island Lighting Ccmpany 250 Old Country Road s
Mineola, New York 11501
GENERAL C00TEHTS OF THE OXI?
Section 1 - Set Points Provide the ecuations ano rethoddiogy to be used at the station or unit for each alarm and trip set noint on each effluent release point according to the Speci fications 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 ef fluent isolation control device, its location, power source and identification number.
If the set point value is variable, provide the ecuation to be used to predetennine the set coint 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 survefilance requirements and the calibration method, should be addressed.
Section 2 - Liquid Effluent Concentr*ation 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 appro4al and effective date.
. continuous and/or batch releases, the assumptions used for manual and auto-matic tem.ination of releases shoul : be provided.
For batch releases, the calculational methods, ecuations and assumptions used, tocether 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 addressei.
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 elevatiore, site related parameters and radionuclide contribution to the dose inpact limitation.
Provide the ecua-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 elevation:.. 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-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 location by direction and distance, and the nethod of estir.ating and updating cumulativt doses due to licuid releases.
The dose factors, pathway transfer factors, oathway usage factors, and oilution factors for the coints of patnway origin, etc., should be given, as well as receptor age grovo, water and food consumption rate and other factors assumed or measured. Provide the method of determ:ning the dilu-tion factor at the discharoe during any liquid effluent release and any site specific paraneters used in these deterninations. 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 gisen 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 or measured.
Provide the method of determining dispersion values (X/Q and D/0) for short-term and long-term releases and any site specific parameters
. anc release paint elevations used in these determinations.
Also, provide the criteria for determining short and long term releases. Othe-features such as surveillance reouirements, sarpling and analysis prograr, detection limitations and representative sarpling should be addressed.
Section 6 - Projected Doses For liquid and gaseous radwaste treatment systems, provide the method of projectino deses 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 Ecuioment Provide a flow diagram ( s) defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste managenent 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 permit applications were filed prior to January 2,1971, the flow diagram (s) shall be consistent with the information provided in coriformance with Section V.B.1 of Appendix I to 10 CFR Part 50.
For OI. appl ications whose construction permits were fi' ed 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 t} ereto.
s
. Section P, - Sa-cle Locations
- rovide a rao of the Radiological Er.vircr.,ertal !!onitoring.arple Locations indicating the nunbered sarpling locations given in Table 3.12-1.
Further clarification on tnese nur.bered sanpling locations can be provided by a list, incicating the direction and distance from the center of the building complex of the unit or station, and may include a discriptive name for identification ourposes.
e8