NRC Generic Letter 1979-06

NRC Generic Letter 1979-006: Contents of Offsite Dose Calculations Manual (North Anna Power Station, Unit 2)

ML031320251
Person / Time
Issue date:	02/14/1979
From:	Parr O D Office of Nuclear Reactor Regulation
To:	Proffitt W L Virginia Electric & Power Co (VEPCO)
References
NUDOCS 7903080031, GL-79-006
Download: ML031320251 (9)

, -0 --DISTRIBUTION OF LETTER TO OL APPLICANTSDistributionto be comDleted by Secretaries:Docket File(sNRC PDR -ftLocal PDR0. D. ParrL PM AM. RushbrookLWR #3 File'Attorney, OELDM. ServiceDistribution to be completed by M. Service:Central FilesR. BoydD. RossD. VassalloM. WilliamsR. DeYoungR. VollmerJ. CollinsI&E-Fonm Letter FileBCC: ACRSNSICTIC(16)'r -.-rn#%IJ4.f 08e) 0 511 FtB 1 4 1979Docket Ho. 50-339W. W. L. ProffittSenior Vice President -PowerOperationsVirginia Electric A Power CompanyP. 0. Box 26666Richmond, Virginia 23261Dear Mr. Proffitt:SUBJECT: CONTENTS OF THE OFFSITE DOSE CALCULATION MANUAL(North Anna Power Station, Unit 2)The Radiological Effluent Technical Specifications for PMR and Bl.Rfacilities issued in November 1978, require you to provide an OffsiteDose Calculation Manual (ODCM) with your proposed Technical Specifi-cations implementing 10 CFR 50.36a and other Federal Regulations.The enclosure to this letter describes the staff's recommendationsfor the general contents of the ODCM. The format for the ODCM is leftto your discretion.Sincerely,mga Stgned by0..ParrOlan D. Parr, ChiefLight Water Reactors Branch No. 3Division of Project ManagementEnclosure:General Contents ofthe ODCMcc w/enclosure:See next pageA-pNRC FORK 318 (9-76) NCM 0240* UW *. GOVRNME4NT PRINTIIN OFFICK0F U 1§7*-A64 Mr. W. L. Proffittcc: Mrs. James C. ArnoldP. 0. Box 3951Charlottesville, Virginia-2 -22903Mr. Anthony GambaradellaOffice of the Attorney General11 South 12th Street -Room 308Richmond, Virginia 23219FEB 1 4 1979John J. Runzer, Esq.Pepper, Hamilton & Scheetz123 South Broad StreetPhiladelphia, Pennsylvania 19109Clarence T. Kipps, Jr., Esq.1700 Pennsylvania Avenue,. N.W.Washington, D. C. 20006Carroll J. Savage, Esq.1700 Pennsylvania Avenue, N. W.Washington, D. C. 20006Mr. James C. DunstanState Corporation ComrmissionCoc;monwealth of VirginiaBlandon BuildingRichmond, Virginia 23209Richard M. Foster, Esq.211 Stribling AvenueCharlottesville, Virginia22903Michael W. Maupin, Esq.Hunton, Williams, Gay & GibsonP. 0. Box 1535Richmond, Virginia 23212Mrs. June Allen412 Owens DriveHuntsville, Alabama 35801Mr. James Torson501 LeroySocorro, New Mexico 87801Mrs. Margaret DietrichRoute 2, Box 568Gordonsville, Virginia 22942William H. Rodgers, Jr., Esq.Georgetown University Law Center600 New Jersey Avenue, N.W.Washington, D. C. 20001Mr. Peter S. HeppExecutive Vice PresidentSun Shipping & Dry Dock CompanyP. 0. Box 540Chester, Pennsylvania 19013Alan S. Rosenthal, Esq.Atomic Safety and LicensingAppeal BoardU.S. Nuclear Regulatory CommissionWashington, D. C. 20555Michael C. Farrar, Esq.Atomic Safety and LicensingAppeal BoardU.S. Nuclear Regulatory CommissionWashington, D. C. 20555Dr. John H. BuckAtomic Safety and LicensingAppeal BoardU.S. Nuclear Regulatory CommissionWashington, D. C. 20555Mr. R. B. BriggsAssociate Director -110 Evans LaneOak Ridge, TennesseeAtomic Safety and LicensingBoard PanelU.S. Nuclear Regulatory Commission37830 Washington, D. C. 20555 Mr. W. L. Proffitt -3- 3 FEB 14 1979cc: Mr. Michael S. KiddU. S. Nuclear Regulatory CommissionP. 0. Box 128Spotslvania, Virginia 22553Dr. Paul W. PurdomDepartment of Civil EngineeringDrexel UniversityPhiladelphia, Pennsylvania 19104Dr. Lawrence R. QuarlesApartment No. 51Kendal -at-LongwoodKennett Square, Pennsylvania 19348 GENJERA4 CC'JTENTS OF THE (,Xrt,*Sectiop 1 -Set PointsProvide the equations and methoddlocy to be used at the station or unitfor each alarm and trip set point on each effluvqt release point accordingto'the Specifications 3.3.3.8 and 3.3.3.9. Provide the alarm and controllocation, the monitor description, location, power source, scale, rangeand identification number, and the effluent isolation control device, itslocation, power source and identification number. If the set point valueis variable, provide the equation to be used to predetermine the set pointvalue 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 dilutionor 'dispersion is used, describe the on-site equipment and measurementmethod used during release, the site related parameters and the set Pointsused tp 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 radioactiveeffluent to have a radionuclide distribution represented by normal andanticipated operational occurrences. Other features, such as surveillancerequirements and the calibration method, should be addressed.Section 2 -Liquid Effluent ConcentrationProvide the equations and methodology to be used at the station or unit foreach liqio 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 simplifiedby tables and grid printout. Each page should be numbered and indicatethe facility approval and effective date.

-2-continuous and/or batch releases, the assumptions used for manual and auto-matic termination of releases should be provided. For batch releases, thecalculational methods, equations dnd assumptions used, together with thepre-release and post-release analyses should be provided. Other features,such as surveillance requirements, sampling and analysis program, detectionlimitations and representative sampling should be addressed.Section 3 -Gaseous Effluent Dose RateProvide the equations and methodology to be used at the station or unit foreach gaseous release point according to Specification 3.11.2.1. Considerthe various pathways, release point elevations, site related parameters andradionuclide contribution to the dose impact limitation. Provide the equa-tions and assumptions used, stipilating the pathway, receptor location andreceptor age. Provide the dose factors to be used for the identified radio-nuclides released. Provide the annual average dispersion values (X/Q andD/Q), the site specific parameters and release point elevations. Otherfeatures, such as surveillance requirements, sampling and analysis program,detection limitations and representative sampling should be addressed.Section 4 -Liquid Effluent DoseProvide the equations and methodology to be used at the station or unit foreach liquid release point according to the dose objectives given in Speci-fiFations 3.11.14. The section should describe how the dose contributionsare to be calculated for the various pathways and release points, theequations and assumptions to be used, the site specific parameters to he

-3-measured and used, the receptor location by direction and distance, and themethod of estir.ating and updating cumulative doses due to liquid releases.The dose factors, pathway transfer factors, Dathway usace factors, anddilution factors for the points of pathway oripin, etc., should be given,as well as receptor age group, water and food consumption rate and otherfactors assumed or measured. Provide the method of determining the dilu-tion factor at the discharge during any liquid effluent release and anysite specific parameters used in these determinations. Other features suchas surveillance requirements, sampling and analysis program, detectionlimitations and representative sampling should be addressed.Section 5 -Gaseous Effluent DoseProvide the equations and methodology to be used at the station or unit foreach 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 dosecontributions are to be calculated for the various pathways and releasepoints, 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 togaseous releases. the location direction and distance to the nearestresidence, cow, goat, meat animal, garden, etc., should be given, as wellas receptor age group, crop yield, grazing time and other factors assumedor measured. Provide the method of determining dispersion values (X/Q andD/Q) for short-term and long-term releases and any site specific parameters

-4-and release paint elevations used in these determinations. Also, providethe criterij for determining short and lona term releases. Other featuressuch as surveillance requirements, sampling and analysis program, detectionlimitations and representative sampling should be addressed.Section 6 -Projected DosesFor liquid and gaseous radwaste treatment systems, provide the method ofprojecting doses due to effluent releases for the normal and alternate path-ways of treatment according to the specifications, describing the componentsand subsystems to be used.Section 7 -Operability of EquipmentProvide a flow diacram(s) defining the treatment paths and the componentsof the radioactive liquid, gaseous and solid waste management systems thatare to be maintained and used, pursuant to 10 CFR 50.36a, to meet TechnicalSpecifications 3.11.1.3, 3.11.2.4 and 3.11.3.1. Suibcomponents of packagedequipment can be identified by a list. For operating reactors whose con-struction permit applications were filed prior to January 2, 1971, the flowdiagram(s) shall be consistent with the information provided in conformancewith Section V.B.1 of Appendix I to 10 CFR Part 50. For 01. applicationswhose construction permits were filed after January 2, 1971, the flowdiaqram(s) shall be consistent with the information provided in Chapter 11of the Final Safety Analysis Report (FSAR) or amendments tler-eto.

-5-Section P. -Sar le LocationsFrovide a rap of the Radiolooical Envirore.Iental flonitoring 5arple Locationsindicating the numbered sarpling locations given in Table 3.12-1. Furtherclarification on these numbered sampling locations can be provided by alist, indicating the direction and distance from the center of the buildingcomplex of the unit or station, and may include a discriptive name foridentification purposes.