NRC Generic Letter 1979-03: Difference between revisions

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| issue date = 01/18/1979
| issue date = 01/18/1979
| title = NRC Generic Letter 1979-003: Submittal of Guidance on the General Contents of the Offsite Dose Calculation Manual to Aid in Its Preparation for NRC Approval
| title = NRC Generic Letter 1979-003: Submittal of Guidance on the General Contents of the Offsite Dose Calculation Manual to Aid in Its Preparation for NRC Approval
| author name = Grimes B K
| author name = Grimes B
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 5
| page count = 5
}}
}}
{{#Wiki_filter:is pla REG&,; UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, 0. C. 20555January 18, 1979GE-17 -3ALL POWER REACTOR LICENSEESGentlemen:By letter dated November 15, 1978, you were requested to submitRadiological Effluent Technical Specifications and provide for NRCapproval your Offsite Dose Calculation Manual (ODCM). During therecent seminars held at the NRC Regional Offices, we receivednumerous requests for additional guidance on the content for theODCMs. The attachment to this letter provides guidance on thegeneral contents of the ODCM to aid you in its preparation.Sincerely,Brian K. Grimes, Assistant Directorfor Engineering and ProjectsDivision of Operating ReactorsEnclosure:General Contents of theODCM190g8O°3g &
{{#Wiki_filter:is pla REG&,;                       UNITED STATES
GENERAL CONTENTS OF THE ODCM*Section 1 -Set PointsProvide the equations and methodology to be used at the station or unitfor each alarm and trip set point on each effluent 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 to 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 liquid release point according to the Specification 3.11.1.1. Forcontinuous and/or batch releases, the assumptions used for manual and auto-matic termination of releases should be provided. For batch releases, thecalculational methods, equations and 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, stipulating 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.*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.
                          NUCLEAR REGULATORY COMMISSION
                                WASHINGTON, 0. C. 20555 January 18, 1979 GE-1  7 -3 ALL POWER REACTOR LICENSEES
      Gentlemen:
      By letter dated November 15, 1978, you were requested to submit Radiological Effluent Technical Specifications and provide for NRC
      approval your Offsite Dose Calculation Manual (ODCM). During the recent seminars held at the NRC Regional Offices, we received numerous requests for additional guidance on the content for the ODCMs. The attachment to this letter provides guidance on the general contents of the ODCM to aid you in its preparation.


-2 -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-fications 3.11.1.2. 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 bemeasured and used, the receptor location by direction and distance, and themethod of estimating and updating cumulative doses due to liquid releases.The dose factors, pathway transfer factors, pathway usage factors, anddilution factors for the points of pathway origin, 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 parametersand release point elevations used in these determinations. Also, providethe criteria for determining short and long 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 diagram(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 Technical
Sincerely, Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors Enclosure:
-3-Specifications 3.11.1.3, 3.11.2.4 and 3.11.3.1. Subcomponen'ts of packagedequipient 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 OL applicationswhose construction permits were filed after January 2, 1971, the flowdiagram(s) shall be consistent with the information provided in Chapter 11of the Final Safety Analysis Report (FSAR) or amendments thereto.Section 8 -Sample LocationsProvide a map of the Radiological Environmental Monitoring Sample Locationsindicating the numbered sampling 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.
      General Contents of the ODCM
                                    1 9 0 g8O°3g&


JConsolidated Edison Company --of New York, Inc.cc: White Plains Public Library100 Martine AvenueWhite Plains, New York 10601Joseph D. Block, Esq.Executive Vice President -AdministrationConsolidated Edison Companyof New York, Inc.4 Irving PlaceNew York, New York 10003Edward J. Sack, Esq.Law DepartmentConsolidated Edison Companyof New York, Inc.4 Irving PlaceNew York, New York 10003Anthony Z. RoismanNatural Resources Defense Council917 -15th Street, NWWashington, D.C. 20005Paul S. Shemin, EsquireAssistant Attorney GeneralState of New YorkOepartment of LawTwo World Trade CenterNew York, New York 10047Sarah Chasis, EsquireNatural Resources Defense Council122 East 42nd StreetNew York, New York 10017Theodore A. RebelwoskiUSNRCP. 0. Box 38Buchanan, New York 10511  
GENERAL CONTENTS OF THE ODCM*
}}
Section 1 - Set Points Provide the equations and methodology 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 equation to be used to predetermine the set point value 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.
 
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 - 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 continuous and/or batch releases, the assumptions used for manual and auto- matic termination of releases should be provided. For batch releases, the calculational methods, equations and assumptions used, together with the pre-release and post-release analyses should be provided. Other features, such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.
 
Section 3 - Gaseous Effluent Dose Rate Provide the equations 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 pathways, release point elevations, site related parameters and radionuclide contribution to the dose impact 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/Q 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.
 
*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.
 
- 2 -
  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 measured and used, the receptor location by direction and distance, and the method of estimating and updating cumulative doses due to liquid releases.
 
The dose factors, pathway transfer factors, pathway usage factors, and dilution factors for the points of pathway origin, etc., should be given, as well as receptor age group, water and food consumption rate and other factors assumed or measured. Provide the method of determining the dilu- tion factor at the discharge during any liquid effluent release and any site specific parameters 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 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 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 and release point elevations used in these determinations. Also, provide the criteria for determining short and long term releases. Other features such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.
 
Section 6 - Projected Doses For liquid and gaseous radwaste treatment systems, provide the method of projecting 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 Equipment 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
 
-3- packaged
                3.11.1.3,  3.11.2.4  and 3.11.3.1. Subcomponen'ts of Specifications                                                      whose con- can be identified  by  a list. For operating reactors            flow equipient applications  were  filed prior to January 2, 1971, the struction permit                  with the information provided in conformance diagram(s) shall be consistent I to 10 CFR Part 50. For OL applications with Section V.B.1 of Appendix filed after January 2, 1971, the flow whose construction permits were with the information provided in Chapter 11 diagram(s) shall be consistentReport (FSAR) or amendments thereto.
 
of the Final Safety Analysis Section 8 - Sample Locations Locations Environmental Monitoring Sample Provide a map of the Radiological locations given in Table 3.12-1. Further indicating the numbered sampling sampling locations can be provided by a clarification on these numbered and distance from the center of the building list, indicating the direction and may include a discriptive name for complex of the unit or station, identification purposes.
 
J
Consolidated Edison Company       -   -
  of New York, Inc.
 
cc: White Plains Public Library
      100 Martine Avenue White Plains, New York 10601 Joseph D. Block, Esq.
 
Executive Vice President -
        Administration Consolidated Edison Company of New York, Inc.
 
4 Irving Place New York, New York 10003 Edward J. Sack, Esq.
 
Law Department Consolidated Edison Company of New York, Inc.
 
4 Irving Place New York, New York 10003 Anthony Z. Roisman Natural Resources Defense Council
    917 - 15th Street, NW
    Washington, D.C. 20005 Paul S. Shemin, Esquire Assistant Attorney General State of New York Oepartment of Law Two World Trade Center New York, New York 10047 Sarah Chasis, Esquire Natural Resources Defense Council
    122 East 42nd Street New York, New York 10017 Theodore A. Rebelwoski USNRC
    P. 0. Box 38 Buchanan, New York 10511}}


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Latest revision as of 01:57, 24 November 2019

NRC Generic Letter 1979-003: Submittal of Guidance on the General Contents of the Offsite Dose Calculation Manual to Aid in Its Preparation for NRC Approval
ML031290488
Person / Time
Site: Beaver Valley, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Salem, Nine Mile Point, Indian Point, Kewaunee, Point Beach, Cooper, Pilgrim, Prairie Island, Brunswick, Surry, Turkey Point, Vermont Yankee, Duane Arnold, Farley, Robinson, Cook, Quad Cities, Humboldt Bay, Zion, FitzPatrick, 05000000, Trojan
Issue date: 01/18/1979
From: Grimes B
Office of Nuclear Reactor Regulation
To:
References
NUDOCS 7902280385, GL-79-003
Download: ML031290488 (5)


is pla REG&,; UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, 0. C. 20555 January 18, 1979 GE-1 7 -3 ALL POWER REACTOR LICENSEES

Gentlemen:

By letter dated November 15, 1978, you were requested to submit Radiological Effluent Technical Specifications and provide for NRC

approval your Offsite Dose Calculation Manual (ODCM). During the recent seminars held at the NRC Regional Offices, we received numerous requests for additional guidance on the content for the ODCMs. The attachment to this letter provides guidance on the general contents of the ODCM to aid you in its preparation.

Sincerely, Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors Enclosure:

General Contents of the ODCM

1 9 0 g8O°3g&

GENERAL CONTENTS OF THE ODCM*

Section 1 - Set Points Provide the equations and methodology 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 equation to be used to predetermine the set point value 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.

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 - 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 continuous and/or batch releases, the assumptions used for manual and auto- matic termination of releases should be provided. For batch releases, the calculational methods, equations and assumptions used, together with the pre-release and post-release analyses should be provided. Other features, such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.

Section 3 - Gaseous Effluent Dose Rate Provide the equations 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 pathways, release point elevations, site related parameters and radionuclide contribution to the dose impact 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/Q 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.

  • 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.

- 2 -

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 measured and used, the receptor location by direction and distance, and the method of estimating and updating cumulative doses due to liquid releases.

The dose factors, pathway transfer factors, pathway usage factors, and dilution factors for the points of pathway origin, etc., should be given, as well as receptor age group, water and food consumption rate and other factors assumed or measured. Provide the method of determining the dilu- tion factor at the discharge during any liquid effluent release and any site specific parameters 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 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 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 and release point elevations used in these determinations. Also, provide the criteria for determining short and long term releases. Other features such as surveillance requirements, sampling and analysis program, detection limitations and representative sampling should be addressed.

Section 6 - Projected Doses For liquid and gaseous radwaste treatment systems, provide the method of projecting 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 Equipment 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

-3- packaged

3.11.1.3, 3.11.2.4 and 3.11.3.1. Subcomponen'ts of Specifications whose con- can be identified by a list. For operating reactors flow equipient applications were filed prior to January 2, 1971, the struction permit with the information provided in conformance diagram(s) shall be consistent I to 10 CFR Part 50. For OL applications with Section V.B.1 of Appendix filed after January 2, 1971, the flow whose construction permits were with the information provided in Chapter 11 diagram(s) shall be consistentReport (FSAR) or amendments thereto.

of the Final Safety Analysis Section 8 - Sample Locations Locations Environmental Monitoring Sample Provide a map of the Radiological locations given in Table 3.12-1. Further indicating the numbered sampling sampling locations can be provided by a clarification on these numbered and distance from the center of the building list, indicating the direction and may include a discriptive name for complex of the unit or station, identification purposes.

J

Consolidated Edison Company - -

of New York, Inc.

cc: White Plains Public Library

100 Martine Avenue White Plains, New York 10601 Joseph D. Block, Esq.

Executive Vice President -

Administration Consolidated Edison Company of New York, Inc.

4 Irving Place New York, New York 10003 Edward J. Sack, Esq.

Law Department Consolidated Edison Company of New York, Inc.

4 Irving Place New York, New York 10003 Anthony Z. Roisman Natural Resources Defense Council

917 - 15th Street, NW

Washington, D.C. 20005 Paul S. Shemin, Esquire Assistant Attorney General State of New York Oepartment of Law Two World Trade Center New York, New York 10047 Sarah Chasis, Esquire Natural Resources Defense Council

122 East 42nd Street New York, New York 10017 Theodore A. Rebelwoski USNRC

P. 0. Box 38 Buchanan, New York 10511

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