Working Paper Entitled, Demonstrating Compliance W/Radiological Criteria for Decommissioning Section C.4: Regulatory Position:Alternative Position, for Future Regulatory GuideML20198Q102 |
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01/06/1998 |
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NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
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ML20198Q077 |
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NUDOCS 9801220344 |
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Category:NRC TECHNICAL REPORT
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Annual Report ML20198Q1101998-01-0808 January 1998 Working Paper Entitled, Demonstrating Compliance W/Radiological Criteria for Decommissioning Section C.4: Regulatory Position:Alara Analyses, for Future Regulatory Guide ML20198Q1021998-01-0606 January 1998 Working Paper Entitled, Demonstrating Compliance W/Radiological Criteria for Decommissioning Section C.4: Regulatory Position:Alternative Position, for Future Regulatory Guide ML20202G1811997-12-31031 December 1997 Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance.Appendices ML20202G1231997-12-31031 December 1997 Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance.Summary Report ML20202G1551997-12-31031 December 1997 Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance ML20199K0271997-11-30030 November 1997 Feasibility of Underwater Welding of Highly Irradiated IN-VESSEL Components of Boiling Water Reactors.A 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Costs at Low-Level Waste Burial Facilities ML20116P2611996-08-31031 August 1996 A Reassessment of the Potential for an ALPHA-MODE Containment Failure and a Review of the Current Understanding of Broader FUEL-COOLANT Interaction Issues. Report of the Second Steam Explosion Review Group Workshop ML20116E3721996-07-31031 July 1996 A Prioritization of Generic Safety Issues ML20112H6051996-05-31031 May 1996 Public Comments on the Proposed 10 CFR Part 51 Rule for Renewal of Nuclear Power Plant Operating Licenses and Supporting Documents: Review of Concerns and NRC Staff Response.Executive Summary ML20112H5651996-05-31031 May 1996 Regulatory Analysis for Amendments to Regulations for the Environmental Review for Renewal of Nuclear Power Plant Operating Licenses.Final Report ML20134C8301996-03-26026 March 1996 Rulemaking Issues Radiological Criteria for License Termination for 960326 ML20096H6571995-12-31031 December 1995 Reassessment of NRCs Dollar Per PERSON-REM Conversion Factor Policy 1999-09-30
[Table view]Some use of "" in your query was not closed by a matching "". Category:TEXT-SAFETY REPORT
MONTHYEARML20195D8661999-12-31031 December 1999 Draft Rept, Evaluation of Air-Operated Valves at Us Light-Water Reactors ML20217K0811999-10-31031 October 1999 Methodology for Identifying Financial Variables for Trend Analysis ML20217D0851999-09-30030 September 1999 Interim Report, Regulatory Effectiveness of Station Blackout Rule ML20211F1221999-07-31031 July 1999 Generic Issue Management Control System Rept ML20196K6981999-06-30030 June 1999 Effects of Deregulation of Electric Power Industry on Nuclear Plant Offsite Power Sys:An Evaluation ML20196J0821999-06-30030 June 1999 Draft Rept, NRC Fire Risk Research Plan:Fys 1998-2000 ML20206Q4151999-05-31031 May 1999 Report to Congress on Abnormal Occurrences.Fiscal Year 1998 ML20206H4691999-04-30030 April 1999 A Prioritization of Generic Safety Issues ML20205Q7501999-04-22022 April 1999 Draft Vision Statement on Performance-Based Approaches ML20206N2431999-03-31031 March 1999 Radiological Assessment for Clearance of Equipment and Materials from Nuclear Facilities.Main Report.Draft Report for Comment ML20206K2561999-03-31031 March 1999 Radiological Assessments for Clearance of Equipment and Materials from Nuclear Facilities.Appendices.Draft Report for Comment ML20205P0811999-01-31031 January 1999 Technical Elements of RISK-INFORMED Inservice Inspection Programs for Piping ML20199L3771998-12-31031 December 1998 Report on Waste Burial Charges.Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities ML20199J3171998-12-17017 December 1998 Options for Incorporating Risk Insights Into 10CFR50.59 Process ML20196H2051998-11-30030 November 1998 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 1997.Thirtieth Annual Report ML20155C0231998-10-31031 October 1998 Compilation of Reports from Research Supported by the Electrical,Materials and Mechanical Engineering Branch, Division of Engineering ML20153D4031998-07-31031 July 1998 Technical Review of RISK-INFORMED, PERFORMANCE-BASED Methods for Nuclear Power Plant Fire Protection Analyses.Draft Report for Comment ML20236T1171998-06-30030 June 1998 A Nonparametric Statistical Methodology for the Design and Analysis of Final Status Decommissioning Surveys.Interim Report for Use and Comment ML20248H7681998-05-31031 May 1998 Technical Basis and Implementation Guidelines for a Technique for Human Event Analysis (Atheana).Draft Report for Comment ML20248H7321998-05-31031 May 1998 Proceedings of the Workshop on Review of Dose Modeling Methods for Demonstration of Compliance with the Radiological Criteria for License Termination ML20216D2421998-04-30030 April 1998 Generic Issue Mgt Control Sys Rept ML20247E1551998-04-30030 April 1998 The Characterization of Vickers Microhardness Indentations and PILE-UP Profiles as a STRAIN-HARDENING Microprobe ML20217M1091998-03-31031 March 1998 A Prioritization of Generic Safety Issues ML20196H7121998-03-13013 March 1998 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors (10CFR50) ML20216E6521998-02-28028 February 1998 Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other FACILITIES,1996.Twenty-Ninth Annual Report ML20198Q1101998-01-0808 January 1998 Working Paper Entitled, Demonstrating Compliance W/Radiological Criteria for Decommissioning Section C.4: Regulatory Position:Alara Analyses, for Future Regulatory Guide ML20198Q1021998-01-0606 January 1998 Working Paper Entitled, Demonstrating Compliance W/Radiological Criteria for Decommissioning Section C.4: Regulatory Position:Alternative Position, for Future Regulatory Guide ML20202G1811997-12-31031 December 1997 Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance.Appendices ML20202G1231997-12-31031 December 1997 Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance.Summary Report ML20202G1551997-12-31031 December 1997 Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance ML20199K0271997-11-30030 November 1997 Feasibility of Underwater Welding of Highly Irradiated IN-VESSEL Components of Boiling Water Reactors.A Literature Review ML20202J3131997-11-30030 November 1997 Report on Waste Burial Charges.Escalation of Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities ML20198F7771997-09-11011 September 1997 Working Paper Reg Guide:Demonstrating Compliance W/ Radiological Criteria for Decommissioning Section C.3: Regulatory Position:License Termination Under Restricted Conditions ML20149G3161997-06-30030 June 1997 Generic Issue Mgt Control Sys Second Quarter FY-97 Update ML20217G9901997-06-0101 June 1997 LWR Severe Accident Research Accomplishments & Future Plans, Presented at 970601-04 Second Intl Conference on Advanced Reactor Safety in Orlando,Florida ML20217H2521997-05-26026 May 1997 NRC Response to Electric Utility Deregulation Relating to Financial Assurance for Decommissioning, Presented at 970526-30 5th International Conference on Nuclear Engineering in Nice,France ML20248F0531997-05-19019 May 1997 Review of In-Vessel Coolability & Retention of Core Melt DOE/ID-10460, Jul 1995 ML20149E3771997-04-30030 April 1997 Errata to Regulatory Analysis on Criteria for Release of Patients Administered Radioactive Matl,Final Rept, Replacing Pages A.1 & A.2 in App a W/Encl Pages.In Table A.1,exposure Rate Constant for Pd-103 Implant Changed ML20217J3171997-04-0202 April 1997 Effect of RELAP5/MOD3.2 User Options on Calculated Results ML20217H3011997-03-0303 March 1997 Conference Paper, Us NRC Seismic Regulations,Research & Emerging Trends, Presented at 970303-06 International Symposium on Seismic Safety Relating to NPP Held in Kobe, Japan ML20137A2401997-02-28028 February 1997 Regulatory Analysis on Criteria for the Release of Patients Administered Radioactive Material.Final Report ML20136C3341997-02-28028 February 1997 Sampling Plans for Dedicating Simple,Metallic Commercial Grade Items at Npps ML20147H6271997-02-28028 February 1997 Generic Issue Mgt Control Sys First Quarter FY97 Update ML20134L3161997-01-31031 January 1997 Occupational Radiation Exposure at Commerical Nuclear Power Reactors and Other FACILITIES,1995.Twenty-Eighth Annual Report ML20132B2001996-12-31031 December 1996 Generic Issue Mgt Control Sys Fourth Quarter FY96 Update ML20133E8291996-12-31031 December 1996 A Prioritization of Generic Safety Issues ML20132A8101996-11-30030 November 1996 Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance.Parts 2-5.Draft Report for Comment ML20149L8931996-10-31031 October 1996 Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance.Summary Report.Draft Report for Comment ML20117P2171996-09-30030 September 1996 Report on Waste Burial Charges.Escalation of Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities ML20116P2611996-08-31031 August 1996 A Reassessment of the Potential for an ALPHA-MODE Containment Failure and a Review of the Current Understanding of Broader FUEL-COOLANT Interaction Issues. Report of the Second Steam Explosion Review Group Workshop 1999-09-30
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DEMONSTRATING COMPLIANCE WITH THE RADIOLOGICAL CRITERIA FOR DECOMM.ISSIONING SECTION C.4: REGULATORY POSITION:
AlsTERNATIVE CRITERIA FOR LICENSE TERMINATION Omce of Nuclear Regulatory itesearch U. S. Nuclear Regulatory Commission DISCLAIMER This working paper is being developed for a future NRC Regulatory Guide,
" Demonstrating Compliance with the Radiological Criteria for Decommissioning." It is a working draft only and is subject to extensive change. Its purpose is to obtain comments from NRC staff and others. It has received only limited NRC staff review and no NRC i
management approval.
3.4 Alternate criteria for license tennination For a few sites with unique decommissioning problems, the NRC may terminate a license under 10 CFR 20.1404 using an alternate dose criterion greater than 25 millirems (0.25 millisievert) per year up to a maximum of 100 millirems (1 millisievert) per year from all manmade sources except medical.
Ilowever, the NRC expects to do this only under very rare and unusual circumstances.
9001D20344 900112 PDR STPRO ESGOH I or3 PDR 01/06/98 12:28:39 i
i-hupd/techconf. tint govhaderPmodc3 4.html http1/techconf,llnl gov /radcrPmodc3 4 html In order for the NRC to consider a licensee's request to terminate their license using the altetaate criteria option,10 CFR 20.1404(a) requires that the licensee meet all of the following reqmrements:
- 1. Pmvide assurance that public health and safety would continue to be protected, and that it is unlikely that the dose from all man made sources combined, other than medical, would be more than 100 millirems (1 millisievert) per year.
- 2. Employ, to the extent practical, restrictions on site use.
- 3. Redue: doses to Al ARA levels.
- 4. Submit a decommissioning plan or license tennination plan that indicates the intent to release the site under alternate criteria, includmg information on how advice ofindividuals and institutions in the community who may be affected by the decommissioning has been sought and addressed.
The use of alternate criteria to terminate a license requires the approval of the Commission after consideration of the NRC staffs recommendations that will address any comments provided by the Environmental Protection Agency and any public comments submitted.
3.4.1 Limit on dose from all man made sources combined The licensee should submit a complete and comprehensive analysis of man made sources of radiation exposure, other than medical. The man made sources of radiation that should be included include the following: (1) lonie.ini; radiation from licensed or regulated byproduct, source, or special material, but excluding medical exposures received by patients,(2) ionizing radiation from x ray machines, accelerators, and similar electronic devices producing lonizing radiation, but excluding medical exposures received by patients,(3) ionizing radiation fmm naturally occurring radioactive materials that have been processed, concentrated, and purified, such as sealed sources containing radium or chemical compounds containing radium, and (4) ionizing radiatian from radioactive fallout from weapons testing.
Sources ofionizing radiation not included are: (1) ionizing radiation from natural background, (2) ionizing radiat' smm naturally occurring radioactivity found in building materials,(3) ionizing radiation from naturally occurring radioactivity svhose dose has been changed through some aspect of building design or construction, for example, naturally occurring radon in a building is not considered a man made source regardless of the way in which the design, construction, or operation of the building would affect the radon concentration, and (4) radiation exposure to patients from medical practices.
For radiation exposures that are not associated with the site, the dose to the average member of the critical group can be taken to be the dose to the average member of the U. S. poaulation. The analysis may use infomiation from sources such as NCRP Report 92 "Public Radiation 2xposure from Nuclear Power Generation in the United States," NCRP Report 93, "lonizing Radiation Exposure of the Population of the United States," and NCRP Report 95, " Radiation Exposure of the U. S. Population fmm Consumer Products and Miscellaneous Sources."
The analysis should include site-specific considerations, in general, the annual dose is calculated survey unit by-survey unit. The radiation dose from residual radioactivity in the survey unit should be added to the doses from other man made radiation exposure other than medical, The site specific sources should include the radiation exposure from other nearby sites using radioactive msterials, and radiation exposure from groundwater that has migrated from other areas with man-made sources of residual radioactivity.
This approach will allow the licensee to determine which survey units will be subject to the alternate criteria. The objective is for the area to be subject to the alternate criteria to be as small as possibic.
'llowever, in selecting the area to be released under the alternate criteria, the site should normally have only a single such area and the area should have fairly regular (not gerrymandered) boundaries. This may meen that the area subject to the altemate criteria may include some areas that did not have to be 01/0&98 12:28:39 2 of 3 n
http/hechconf lini gov /radcri' mode)-4.html http/Accheonf.llnl gov /raderi'modc3-4.html released under the alternate criteria.
3.4.2 Practical restrictions on site use 1
The licensee must employ restrictions on site use to the extent practical (10 CFR 20.1404(a)(2)).
l Restrictions that are practical usually means simple deed restrictions that do not require periodic maintenance or financial assurance. Deed restrictions are usually practical because they are relatively easy and inexpensive to impose and do not normally require active control or maintenance. Thus, simple deed restrictions should nonnally be used to meet this requirement for practical restrictions. Therefore, sites released under alternate criteria would gen rally be released under restricted conditions. Examples of simple deed restrictions that are normally practical and which should be considered when appropriate inch.de prohibitions on: residences, farming, using ground water for irrigation, and using ground water for drinking water.
3.4.3 information to be submitted in the decommissionine plan or license termination plan in addition to the information required for release under resti,1ed conditions, release under attemate criteria should include the following additional information: (1) an analysis to demonstrate that the limit on dose from all man made sources of radiation combined will be met, and (2) the practical restrictions on site use that will be used and evaluations for other restrictions that were considered but not used.
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