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Category:REGULATORY GUIDE (REG GUIDE)
MONTHYEARML20217D7721999-10-31031 October 1999 Rev 1 to Reg Guide 08.015, Acceptable Programs for Respiratory Protection ML20217D7821999-09-30030 September 1999 Reg Guide 01.181, Content of UFSAR in Accordance with 10CFR50.71(e) ML20212B3121999-09-17017 September 1999 Draft Reg Guide DG-1053 (Previous Draft Was DG-1025), Calculational & Dosimetry Methods for Determining Pressure Vessel Neutron Fluence. with 990917 Transmittal Memo ML20210T3131999-08-31031 August 1999 For Comment Issue of Draft Rev 3 to Reg Guide 1.149, Nuclear Power Plant Simulation Facilities for Use in Operator Training & License Examinations ML20195J1021999-06-30030 June 1999 Rev 3 to Reg Guide 8.13,task DG-8014, Instructions Re Prenatal Radiation Exposure ML20209D1291999-06-30030 June 1999 For Comment Issue of Draft Reg Guide DG-3014,(proposed Rev 1 to Reg Guide 3.66), Std Format & Content of Financial Assurance Mechanisms Required for Decommissioning Under 10CFR30,40,70 & 72 ML20195F7901999-05-31031 May 1999 Rev 31 to Reg Guide 1.84,task DG-1048, Design & Fabrication Code Case Acceptability,Asme Section Iii,Div 1 ML20207H3291999-05-31031 May 1999 Rev 12 to Reg Guide 1.147, Inservice Insp Code Case Acceptability,Asme Section Xi,Div 1 ML20195F5591999-05-30030 May 1999 Rev 31 to Reg Guide 01.085, Materials Code Case Acceptability ASME Section Iii,Division 1 ML20204E6271999-03-31031 March 1999 For Comment Issue of Draft Rev 1 to Reg Guide 01.054 (DG-1076), Svc Level I,Ii & III Protective Coatings Applied to Nuclear Power Plants ML20204C5301999-03-31031 March 1999 For Comment Issue of 2nd Proposed Rev 3 of RG 1.8, Qualification & Training of Personnel for Nuclear Power Plants ML20203B8061999-01-31031 January 1999 Reg Guide 01.179, Std Format & Content of License Termination Plans for Nuclear Power Reactors. Draft Was Issued as DG-1078 ML20206U2191999-01-31031 January 1999 Rev 1 to Reg Guide 03.054,task DG-3010, Spent Fuel Heat Generation in Independent Spent Fuel Storage Installation ML20199A4681998-12-31031 December 1998 For Comment Issue of Draft Reg Guide,Task DG-1074, SG Tube Integrity ML20154S5611998-09-30030 September 1998 Reg Guide 01.178, Approach for Plant-Specific Risk-Informed Decisionmaking Inservice Insp of Piping ML20154S6081998-09-30030 September 1998 Reg Guide 01.178 (Draft Issued as DG-1063), Approach for Plant-Specific Risk-Informed Decisionmaking Inservice Insp of Piping. Issued for Trial Use ML20151U4991998-08-31031 August 1998 Reg Guide 1.175, Approach for Plant-Specific,Risk-Informed Decisionmaking Inservice Testing ML20151U5071998-08-31031 August 1998 Reg Guide 1.177, Approach for Plant-Specific,Risk-Informed Decisionmaking:Tss ML20151U5131998-08-31031 August 1998 Reg Guide 1.176, Approach for Plan-Specific,Risk-Informed Decisionmaking:Graded Quality Assurance ML20238E7751998-08-31031 August 1998 Reg Guide 03.071 (Draft Was Issued as DG-3013), Nuclear Criticality Safety Stds for Fuels & Matl Facilities ML20236V8731998-08-31031 August 1998 For Comment Issue of Draft Reg Guide DG-4006, Demonstrating Compliance W/Radiological Criteria for License Termination ML20154M5751998-07-31031 July 1998 For Comment Issue of Draft Reg Guide DG-8022 (Proposed Rev to Reg Guide 8.15), Acceptable Programs for Respiratory Protection ML20237B9081998-07-31031 July 1998 Reg Guide 01.174,draft Issued as DG-1061, Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to Licensing Basis ML20236X7851998-07-31031 July 1998 For Comment Issue of Draft Reg guide,DG-4005,(supersedes DG-4002), Preparation of Supplemental Environmental Reports for Application to Renew Nuclear Power Plant Operating Licenses ML20236T6581998-07-31031 July 1998 For Comment Issue of Draft Reg Guide DG-1069, Fire Protection Program for Nuclear Power Plants During Decommissioning & Permanent Shutdown ML20217Q2081998-04-30030 April 1998 Rev 2 to Reg Guide 4.7, General Site Suitability Criteria for Nuclear Power Stations ML20217Q4291998-04-30030 April 1998 For Comment Issue of Draft Reg Guide DG-1078, Std Format & Content of License Termination Plans for Nuclear Power Reactor ML20217E4781998-03-31031 March 1998 Rev 3 to Reg Guide 01.134,task DG-1068, Medical Evaluation of Licensed Personnel at Npps ML20198N2861998-01-31031 January 1998 For Comment Issue of Draft Reg Guide DG-3013, Nuclear Criticality Safety Stds for Fuels & Matl Facilities ML20198D8781997-12-31031 December 1997 For Comment Issue of Draft Reg Guide DG-5008 (Proposed Rev 2 of RG 5.62), Reporting of Safeguards Events ML20198D6371997-12-31031 December 1997 For Comment Issue of Draft Reg guide,DG-1071, Std Format & Content for Post-Shutdown Decommissioning Activities Rept ML20198L6011997-10-31031 October 1997 Rev 3 to Reg Guide 5.44, Perimeter Intrusion Alarm Sys. (Draft Was DG-5007) ML20198K1571997-10-31031 October 1997 for Comment Issue of Draft Reg Guide DG-1063, Approach for Plant-Specific,Risk-Informed Decisionmaking:Inservice Insp of Piping ML20199D2061997-10-17017 October 1997 Rev 1 to Reg Guide 3.46,(Task Fp), Std Format & Content of License Applications,Including Environ Repts for in Situ U Solution Extraction ML20211J3411997-09-30030 September 1997 For Comment Issue of Proposed Rev 1 to Draft RG 3.54, Sf Heat Generation in Independent Spent Fuel Storage Installation ML20198F7621997-09-30030 September 1997 Reg Guide 01.171, Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants ML20198F7571997-09-30030 September 1997 Reg Guide 01.172, Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants Regulatory Guide 01.1691997-09-30030 September 1997 Configuration Mgt Plans for Digital Computer Software Used in Safety Sys of Nuclear Power Plants ML20216G5861997-09-30030 September 1997 For Comment Issue of Draft Reg Guide,Task DG 1060, Financial Accounting Standards Board (Fasb) Standards for Decommissioning Cost Accounting ML20198F7731997-09-30030 September 1997 Reg Guide 01.168, Verification Validation Reviews & Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants ML20198F7851997-09-30030 September 1997 Reg Guide 01.173, Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Sys of Npp ML20217R0761997-08-31031 August 1997 Reg Guide 3.70, Use of Fixed Neutron Absorbers at Fuels & Matls Facilities ML20141G3081997-06-30030 June 1997 For Comment Issue of Draft Reg Guide,Task DG-1065, Approach for Plant-Specific,Risk-Informed Decisionmaking: Technical Specifications ML20148Q8051997-06-30030 June 1997 For Comment Issue of Draft Reg Guide DG-1064, Approach for Plant-Specific,Risk-Informed Decisionmaking:Graded Quality Assurance ML20141G2821997-06-30030 June 1997 For Comment Issue of Draft Reg Guide DG-1061, Approach for Using PRA in Risk-Informed Decisions on Plant-Specific Changes to Current Licensing Basis ML20141G2721997-06-30030 June 1997 For Comment Issue of Draft Reg Guide DG-1062, Approach for Plant-Specific,Risk-Informed,Decisionmaking: Inservice Testing ML20140G2751997-06-30030 June 1997 For Comment Issue of Draft Reg Guide 1067, Decommissioning of Nuclear Power Reactors ML20140G8881997-05-31031 May 1997 For Comment Issue of Rev 31 to Draft Reg Guide DG-1049, Matls Code Case Acceptability ASME Section Iii,Div 1 ML20140G9911997-05-31031 May 1997 For Comment Issue of Draft Rev 31 to Reg Guide 01.084, Task DG-1048, Design & Fabrication Code Case Acceptability, ASME Section Iii,Div 1 ML20141G8741997-05-31031 May 1997 Errata to Reg Guide 8.39, Release of Patients Administered Radioactive Matls. Equations 2 & 3 Misstated When Guide Issued in April 1997.Parentheses Omitted from Denominator of Both Equations 1999-09-30
[Table view]Some use of "" in your query was not closed by a matching "". Category:REGULATORY GUIDES & STD. REVIEW PLANS-TEXT
MONTHYEARML20217D7721999-10-31031 October 1999 Rev 1 to Reg Guide 08.015, Acceptable Programs for Respiratory Protection ML20217D7821999-09-30030 September 1999 Reg Guide 01.181, Content of UFSAR in Accordance with 10CFR50.71(e) ML20212B3121999-09-17017 September 1999 Draft Reg Guide DG-1053 (Previous Draft Was DG-1025), Calculational & Dosimetry Methods for Determining Pressure Vessel Neutron Fluence. with 990917 Transmittal Memo ML20210T3131999-08-31031 August 1999 For Comment Issue of Draft Rev 3 to Reg Guide 1.149, Nuclear Power Plant Simulation Facilities for Use in Operator Training & License Examinations ML20195J1021999-06-30030 June 1999 Rev 3 to Reg Guide 8.13,task DG-8014, Instructions Re Prenatal Radiation Exposure ML20209D1291999-06-30030 June 1999 For Comment Issue of Draft Reg Guide DG-3014,(proposed Rev 1 to Reg Guide 3.66), Std Format & Content of Financial Assurance Mechanisms Required for Decommissioning Under 10CFR30,40,70 & 72 ML20195F7901999-05-31031 May 1999 Rev 31 to Reg Guide 1.84,task DG-1048, Design & Fabrication Code Case Acceptability,Asme Section Iii,Div 1 ML20207H3291999-05-31031 May 1999 Rev 12 to Reg Guide 1.147, Inservice Insp Code Case Acceptability,Asme Section Xi,Div 1 ML20195F5591999-05-30030 May 1999 Rev 31 to Reg Guide 01.085, Materials Code Case Acceptability ASME Section Iii,Division 1 ML20204E6271999-03-31031 March 1999 For Comment Issue of Draft Rev 1 to Reg Guide 01.054 (DG-1076), Svc Level I,Ii & III Protective Coatings Applied to Nuclear Power Plants ML20204C5301999-03-31031 March 1999 For Comment Issue of 2nd Proposed Rev 3 of RG 1.8, Qualification & Training of Personnel for Nuclear Power Plants ML20203B8061999-01-31031 January 1999 Reg Guide 01.179, Std Format & Content of License Termination Plans for Nuclear Power Reactors. Draft Was Issued as DG-1078 ML20206U2191999-01-31031 January 1999 Rev 1 to Reg Guide 03.054,task DG-3010, Spent Fuel Heat Generation in Independent Spent Fuel Storage Installation ML20199A4681998-12-31031 December 1998 For Comment Issue of Draft Reg Guide,Task DG-1074, SG Tube Integrity ML20154S5611998-09-30030 September 1998 Reg Guide 01.178, Approach for Plant-Specific Risk-Informed Decisionmaking Inservice Insp of Piping ML20154S6081998-09-30030 September 1998 Reg Guide 01.178 (Draft Issued as DG-1063), Approach for Plant-Specific Risk-Informed Decisionmaking Inservice Insp of Piping. Issued for Trial Use ML20151U4991998-08-31031 August 1998 Reg Guide 1.175, Approach for Plant-Specific,Risk-Informed Decisionmaking Inservice Testing ML20151U5071998-08-31031 August 1998 Reg Guide 1.177, Approach for Plant-Specific,Risk-Informed Decisionmaking:Tss ML20151U5131998-08-31031 August 1998 Reg Guide 1.176, Approach for Plan-Specific,Risk-Informed Decisionmaking:Graded Quality Assurance ML20238E7751998-08-31031 August 1998 Reg Guide 03.071 (Draft Was Issued as DG-3013), Nuclear Criticality Safety Stds for Fuels & Matl Facilities ML20236V8731998-08-31031 August 1998 For Comment Issue of Draft Reg Guide DG-4006, Demonstrating Compliance W/Radiological Criteria for License Termination ML20154M5751998-07-31031 July 1998 For Comment Issue of Draft Reg Guide DG-8022 (Proposed Rev to Reg Guide 8.15), Acceptable Programs for Respiratory Protection ML20237B9081998-07-31031 July 1998 Reg Guide 01.174,draft Issued as DG-1061, Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to Licensing Basis ML20236X7851998-07-31031 July 1998 For Comment Issue of Draft Reg guide,DG-4005,(supersedes DG-4002), Preparation of Supplemental Environmental Reports for Application to Renew Nuclear Power Plant Operating Licenses ML20236T6581998-07-31031 July 1998 For Comment Issue of Draft Reg Guide DG-1069, Fire Protection Program for Nuclear Power Plants During Decommissioning & Permanent Shutdown ML20217Q2081998-04-30030 April 1998 Rev 2 to Reg Guide 4.7, General Site Suitability Criteria for Nuclear Power Stations ML20217Q4291998-04-30030 April 1998 For Comment Issue of Draft Reg Guide DG-1078, Std Format & Content of License Termination Plans for Nuclear Power Reactor ML20217E4781998-03-31031 March 1998 Rev 3 to Reg Guide 01.134,task DG-1068, Medical Evaluation of Licensed Personnel at Npps ML20198N2861998-01-31031 January 1998 For Comment Issue of Draft Reg Guide DG-3013, Nuclear Criticality Safety Stds for Fuels & Matl Facilities ML20198D8781997-12-31031 December 1997 For Comment Issue of Draft Reg Guide DG-5008 (Proposed Rev 2 of RG 5.62), Reporting of Safeguards Events ML20198D6371997-12-31031 December 1997 For Comment Issue of Draft Reg guide,DG-1071, Std Format & Content for Post-Shutdown Decommissioning Activities Rept ML20198L6011997-10-31031 October 1997 Rev 3 to Reg Guide 5.44, Perimeter Intrusion Alarm Sys. (Draft Was DG-5007) ML20198K1571997-10-31031 October 1997 for Comment Issue of Draft Reg Guide DG-1063, Approach for Plant-Specific,Risk-Informed Decisionmaking:Inservice Insp of Piping ML20199D2061997-10-17017 October 1997 Rev 1 to Reg Guide 3.46,(Task Fp), Std Format & Content of License Applications,Including Environ Repts for in Situ U Solution Extraction ML20211J3411997-09-30030 September 1997 For Comment Issue of Proposed Rev 1 to Draft RG 3.54, Sf Heat Generation in Independent Spent Fuel Storage Installation ML20198F7621997-09-30030 September 1997 Reg Guide 01.171, Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants ML20198F7571997-09-30030 September 1997 Reg Guide 01.172, Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants Regulatory Guide 01.1691997-09-30030 September 1997 Configuration Mgt Plans for Digital Computer Software Used in Safety Sys of Nuclear Power Plants ML20216G5861997-09-30030 September 1997 For Comment Issue of Draft Reg Guide,Task DG 1060, Financial Accounting Standards Board (Fasb) Standards for Decommissioning Cost Accounting ML20198F7731997-09-30030 September 1997 Reg Guide 01.168, Verification Validation Reviews & Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants ML20198F7851997-09-30030 September 1997 Reg Guide 01.173, Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Sys of Npp ML20217R0761997-08-31031 August 1997 Reg Guide 3.70, Use of Fixed Neutron Absorbers at Fuels & Matls Facilities ML20141G3081997-06-30030 June 1997 For Comment Issue of Draft Reg Guide,Task DG-1065, Approach for Plant-Specific,Risk-Informed Decisionmaking: Technical Specifications ML20148Q8051997-06-30030 June 1997 For Comment Issue of Draft Reg Guide DG-1064, Approach for Plant-Specific,Risk-Informed Decisionmaking:Graded Quality Assurance ML20141G2821997-06-30030 June 1997 For Comment Issue of Draft Reg Guide DG-1061, Approach for Using PRA in Risk-Informed Decisions on Plant-Specific Changes to Current Licensing Basis ML20141G2721997-06-30030 June 1997 For Comment Issue of Draft Reg Guide DG-1062, Approach for Plant-Specific,Risk-Informed,Decisionmaking: Inservice Testing ML20140G2751997-06-30030 June 1997 For Comment Issue of Draft Reg Guide 1067, Decommissioning of Nuclear Power Reactors ML20140G8881997-05-31031 May 1997 For Comment Issue of Rev 31 to Draft Reg Guide DG-1049, Matls Code Case Acceptability ASME Section Iii,Div 1 ML20140G9911997-05-31031 May 1997 For Comment Issue of Draft Rev 31 to Reg Guide 01.084, Task DG-1048, Design & Fabrication Code Case Acceptability, ASME Section Iii,Div 1 ML20141G8741997-05-31031 May 1997 Errata to Reg Guide 8.39, Release of Patients Administered Radioactive Matls. Equations 2 & 3 Misstated When Guide Issued in April 1997.Parentheses Omitted from Denominator of Both Equations 1999-09-30
[Table view]Some use of "" in your query was not closed by a matching "". |
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U.S. NUCLEAR REGULATORY COMMISSION February 1997 P
0FFICE OF NUCLEAR REGULATORY RESEARCH Division 1 o
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Draft DG-1068 f
DRAFT REGULATORY GUIDE j
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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 55.3,
ow W Apply," and 55.57, " Renewal of Licenses," require that each initial application for an operator or senior operator license contain a cer of medical condition and general health as specified in Subpart C, "Me 1
ements," of 10 CFR Part
- 55. Sections 55.33, " Disposition of an Initi ion," and 55.57 state that the initial or renewal applications for th e s will be approved if, among other things, the applicant's medical cond a
general health will not cause (G
operational errors that endanger publ nd safety.
In 10 CFR 55.53, 4
4
" Conditions of Licenses," Paragr res the licensee to have a medical examination biennially (i.e., ev 2
ars).
Section 55.25, "Incap ause of Disability or Illness," is concerned with an operato, or senior a r 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 me ifications data, test results, and each operator's medical history for t license period and provide this documentation to the NRC upon it st The facility licensee must retain this documentation as long as the i nctions as an operator or senior operator.
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This regulatory guide is being issued in draf t 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 r.ce;ved by March 17, 1997.
Requests for single copies of draf t or active regulatory guides (which may be reproduced) or for placement on an automatic distribution list for
{
sirigle copies of future drsft guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, DC
=
20$55, Attention: Distribution and Niail Services Section, or by f ax to (301)415 2260.
9702200378 970220 PDR REGGD 01.134 R PDR
l This guide describes a method acceptable to the NRC staff for providing the information needed by the staff for its evaluation of the medical l
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 collecticn 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 h3C-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 examiriation 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 affet t the performance of assigned operator job duties or cause operational errors endangering public h ulth 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
i i
l
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 licenses 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,"2 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 i
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 l'
' 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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3 VALUE/ IMPACT ANALYSIS A separate value/ impact analysis has not been prepared for this draft i
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 I
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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