Rev 3 to Reg Guide 01.134,task DG-1068, Medical Evaluation of Licensed Personnel at NppsML20217E478 |
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Issue date: |
03/31/1998 |
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From: |
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
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To: |
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References |
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TASK-*****, TASK-RE REGGD-01.134, REGGD-1.134, NUDOCS 9803310053 |
Download: ML20217E478 (4) |
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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 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 ML20195J1021999-06-30030 June 1999 Rev 3 to Reg Guide 8.13,task DG-8014, Instructions Re Prenatal Radiation Exposure ML20207H3291999-05-31031 May 1999 Rev 12 to Reg Guide 1.147, Inservice Insp Code Case Acceptability,Asme Section Xi,Div 1 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 ML20195F5591999-05-30030 May 1999 Rev 31 to Reg Guide 01.085, Materials Code Case Acceptability ASME Section Iii,Division 1 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 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 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 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 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 ML20236V8731998-08-31031 August 1998 for Comment Issue of Draft Reg Guide DG-4006, Demonstrating Compliance W/Radiological Criteria for License Termination ML20238E7751998-08-31031 August 1998 Reg Guide 03.071 (Draft Was Issued as DG-3013), Nuclear Criticality Safety Stds for Fuels & Matl Facilities 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 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 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 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 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 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 ML20217Q2081998-04-30030 April 1998 Rev 2 to Reg Guide 4.7, General Site Suitability Criteria for Nuclear Power Stations 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 ML20198D6371997-12-31031 December 1997 for Comment Issue of Draft Reg guide,DG-1071, Std Format & Content for Post-Shutdown Decommissioning Activities Rept 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 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 ML20198L6011997-10-31031 October 1997 Rev 3 to Reg Guide 5.44, Perimeter Intrusion Alarm Sys. (Draft Was DG-5007) 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 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 ML20198F7571997-09-30030 September 1997 Reg Guide 01.172, Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants ML20198F7621997-09-30030 September 1997 Reg Guide 01.171, Software Unit Testing 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 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 Regulatory Guide 01.1691997-09-30030 September 1997 Configuration Mgt Plans for Digital Computer Software Used in Safety Sys of Nuclear Power Plants 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 ML20217R0761997-08-31031 August 1997 Reg Guide 3.70, Use of Fixed Neutron Absorbers at Fuels & Matls Facilities ML20148Q8051997-06-30030 June 1997 for Comment Issue of Draft Reg Guide DG-1064, Approach for Plant-Specific,Risk-Informed Decisionmaking:Graded Quality Assurance ML20141G2721997-06-30030 June 1997 for Comment Issue of Draft Reg Guide DG-1062, Approach for Plant-Specific,Risk-Informed,Decisionmaking: Inservice Testing 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 ML20141G3081997-06-30030 June 1997 for Comment Issue of Draft Reg Guide,Task DG-1065, Approach for Plant-Specific,Risk-Informed Decisionmaking: Technical Specifications ML20140G2751997-06-30030 June 1997 for Comment Issue of Draft Reg Guide 1067, Decommissioning of Nuclear Power Reactors 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 ML20148B1641997-05-31031 May 1997 Draft Rev 12 to Reg Guide 01.147, Inservice Inspection Code Case Acceptability,Asme Section Xi,Division 1 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 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 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 ML20195J1021999-06-30030 June 1999 Rev 3 to Reg Guide 8.13,task DG-8014, Instructions Re Prenatal Radiation Exposure ML20207H3291999-05-31031 May 1999 Rev 12 to Reg Guide 1.147, Inservice Insp Code Case Acceptability,Asme Section Xi,Div 1 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 ML20195F5591999-05-30030 May 1999 Rev 31 to Reg Guide 01.085, Materials Code Case Acceptability ASME Section Iii,Division 1 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 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 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 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 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 ML20236V8731998-08-31031 August 1998 for Comment Issue of Draft Reg Guide DG-4006, Demonstrating Compliance W/Radiological Criteria for License Termination ML20238E7751998-08-31031 August 1998 Reg Guide 03.071 (Draft Was Issued as DG-3013), Nuclear Criticality Safety Stds for Fuels & Matl Facilities 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 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 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 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 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 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 ML20217Q2081998-04-30030 April 1998 Rev 2 to Reg Guide 4.7, General Site Suitability Criteria for Nuclear Power Stations 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 ML20198D6371997-12-31031 December 1997 for Comment Issue of Draft Reg guide,DG-1071, Std Format & Content for Post-Shutdown Decommissioning Activities Rept 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 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 ML20198L6011997-10-31031 October 1997 Rev 3 to Reg Guide 5.44, Perimeter Intrusion Alarm Sys. (Draft Was DG-5007) 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 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 ML20198F7571997-09-30030 September 1997 Reg Guide 01.172, Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants ML20198F7621997-09-30030 September 1997 Reg Guide 01.171, Software Unit Testing 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 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 Regulatory Guide 01.1691997-09-30030 September 1997 Configuration Mgt Plans for Digital Computer Software Used in Safety Sys of Nuclear Power Plants 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 ML20217R0761997-08-31031 August 1997 Reg Guide 3.70, Use of Fixed Neutron Absorbers at Fuels & Matls Facilities ML20140G2751997-06-30030 June 1997 for Comment Issue of Draft Reg Guide 1067, Decommissioning of Nuclear Power Reactors ML20141G2721997-06-30030 June 1997 for Comment Issue of Draft Reg Guide DG-1062, Approach for Plant-Specific,Risk-Informed,Decisionmaking: Inservice Testing 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 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 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 "". |
Text
U.S. NUCLEAR REGULATORY COMMISSION Revision 3 March 1998 C
g[ mow) REGULATORY GUIDE
- OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.134 (Draft issued as DG-1068)
MEDICAL EVALUATION OF LICENSED PERSONNEL AT NUCLEAR POWER PLANTS A. INTRODUCTION documentation to the NRC upon its request. He facili-ty licensee must retain this documentation as long as In 10 CFR Part 55, " Operators' Licenses," Sec- the individual functions as an operator or senior tions 55.31,"llow To Apply,"and 55.57," Renewal of operator.
Licenses," require that each initial or renewal applica- . . .
. . This guide describes a method acceptable to the tion for an operator or senior operator license contam a .
. . NRC staff for providing the m. f.ormation needed by the certification of medical condition and. . general health as . .
staff foi its evaluation of the medical qualifications of specified in Subpart C," Medical Requirements,"of 10 rinidal rmnew I paatomsenimopa-apphcan CFR Part 55. Sections 55.33," Disposition of an Initial ator licenses for nuclear power plants and for providing Application,".and 55.57 state that the initial or renewal notification to the NRC of an incapacitating disability applications for these licenses will be approved if, O among other things, the applicant's medical condition and general health will not cause operational errors that The information collections contained in this regu-endanger public health and safety. In 10 CFR 55.53, latory guide are covered by the requirements of 10 CFR
" Conditions of Licenses," Paragraph (i) requires the li- Part 55, which were approved by the Office of Manage-censee to have a medical examination biennially (i.e., ment and Budget, approval number 3150-0018. The every 2 years).. ,
NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information un-Section 55.25,"Incapacitatm.n Because of Disabil- less it displays a currently valid OM B control number.
ity or lilness, is concerned with an operator or senior operator who becomes incapacitated because of a men. IL DISCUSSION tal or physical condition that might cause impaired In Subpart C, " Medical Requirements," of 10 judgment or motor coordination.
CFR Part S5, Section 55.23," Certification," requires Section 55.27,"Documeritation," requires that the certification that a physician has examined the appli-facility licensee document and maintain medical quali- cant in accordance with NRC's regulatory guidance.
fications data, test results, and each operator's medical Form NRC-396," Certification of Medical Examina-history for the current license period and provide this tion by Facility Licensee," must be completed by an UsMtc Rid'1AlnRY GlqDis The guides are issued in the following ten broad divis* ors' Regulatory Guides are leeued to desuibe and rnake available to the public such erforma-tion as enethods acooptable to the NRC staff for ernplemerw6ng specche parts of the Cor* 1. Power Readors O Products .
rrweseon a regulations techniques used by the etaff inevalualmo specfhe problems or pos- 2 Research and fest Fleactors 7 Tansportat on i tulated accidents and data needed by the NRC staff an its review of apphcations for per- 3 Fuels and Materiais Faalities 8 Occupational Health rv wtt ed r r i t in 6 ena and F tart action G r will be acceptable il they orovide a bes* for the fmdmgs requisite to the esuance or con-The guide was issued att ru d a on a received from the public Cor* r) Br's otti e of fm
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' issued guides may a4so be purchased from the National Technecalirformstson Serwce on Written commeras may be submitted to the Rules Review and Desctives Brancts DFIPS a stanoin0 order bests Details on this servios may be obtamed by wrmng NTIS. 5265 Port ADM, U S. Nuo6 ear Regulatory Commissiort Washingtort DC 20555-0001. Royal Road. Spnnghend, VA 22101, 7
9003310053 980331 PDR REGGD / d' E {c' 01.134 R PDR f 'b ' of )/gn'h'"
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authorized representative of the facility licensee and tablishing minimum health requirements should aid must certify that a physician has conducted the medi-in more uniform medical evaluations. Ilowever,it is cal examination of the applicant as required by 10 necessary to recognize that, although it is the physi-CFR 55.21. The physician should have determined cian's responsibility to identify and evaluate any po-that the examince's medical condition and general tentially disqualifying medical conditions, the NRC health will not adversely alfect the performance of as- makes the final determination of the applicant's med-signed operator job duties or cause operational errors ical fitness.
endangering public health and safety. The intent of Nothing in ANSI /ANS-3.4-1996 or this guide these requirements is to have the facility beensee cer- should be construed to mean that such matters as an lify the health of its operators. individual's reading habits, political or religious be-The facility licensee is expected to maintain the liefs, or attitudes on social, economic, or political is-records on operators or senior operators that may be sues should be investigated or judged.
requested and reviewed by the NRC. Therefore,10 C. REGULATORY POSITION CFR 55.27 requires the f acility licensee to document and maintain the medical qualifications data, test re- The requirements contained in ANSI /
suits, and each operator's medical history. In addi- ANS-3.4-1996, " Medical Certification and Monitor-tion,10 CFR 55.27 requires the facility licensee to rc~ ing of Personnel Requiring Operator Licenses for Nu-tain each operator's medical history for the current clear Power Plants," provide methods acceptable to the }
NRC staff for determining the medical qualifications of )
license period and provide that information to the NRC on request. applicants for initial or renewal operator or senior oper-ator licenses svith the following exceptions to the There are two instances in which medical infor-standard. .
mation must be sent to the N RC One is when a condi-tional license based on medical evidence is requested in regard to criteria 2 and 3 of the standard's Sec-under the provisions of 10 CFR 55.23(b) and tion 5.3.5, " Cardiovascular," the examining physician 55.33(b). The second instance is when a licensed in- should have the flexibility to use medical judgment re-dividual has become mentally or physically unable to garding asymmetric peripheral pulses and pulse rates perform job duties. In this case, the facility licensee out of the specified range.
must notify the NRC within 30 days af ter learning of in regard to the standard's Section 5.3.6,"Labora-the diagnosis, if a conditional license is requested, j tory," whether to perform liver function tests should be the facility licensee must forward the medical evi. subject to the medical judgment of the examining dencc on Form NRC-396. This documentation is re.
quired by 10 CFR 55.27 to be maintained by the facility. D. IMPLEMENTATION An American National Standard developed by . . . . l The purpose of this section is to provide m. forma-the American Nuclear Seciety, ANSI /
t.mn to ap% cants and licensees about the NRC staff's ANS-3.4-1996, " Medical Certification and Moni- ,
Pl ans for using this regulatory guide.
toring of Personnel Requiring Operator Licenses for Nuclear Power Plants,"t prcscribes minimum re- Except in those cases in which an applicant or li-quirements necessary to determine that the medical censee proposes an acceptable alternative method for condition and general health of nuclear reactor opera- complying with specified portions of the NRC's regu-l tors will not cause operational errors. The criteria lations, the methods described in this guide reflecting l
presented in this standard provide an examining phy- public comments will be used in evaluating the part of sician a basis for determining whether a potentially an application for initial or renewal operator or senior disqualifying abnormal health condition exists. Es- operator licenses that is submitted on NRC Form 396,
" Certification of Medicai Examination by Facility Li-ICnpics may be obtained from the Arnerican Nuclear Society,5s5 North Kensington Avenue,l.a Grange Park,Ilknois 60525. censec."
Ol 1.134 - 2
VALUFJIMPACT ANALYSIS
/] A separate value/irnpact analysis has not been prepared for this regulatory guide. A value/
(j impact analysis was included in the regulatory analysis for the amendments to 10 CFR Part S5 that was published on March 25,1987. A copy of the regulatory analysis was placed in the N RC Public Document Room at that time. This regulatory analysis is also appropriate to Revi-sion 3 of Regulatory Guide 1.134. A copy of the regulatory analysis is available forinspection 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.
'J Printed on recycled paper
- O Federal Recycling Program 1.134 - 3
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UNITED STATES FIRST CLASS Mall NUCLEAR REGULATORY COMMISSION POSTAGE AND FEES PAID US WASHINGTON, DC 20555-0001 .
pggylT NO G 67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 120555064215 2 IS"11*
fhr$h5foJ & REC 0 ADS MGMT 00CUMENT CONTA.0L DE K IWFN-P117 DC 20555 WASHINGTON O
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