ML14107A096
| ML14107A096 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/08/2014 |
| From: | Yankee Atomic Electric Co |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML14107A089 | List: |
| References | |
| BYR 2014-019 | |
| Download: ML14107A096 (12) | |
Text
BYR 2014-019 ENCLOSURE 3 YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION OFF-SITE DOSE CALCULATION MANUAL, REVISION NO. 22
YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
OFF-SITE DOSE CALCULATION MANUAL TABLE OF CONTENTS 1.0 INT R O D UC T IO N ................................................................................................ 3 1.1 Definitions 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ................................................. 7 2.1 Monitoring Program 2.2 Environmental Monitoring Locations 2.3 Dose/Dose Rate Controls and Calculations 3.0 REPO RTING REQ UIREM ENTS ................................................................................ 10 3.1 Annual Radiological Environmental Operating Report 3.2 Annual Radioactive Effluent Release Report 4 .0 R E FE R E NC E S .............................................................................................................. 11 Revision 22 1
LIST OF FIGURES Figure Title Paqe 1.1 ISFSI Radiological Environmental Monitoring Program TLD Locations 5 (Direct Radiation Pathway) 1.2 ISFSI Radiological Environmental Monitoring Program TLD Locations 6 (Direct Radiation Pathway)
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1.0 INTRODUCTION
The purpose of this document is to provide a method for demonstrating compliance with the dose limits for MEMBERS OF THE PUBLIC and contains the guidance for submittal of the annual reports required by 10 CFR Part 50. In addition, the document provides the locations and type of monitoring required for the Radiological Environmental Monitoring Program (REMP).
In accordance with the requirements of 40CFR Part 190 and 10CFR72.104, the dose to a MEMBER OF THE PUBLIC for radioactive material in effluents and direct radiation from an Independent Spent Fuel Storage Installation (ISFSI) is limited to 25 mrem/yr to the whole body, 75 mrem/yr to the thyroid and 25 mrem/yr to any other critical organ as a result of exposure to planned discharges of radioactive materials to the environment, direct radiation from the ISFSI and any other radiation from uranium fuel cycle operations within the region.
Under normal operations, experience has shown that the ISFSI will be operated at a small fraction of the above dose limits. This is primarily due to the design of the Independent Spent Fuel Storage Installation, which prevents the release of radioactive materials in liquid and particulate form and there are no other uranium fuel cycle operations within 5 miles of the YAEC site. Therefore, the dose equations from regulatory guide 1.109, Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I are not necessary for inclusion in the ODCM. The remaining dose component to be considered is from direct radiation. 40 CFR 190 and 10CFR72.104 establish this dose limit as 25 mrem/yr for MEMBERS OF THE PUBLIC.
Figure 1.2 shows the Owner Controlled Area (OCA) and the current 10CFR Part 50 Licensed area.
1.1 DEFINITIONS Member(s) of the Public MEMBER(S) OF THE PUBLIC (for the purposes of 1 OCFR50, Appendix I) shall include all persons who are not occupationally associated with the site. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category, are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the ISFSI operations.
Offsite Dose Calculation Manual (ODCM)
The ODCM contains the methodology and parameters used in the calculation of off-site doses in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by the Yankee Quality Assurance Program (QAP) and (2)
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descriptions of the information that should be included in the Annual Radiological Environmental Operation and Annual Radioactive Effluent Release Reports.
Site Boundary The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. Realistic occupancy factors shall be applied at these locations for the purposes of dose calculations. For the ODCM, this area is equivalent to the 300 meter Owner Controlled Area.
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2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING The Radiological Environmental Monitoring Program (REMP) for the ISFSI monitors for direct radiation exposure only. There are no radioactive gaseous or liquid effluent pathways associated with the ISFSI.
2.1 Monitoring Program The type and number of radiological environmental monitoring locations including collection and analysis frequencies are shown below.
Number of Exposure Pathway Locations Collection Frequency Type and Frequency of Analysis DIRECT RADIATION 7 Semi-annual Gamma dose, at least once per six months 2.2 Environmental Monitorinq Locations The radiological environmental monitoring locations are listed below. These locations are shown on the maps, included as Figures 1.1 and 1.2.
Monitoring Location and Distance From Direction From Exposure Pathway Designated Code the ISFSI (km) ISFSI DIRECT RADIATION GM-15 On-Site Perimeter 0.24 NW GM-16 On-Site Perimeter 0.22 NNW GM-17 On-Site Perimeter 0.13 NNE GM-21 On-Site Perimeter 0.17 WSW GM-2 Observation Stand 0.50 NW GM-6 Tunnel Road Readsboro 1.30 N Town Line (Readsboro Road Barrier)
GM-27* Number Nine Road 7.60 ENE
- Designated control location. Two TLDs at this sample location.
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2.3 Dose/Dose Rate Controls and Calculations By design, there are no liquid or gaseous effluents associated with the operation of the ISFSI. With the completion of site remediation activities, along with the removal of all systems or operations that generated, contained or processed waste gas or airborne particulates, there are no longer any gaseous or liquid effluent releases from site operations. Therefore, requirements for control, sampling, analyzing, monitoring or dose impact assessment for radioactive liquids or gases are not needed.
2.3.1 Total Dose 2.3.1 The dose or dose commitment to any real MEMBER OF THE PUBLIC from all site sources is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem) over a calendar year.
Applicability At all times.
ACTION With the calculated or projected dose from direct radiation contributions from the Independent Spent Fuel Storage Installation (ISFSI) determined to be, or projected to be, above the annual (calendar) limits of 2.3.1, prepare and submit to the commission with 30 days, pursuant to 10CFR50.4, a Special Report that defines the corrective action to be taken to reduce subsequent exceedences to prevent recurrence of exceeding the above limits and include the schedule for achieving conformance with the above limits. The Special Report shall include an analysis that estimates the radiation exposure (dose) to a member of the public from site sources for the calendar year covered by the report. It also shall describe levels of radiation and concentrations of radioactive material, if any, involved and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the exposure condition resulting in violation of 40CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFR190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
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SURVEILLANCE REQUIREMENTS 2.3.1 Dose calculations - Cumulative dose contributions from direct radiation shall be determined semi-annually in accordance with Section 2.3.2 of the ODCM.
Bases Section 2.3.1 is provided to meet the dose limitations of 40CFR Part 190 that have been incorporated into 10CFR Part 20 by 46FR18525. It requires the preparation and submittal of a Special Report whenever the calculated or projected doses from the site exceed the dose limits of 40CFR Part 190. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to a MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10CFR Part 20.
2.3.2 Method to Calculate Direct Dose from ISFSI Operations Section 2.3.1 restricts the dose to the whole body and any organ of any real MEMBERS OF THE PUBLIC at and beyond the Site Boundary from all site sources (including direct radiation) to the limit of 25 mrem in a year, except for the thyroid which is limited to 75 mrem in a year.
Estimates of direct exposure above background in areas at and beyond the site boundary can be determined from measurements made by environmental TLDs that are part of the Environmental Monitoring Program (Sections 2.1 and 2.2). A net response is determined by subtracting the average TLD value of the control stations from the semi-annual off-site TLD measurements. A positive net exposure is assumed if the net value is greater than the propogated uncertainty of the TLD indicator and control measurements. Alternatively, direct dose -
calculations from identified fixed sources on-site can be used to estimate the off-site direct dose contribution where TLD information may not be applicable.
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3.0 REPORTING REQUIREMENTS 3.1 Annual Radiological Environmental Operating Report
- a. An Annual Radiological Environmental Operating Report covering the operation of the ISFSI during the previous calendar year shall be submitted to the NRC by May 1 of each year.
- b. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the ISFSI operations on the environment.
The Annual Radiological Environmental Operating Report shall include summarized and tabulated results of all radiological environmental monitoring during the report period pursuant to the table and figures in the ODCM. In the event that some results are not available to include in the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The report also shall include the following: a summary description of the Radiological Environmental Monitoring Program results with a map of all monitoring locations keyed to a table giving distances and directions from the ISFSI.
3.2 Annual Radioactive Effluent Release Report
- a. By May 1 of each year, a report shall be submitted to the NRC covering the radioactive content of effluents released to unrestricted areas during the previous calendar year.
- b. The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, Revision 1, June 1974, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.
In addition, the Annual Radioactive Effluent Release Report shall include an assessment of the radiation doses due to the radioactive effluents released from the site during the previous year. This report also shall include an assessment of the radiation doses from radioactive effluents to MEMBER(S) OF THE PUBLIC due to the allowed recreational Revision 22 10
activities inside the SITE BOUNDARY during the previous year. All assumptions used in making these assessments (e.g., specific activity, exposure time, and location) shall be included in the report. The assessment of radiation doses shall be performed in accordance with the ODCM.
The Annual Radioactive Effluent Release Report also shall include an assessment of radiation doses to the likely most exposed real MEMBER(S) OF THE PUBLIC from site activities to show conformance with 40CFR190, "Environmental Radiation Protection Standards for Nuclear Power Operation," if Section 2.3.1 limits has been exceeded during the calendar year.
The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to site boundary of radioactive materials in effluents made during the reporting period.
The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the ODCM.
4.0 REFERENCES
- a. Regulatory Guide 1.109, "Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," U.S. Nuclear Regulatory Commission, Revision 1, October 1977.
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