ML19317E034
| ML19317E034 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/18/1979 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | Borsum R, Mcgarry J, Porter W BABCOCK & WILCOX CO., DEBEVOISE & LIBERMAN, DUKE POWER CO. |
| References | |
| NUDOCS 7912110812 | |
| Download: ML19317E034 (5) | |
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'4 UNITED STATES i-k NUCLEAR REGULATORY COMMISSION i
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E W ASHWGTON. D. C. 20555
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January 18, 1979 7 4-c 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 ccntent for the ODCMs.- The attachment to this letter provides guidance on the general contents of the ODCM to aid you in its preparation.
Sincerely, J
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Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors
Enclosure:
General Contents of the ODCM L
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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 eouipment 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 - Liauid 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 reouirements, 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 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/0), the site specific parameters and release point elevations.
Other features, such as surveillance requirenents, 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.
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, 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 detemining the dilu-tion factor at the discharge during any liquid effluent release and any site specific parameters used in these deteminations.
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 ooint 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-neters to be measured and used, the receptor location by direction and dis-tance, and.the nethod 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 oiven, as well as receptor age group, crop yield, grazing time and other factors assumed or measured.
Provide the method of detemining dispersion values (X/0 and D/Q) for short-tem and long-tem releases and any site specific parameters and release point elevations used in these deteminations.
Also, provide the criteria for-detemining short and long tem 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 nomal 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 g--
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l 3-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 applications 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
. hose construction permits were. filed after January 2,1971, the flow w
diagram (s) shall be consistent with the information provided in Chapter 11 of the Final Safety Analysis Report (FSAR) or snendments thereto.
Section 8 - Sample Locations i
Provide a map of the Radiological Environmeittal Monitoring Sample Locations indicating the numbered sampling locations given in Table 3.12-1.
Further clarification on these numbered sampling locations can b. 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.
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cc:
Mr. William L. Porter
-Duke Power Company Post Office Box 2178 422 56uth' Church Street:
Charlottei North Carolina 28242-lJ. flichael McGarry, III, Esquire Debevoise & Liberman
- 700 Shoreham Building 806L 15th Street, N.W.
4-Washington, D. C.
20005
.U. S. Nuclear. Regulatory Commission
. Region II Office of Inspection and Enforcement ATTN Mr. Francis Jape.
101,arietta' Street, Suite ~3100 Atlanta, Georgia 30303:
Mr. Robert B. Borsum.
-Babcock & Wilcox Nuclear Power Generation Division Suite 420,~ 7735 Old Georgetown Road Bethesda, Maryland 20014 Manager, LIS-NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Oconee Public Library-201. South Spring. Street Walhalla, South Carolina 29691' L
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