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Category:Regulatory Guide
MONTHYEARML24038A3102024-04-30030 April 2024 Rev 1 Dedication of Commercial-Grade Items for Use in Nuclear Power Plants ML23263A9972024-02-0202 February 2024 Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors ML23286A2512024-02-0202 February 2024 Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23 ML23286A2682024-02-0202 February 2024 Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23) ML23286A2862024-02-0202 February 2024 Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23 ML23286A2822024-02-0202 February 2024 Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23 ML23286A2782024-02-0202 February 2024 Watermarked - DG-5075 - Cyber Security 10-13-23 ML23194A1942023-08-31031 August 2023 Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs ML22165A0722023-02-28028 February 2023 DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2 ML23012A2422023-02-28028 February 2023 DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants ML23018A2932023-02-16016 February 2023 Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy) Regulatory Guide 5.892022-11-0101 November 2022 Rev.0, Fitness-for-Duty Programs for Commercial Power Reactor and Category I Special Nuclear Material Licensees ML22067A0142022-03-31031 March 2022 Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI ML22048B8222022-02-18018 February 2022 DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ML22040A0822021-10-30030 October 2021 Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components ML21167A3512021-06-0101 June 2021 Rev 5 Final Watermarked for ACRS ML21092A1512021-05-0505 May 2021 Rev. 4 ACRS Version ML21092A1342021-05-0505 May 2021 Rev. 2 ACRS Version ML21181A2492021-04-30030 April 2021 Watermark for ACRS Fc Meeting RG 1.9 Rev 5 ML21006A3372021-04-0101 April 2021 Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities ML21006A3352021-04-0101 April 2021 DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities ML20168A8832021-04-0101 April 2021 DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants ML21083A2892021-02-28028 February 2021 Draft for Acrs Review ML21048A4482021-02-17017 February 2021 Rev. 2 ML21011A2312021-01-31031 January 2021 Rev 4 (Draft for ACRS Fc Review on 2-3-21) ML20120A6312021-01-31031 January 2021 Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367) ML20120A6292021-01-31031 January 2021 Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368) ML20120A6332021-01-31031 January 2021 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366) ML20120A6272021-01-31031 January 2021 ASME Code Cases Not Approved for Use, Revision 7 (DG-1369) ML21012A1972021-01-12012 January 2021 a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0 ML20183A4232020-12-31031 December 2020 Draft Regulatory Guide DG-1361 (Proposed Rev. 2 to Reg. Guide 1.89), Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities2020-12-31031 December 2020 Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20238B8732020-12-29029 December 2020 Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20282A2992020-12-0404 December 2020 Regulatory Analysis for DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals ML20282A2982020-12-0404 December 2020 DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals ML20210M0472020-12-0101 December 2020 Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping ML20231A8352020-11-30030 November 2020 Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants ML20231A8562020-11-30030 November 2020 Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants ML20307A0462020-11-0202 November 2020 Draft for ACRS Public Meeting, RG 1.200, R3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20210M0442020-10-28028 October 2020 Regulatory Analysis: Draft Regulatory Guide DG-1288 - an Approach for Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping (Proposed Revision 2 of Regulatory Guide 1.178, Dated September 2003) ML20154K5842020-09-17017 September 2020 Results of Periodic Review of Regulatory Guide (RG) 1.78 ML20182A7882020-08-31031 August 2020 DG 1373 for RG 1.240 - Fresh and Spent Fuel Pool Criticality Analyses ML20055G8232020-08-0707 August 2020 DG 1363 for Proposed Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation Regulatory Guide 3.152020-07-31031 July 2020 Regulatory Guide 3.15. Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant Regulatory Guide 1.2362020-07-30030 July 2020 Draft for ACRS Review ML20119A6142020-04-28028 April 2020 Response to Comments for RG 1.236 for ACRS ML20105A4672020-04-14014 April 2020 Memo to OCA - for Revision 1 of Regulatory Guide 8.39, Release of Patients Administered Radioactive Material ML20099F0262020-04-0707 April 2020 Public Comment Resolution Table for DG 1341 (Regulatory Guide (RG) 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses, Rev. 2 ML19206A4892020-02-0606 February 2020 Draft Regulatory Guide DG-1287, an Approach for Plant-Specific, risk-Informed Decisionmaking: Technical Specifications ML19116A0772019-08-31031 August 2019 Draft Regulatory Guide DG-5040, Urine Specimen Collection and Test Results Review Under 10 CFR Part 26, Fitness for Duty Programs. 2024-04-30
[Table view]Some use of "" in your query was not closed by a matching "". Category:Draft
MONTHYEARML23263A9972024-02-0202 February 2024 Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors ML23286A2512024-02-0202 February 2024 Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23 ML23286A2682024-02-0202 February 2024 Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23) ML23286A2782024-02-0202 February 2024 Watermarked - DG-5075 - Cyber Security 10-13-23 ML23286A2822024-02-0202 February 2024 Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23 ML23286A2862024-02-0202 February 2024 Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23 ML23194A1942023-08-31031 August 2023 Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs ML23012A2422023-02-28028 February 2023 DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants ML22165A0722023-02-28028 February 2023 DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2 ML23018A2932023-02-16016 February 2023 Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy) ML22067A0142022-03-31031 March 2022 Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI ML22048B8222022-02-18018 February 2022 DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ML22040A0822021-10-30030 October 2021 Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components ML21181A2492021-04-30030 April 2021 Watermark for ACRS Fc Meeting RG 1.9 Rev 5 ML21006A3372021-04-0101 April 2021 Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities ML21006A3352021-04-0101 April 2021 DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities ML20168A8832021-04-0101 April 2021 DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants ML20120A6272021-01-31031 January 2021 ASME Code Cases Not Approved for Use, Revision 7 (DG-1369) ML20120A6312021-01-31031 January 2021 Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367) ML20120A6332021-01-31031 January 2021 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366) ML20120A6292021-01-31031 January 2021 Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368) ML20183A4232020-12-31031 December 2020 Draft Regulatory Guide DG-1361 (Proposed Rev. 2 to Reg. Guide 1.89), Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants ML20210M0472020-12-0101 December 2020 Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping ML20231A8562020-11-30030 November 2020 Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants ML20231A8352020-11-30030 November 2020 Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants ML20307A0462020-11-0202 November 2020 Draft for ACRS Public Meeting, RG 1.200, R3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20210M0442020-10-28028 October 2020 Regulatory Analysis: Draft Regulatory Guide DG-1288 - an Approach for Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping (Proposed Revision 2 of Regulatory Guide 1.178, Dated September 2003) ML20055G8232020-08-0707 August 2020 DG 1363 for Proposed Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation NUREG-1575, Rev. 2, Multi-Agency Radiation Survey and Site Investigation Manual (Marssim), Draft for Public Comment2020-05-31031 May 2020 NUREG-1575, Rev. 2, Multi-Agency Radiation Survey and Site Investigation Manual (Marssim), Draft for Public Comment ML21008A5742020-05-31031 May 2020 Appendices to Marssim Revision 2 Draft for Public Comment ML20119A6142020-04-28028 April 2020 Response to Comments for RG 1.236 for ACRS ML19206A4892020-02-0606 February 2020 Draft Regulatory Guide DG-1287, an Approach for Plant-Specific, risk-Informed Decisionmaking: Technical Specifications ML19116A0772019-08-31031 August 2019 Draft Regulatory Guide DG-5040, Urine Specimen Collection and Test Results Review Under 10 CFR Part 26, Fitness for Duty Programs. ML19045A4352019-05-31031 May 2019 Draft Regulatory Guide DG-1356, Guidance for Implementation of 10 CFR 50.59, Changes, Test and Experiments. ML16172A2402019-04-30030 April 2019 Draft Regulatory Guide (DG)-1283, Safety Related Concrete Structures for Nuclear Power Plants ML17258A5792019-04-30030 April 2019 DG-1284, Anchoring Components and Structural Supports in Concrete ML19042A1722019-03-31031 March 2019 Draft Regulatory Guide (DG)-7010, Leakage Tests on for Shipment of Radioactive Material ML18158A3032019-01-31031 January 2019 Draft Regulatory Guide DG-1352, Instrument Sensing Lines ML18087A1692018-10-31031 October 2018 Draft Regulatory Guide DG-4019, Environmental Dosimetry - Performance Specifications, Testing, and Data Analysis ML18087A1672018-10-31031 October 2018 DG-4019 Reg Analysis ML18016A1292018-08-31031 August 2018 Draft Regulatory Guide (DG)-5061, Cyber Security Programs for Nuclear Power Reactors. ML18232A5002018-08-31031 August 2018 Marked Up Draft Regulatory Guide for Cyber Security Programs for Nuclear Power Reactors. (Rdlso - Rg 5.71 Rev. 0 Vs DG-5061) ML18234A0962018-08-31031 August 2018 Draft Regulatory Guide DG-5057, Special Nuclear Material Control and Accounting System for Non-Fuel Cycle Facilities ML17353A7272018-06-30030 June 2018 Draft Regulatory Guide (DG) 1349, Standard Format and Content for Post-Shutdown Decommissioning Activities Report. ML18086A6902018-06-30030 June 2018 Draft Regulatory Guide DG-1351, Dispositioning of Technical Specifications That Are Insufficient to Ensure Plant Safety ML17348B4852018-06-30030 June 2018 Draft Regulatory Guide (DG) 1348, Assuring the Availability of Funds for Decommissioning Production or Utilization Facilities. ML17347A7942018-06-30030 June 2018 Draft Regulatory Guide (DG) 1347, Decommissioning of Nuclear Power Reactors. ML16091A2672018-02-28028 February 2018 Draft Regulatory Guide (DG)-1329, Proposed Revision 4 to Regulatory Guide Rg 1.8, Qualification and Training of Personnel for Nuclear Power Plants. Regulatory Guide 1.2322018-02-27027 February 2018 Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors ML16165A2982017-07-31031 July 2017 Draft Guide (DG) - 1291 Evaluating Deviations and Reporting Defects and Noncompliance Under 10 CFR Part 21 2024-02-02
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SU.S. NUCLEAR REGULATORY COMMISSION February 1997 o _ OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 Draft DG-1068 DRAFT REGULATORY GUIDE
Contact:
D.L. McCain (301)415-1065 DRAFT REGULATORY GUIDE DG-1068 (Proposed Revision 3 to Regulatory Guide 1.134)
MEDICAL EVALUATION OF LICENSED PERSONNEL AT NUCLEAR POWER PLANTS A. INTRODUCTION In 10 CFR Part 55, "Operators' Licenses," Sections 55.31, "and 55.57, "Renewal of Licenses," require that each initia o application for an operator or senior operator license contain a cer t of medical condition and general health as specified in Subpart C, "Me l ements," of 10 CFR Part
- 55. Sections 55.33, "Disposition of an Initi Ap; tion," and 55.57 state that the initial or renewal applications for the e s will be approved if, among other things, the applicant's medical cond ý a general health will not cause operational errors that endanger publi *hnd safety. In 10 CFR 55.53, "Conditions of Licenses," Parag r 0 ulres the licensee to have a medical examination biennially (i.e., ev 2 ars).
Section 55.25, "Incapa i cause of Disability or Illness," is concerned with an operator or senior LFra9 who becomes incapacitated because of a mental or physical condition that might use impaired judgment or motor coordination.
Section 55.2 "Documentation," requires that the facility licensee document and maintain med ifications data, test results, and each operator's medical history fo r u t license period and provide this documentation to the NRC upon it st. The facility licensee must retain this documentation as long as the in P nctions as an operator or senior operator.
This regulatory guide is being issued in draft form to involve the public in the early stages of the development of a regulatory position in this area. It has not received complete staff review and does not represent an official NRC staff position.
Public comments are being solicited on the draft guide (including any implementation schedule) and its associated regulatory analysis or value/impact statement. Comments should be accompanied by appropriate supporting data. Written comments may be submitted to the Rules Review and Directives Branch, DFIPS, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Copies of comments received may be examined at the NRC Public Document Room, 2120 L Street NW., Washington, DC. Comments will be most helpful if received by March 17, 1997.
Requests for single copies of draft or active regulatory guides (which may be reproduced) or for placement on an automatic distribution list for single copies of future draft guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Distribution and Mail Services Section, or by fax to (301)415-2260.
This guide describes a method acceptable to the NRC staff for providing the information needed by the staff for its evaluation of the medical qualifications of applicants for initial or renewal operator or senior operator licenses for nuclear power plants and for providing notification to the NRC of an incapacitating disability or illness.
Regulatory guides are issued to describe and make available to the public such information as methods acceptable to the NRC staff for implementing specific parts of the Commission's regulations, techniques used by the staff in evaluating specific problems or postulated accidents, and guidance to applicants. Regulatory guides are not substitutes for regulations, and compliance with regulatory guides is not required.
Regulatory guides are issued in draft form for public comment to involve the public in the early stages of developing the regulatory positions. Draft regulatory guides have not received complete staff review and do not represent official NRC staff positions.
The information collections contained in this draft regulatory guide are covered by the requirements of 10 CFR Part 55, which were approved by the Office of Management and Budget, approval number 3150-0018. The NRC may not conduct, or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number.
B. DISCUSSION In Subpart C, "Medical Requirements," of 10 CFR Part 55, Section 55.23, "Certification," requires certification that a physician has examined the applicant in accordance with NRC's regulatory guidance. Form NRC-396, "Certification of Medical Examination by Facility Licensee," must be completed by an authorized representative of the facility licensee and must certify that a physician has conducted the medical examination of the applicant as required by 10 CFR 55.21. The physician should have determined that the examinee's medical condition and general health will not adversely affect the performance of assigned operator job duties or cause operational errors endangering public h'alth and safety. The intent of these requirements is to have the facility licensee certify the health of its operators.
The facility licensee is expected to maintain the records on operators or senior operators that may be requested and reviewed by the NRC. Therefore, 2
10 CFR 55.27 requires the facility licensee to document and maintain the medical qualifications data, test results, and each operator's medical history. In addition, 10 CFR 55.27 requires the facility licensee to retain each operator's medical history for the current license period and provide that information to the NRC on request.
There are two instances in which medical information must be sent to the NRC. One is when a conditional license based on medical evidence is requested under the provisions of 10 CFR 55.23(b) and 55.33(b). The second instance is when a licensed individual has become mentally or physically unable to perform job duties. In this case, the facility licensee must notify the NRC within 30 days after learning of the diagnosis. If a conditional license is requested, the facility licensee must forward the medical evidence on Form NRC-396. This documentation is required by 10 CFR 55.27 to be maintained by the facility.
An American National Standard developed by the American Nuclear Society, ANSI/ANS-3.4-1996, "Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants,' prescribes minimum requirements necessary to determine that the medical condition and general health of nuclear reactor operators will not cause operational errors. The criteria presented in this standard provide an examining physician a basis for determining whether a potentially disqualifying abnormal health condition exists. Establishing minimum health requirements should aid in more uniform medical evaluations. However, it is necessary to recognize that, although it is the physician's responsibility to identify and evaluate any potentially disqualifying medical conditions, the NRC makes the final determination of the applicant's medical fitness.
Nothing in ANSI/ANS-3.4-1996 or this guide should be construed to mean that such matters as an individual's reading habits, political or religious beliefs, or attitudes on social, economic, or political issues should be investigated or judged.
C. REGULATORY POSITION The requirements contained in ANSI/ANS-3.4-1996, "Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power
'Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.
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Plants,' provide methods acceptable to the NRC staff for determining the medical qualifications of applicants for initial or renewal operator or senior operator licenses.
D. IMPLEMENTATION The purpose of this section is to provide information to applicants and licensees about the NRC staff's plans for using this regulatory guide.
This draft guide has been released to encourage public participation in its development. Except in those cases in which an applicant or licensee proposes an acceptable alternative method for complying with specified portions of the NRC's regulations, the methods to be described in the final guide reflecting public comments will be used in evaluating the part of an application for initial or renewal operator or senior operator licenses that is submitted on NRC Form 396, "Certification of Medical Examination by Facility Licensee."
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VALUE/IMPACT ANALYSIS A separate value/impact analysis has not been prepared for this draft regulatory guide. A value/impact analysis was included in the regulatory analysis for the amendments to 10 CFR Part 55 that was published on March 25, 1987. A copy of the regulatory analysis was placed in the NRC Public Document Room at that time. This regulatory analysis is also appropriate to Revision 3 of Regulatory Guide 1.134. A copy of the regulatory analysis is available for inspection and copying for a fee at the NRC Public Document Room, 2120 L Street NW., Washington, DC; the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; phone (202)634-3273; fax (202)634-3343.
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FIRST CLASS MAIL UNITED STATES POSTAGE AND FEES PAID NUCLEAR REGULATORY COMMISSION USNRC WASHINGTON, DC 20555-0001 PERMIT NO. G-67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300