RIS 2004-04, Use of Code Cases N-588, N-640, and N-641 in Developing Pressure-Temperature Operating Limits: Difference between revisions

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{{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001April 5, 2004NRC REGULATORY ISSUE SUMMARY 2004-04:USE OF CODE CASES N-588, N-640, AND N-641 IN DEVELOPINGPRESSURE-TEMPERATURE OPERATING LIMITS
{{#Wiki_filter:UNITED STATES
                            NUCLEAR REGULATORY COMMISSION
                        OFFICE OF NUCLEAR REACTOR REGULATION
                                WASHINGTON, D.C. 20555-0001 April 5, 2004 NRC REGULATORY ISSUE SUMMARY 2004-04:
    USE OF CODE CASES N-588, N-640, AND N-641 IN DEVELOPING
                PRESSURE-TEMPERATURE OPERATING LIMITS


==ADDRESSEES==
==ADDRESSEES==
All holders of construction permits or operating licenses for nuclear power reactors except thosewho have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.
All holders of construction permits or operating licenses for nuclear power reactors except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.


==INTENT==
==INTENT==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)to inform addressees of the NRC position on the use of American Society of Mechanical Engineers (ASME) Code Cases N-588, N-640, and N-641 in developing reactor pressure vesselpressure-temperature limits using ASME Section XI, Appendix G.
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
 
to inform addressees of the NRC position on the use of American Society of Mechanical Engineers (ASME) Code Cases N-588, N-640, and N-641 in developing reactor pressure vessel pressure-temperature limits using ASME Section XI, Appendix G. This RIS does not require any action or written response on the part of an addressee.
This RIS does not requireany action or written response on the part of an addressee.


==BACKGROUND==
==BACKGROUND==
Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix G, requires thatpressure-temperature (P-T) limits be established for reactor pressure vessels (RPVs) during normal operating and hydrostatic or leak rate testing conditions. Further, Appendix G of
Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix G, requires that pressure-temperature (P-T) limits be established for reactor pressure vessels (RPVs) during normal operating and hydrostatic or leak rate testing conditions. Further, Appendix G of
10 CFR Part 50 specifies that the requirements for these limits are based on the application of evaluation procedures given in Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (Code).Since ASME Section XI, Appendix G, was first developed, significant advances in fracturemechanics and the analysis of reactor vessel integrity have been achieved. In general, advancements in knowledge are promulgated as ASME Code Cases, for example, Code Cases N-588, N-640, and N-641, which provide alternatives to existing Code requirements for developing pressure-temperature operating limits. These alternatives to the Appendix G
10 CFR Part 50 specifies that the requirements for these limits are based on the application of evaluation procedures given in Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (Code).
methodology have been proposed and accepted as appropriate alternatives and are documented in Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME
Since ASME Section XI, Appendix G, was first developed, significant advances in fracture mechanics and the analysis of reactor vessel integrity have been achieved. In general, advancements in knowledge are promulgated as ASME Code Cases, for example, Code Cases N-588, N-640, and N-641, which provide alternatives to existing Code requirements for developing pressure-temperature operating limits. These alternatives to the Appendix G
Section XI, Division 1."  The provisions of ASME Code Cases N-588, N 640, and N-641 that are applicable to P-T limit curve development were incorporated into ASME Code Section XI,
methodology have been proposed and accepted as appropriate alternatives and are documented in Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME
Appendix G in the 1998 edition through 2000 addenda which is the edition and addenda codified in 10 CFR 50.55a, effective October 28, 2002 (67 FR 60520). Code Case N-588 provides an alternative procedure for assuming axially oriented referencedefects in all axial welds and base metal and circumferentially oriented reference defects in all circumferential welds. Code Case N-640 allows the use of K
Section XI, Division 1. The provisions of ASME Code Cases N-588, N 640, and N-641 that are applicable to P-T limit curve development were incorporated into ASME Code Section XI,
IC ( which is the material toughnessproperty measured in terms of stress intensity factor, K
Appendix G in the 1998 edition through 2000 addenda which is the edition and addenda codified in 10 CFR 50.55a, effective October 28, 2002 (67 FR 60520).
i, which will lead to nonductile crackpropagation) instead of K
Code Case N-588 provides an alternative procedure for assuming axially oriented reference defects in all axial welds and base metal and circumferentially oriented reference defects in all circumferential welds. Code Case N-640 allows the use of KIC ( which is the material toughness property measured in terms of stress intensity factor, Ki, which will lead to nonductile crack propagation) instead of KIA (which is the critical value of the stress intensity factor, KI, for crack arrest as a function of temperature) in the development of pressure-temperature limit curves.
IA (which is the critical value of the stress intensity factor, K
I, for crackarrest as a function of temperature) in the development of pressure-temperature limit curves.


Code Case N-641 presents alternative procedures for calculating pressure-temperature relationships and low-temperature overpressure protection (LTOP) system effective temperatures and allowable pressures. These procedures take into account alternative fracture toughness properties, circumferential and axial reference flaws, and plant-specific LTOP enable temperature calculations.
Code Case N-641 presents alternative procedures for calculating pressure-temperature relationships and low-temperature overpressure protection (LTOP) system effective temperatures and allowable pressures. These procedures take into account alternative fracture toughness properties, circumferential and axial reference flaws, and plant-specific LTOP enable temperature calculations.


==SUMMARY OF ISSUE==
==SUMMARY OF ISSUE==
Historically, the NRC staff has taken the position that licensees are only permitted to useeditions and addenda of Appendix G to Section XI of the ASME Code incorporated into a facility's licensing basis (i.e., through their defined facility inservice inspection program) for thepurpose of meeting the requirements for Appendix G to 10 CFR Part 50. For an example, if a licensee wished to use a less conservative methodology based on the use of an ASME Code Case in order to relax requirements for RPV P-T limit curve development, the licensee needed to obtain an exemption from the requirements of Appendix G to 10 CFR Part 50.Recently, the NRC re-evaluated the relationship between 10 CFR part 50 appendix G and 10CFR 50.55a. In summary:Licensees may use the provisions of any edition and addenda of ASME Code SectionXI, Appendix G incorporated into 10 CFR 50.55a for RPV P-T limit curve development, up to and including the most recently incorporated edition and addenda, without the need for an exemption.Use of NRC approved ASME Code Cases (e.g., N-588, N-640, and N-641) inconjunction with earlier versions of the ASME Code endorsed in 10 CFR 50.55a may also be used for the development of P-T limit curves without the need for an exemption.However, changing the P-T limit curve methodology specified in the licensee
Historically, the NRC staff has taken the position that licensees are only permitted to use editions and addenda of Appendix G to Section XI of the ASME Code incorporated into a facilitys licensing basis (i.e., through their defined facility inservice inspection program) for the purpose of meeting the requirements for Appendix G to 10 CFR Part 50. For an example, if a licensee wished to use a less conservative methodology based on the use of an ASME Code Case in order to relax requirements for RPV P-T limit curve development, the licensee needed to obtain an exemption from the requirements of Appendix G to 10 CFR Part 50.
's TechnicalSpecifications or modifying a facility
 
's pressure-temperature limit report (PTLR)methodology requires NRC staff approval since this is a license amendment.
Recently, the NRC re-evaluated the relationship between 10 CFR part 50 appendix G and 10
CFR 50.55a. In summary:
        Licensees may use the provisions of any edition and addenda of ASME Code Section XI, Appendix G incorporated into 10 CFR 50.55a for RPV P-T limit curve development, up to and including the most recently incorporated edition and addenda, without the need for an exemption.
 
        Use of NRC approved ASME Code Cases (e.g., N-588, N-640, and N-641) in conjunction with earlier versions of the ASME Code endorsed in 10 CFR 50.55a may also be used for the development of P-T limit curves without the need for an exemption.
 
        However, changing the P-T limit curve methodology specified in the licensees Technical Specifications or modifying a facilitys pressure-temperature limit report (PTLR)
          methodology requires NRC staff approval since this is a license amendment.


==BACKFIT DISCUSSION==
==BACKFIT DISCUSSION==
This RIS does not require any action or written response and, therefore, is not a backfit under10 CFR 50.109. Consequently, the staff did not perform a backfit analysis. SMALL BUSINESS REGULATORY ENFORCEMENT FAIRNESS ACTThe NRC has determined that this action is not subject to the Small Business RegulatoryEnforcement Fairness Act of 1996.
This RIS does not require any action or written response and, therefore, is not a backfit under
10 CFR 50.109. Consequently, the staff did not perform a backfit analysis. SMALL BUSINESS REGULATORY ENFORCEMENT FAIRNESS ACT
The NRC has determined that this action is not subject to the Small Business Regulatory Enforcement Fairness Act of 1996.


===FEDERAL REGISTER NOTIFICATION===
===FEDERAL REGISTER NOTIFICATION===
A notice of opportunity for public comment on this RIS was not published in the FederalRegister because the RIS is informational.
A notice of opportunity for public comment on this RIS was not published in the Federal Register because the RIS is informational.


===PAPERWORK REDUCTION ACT STATEMENT===
===PAPERWORK REDUCTION ACT STATEMENT===
This RIS does not contain information collections and, therefore, is not subject to therequirements of Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).Public Protection NotificationThe NRC may not conduct or sponsor, and a person is not required to respond to, aninformation collection unless the requesting document displays a currently valid OMB control number. If you have any questions about this matter, please contact the person listed below or theappropriate Office of Nuclear Regulatory Regulation (NRR) project manager for a specific vendor or industry group as listed on the NRC Web site./RA/William D. Beckner, Chief Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor RegulationTechnical contact:Nihar K. Ray, NRR301-415-2643 E-mail: nkr@nrc.govAttachment: List of Recently Issued Regulatory Issue Summaries  
This RIS does not contain information collections and, therefore, is not subject to the requirements of Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).
                                  Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, an information collection unless the requesting document displays a currently valid OMB control number.
 
If you have any questions about this matter, please contact the person listed below or the appropriate Office of Nuclear Regulatory Regulation (NRR) project manager for a specific vendor or industry group as listed on the NRC Web site.
 
/RA/
                                              William D. Beckner, Chief Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation Technical contact:     Nihar K. Ray, NRR
                      301-415-2643 E-mail: nkr@nrc.gov Attachment: List of Recently Issued Regulatory Issue Summaries
 
ML040920323 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML040920323.wpd OFFICE EMCB:DE            Tech Editor    SC:EMCB:DE BC:EMCB:DE          OES:IROB:DIPM
  NAME    NKRay            PKleene        SMCoffin        WHBateman    CPetrone DATE    03/01/2004      02/25/2004      03/02/2004      03/08/2004    03/01/2004 OFFICE  OGC              OGC            OCIO            CRGR          SC:OES:IROB:DIPM
  NAME    CMHolzle        RWeisman        BCSt.Mary        Cader *email  TReis DATE    03/26/2004      03/23/2004      03/25/2004      03/09/2004      /      /2004 OFFICE  C:IROB:DIPM      OE
  NAME    WDBeckner        CNoland DATE    04/05/2004      04/01/2004        /    /2004    /    /2004    /      /2004
 
Attachment LIST OF RECENTLY ISSUED
                                  NRC REGULATORY ISSUE SUMMARIES
_____________________________________________________________________________________
Regulatory Issue                                            Date of Summary No.                  Subject                      Issuance      Issued to
_____________________________________________________________________________________
2004-03          Risk-informed Approach For Post-          03/02/2004 All holders of operating licenses Fire Safe-Shutdown Associated                        for nuclear power reactors, except Circuit Inspections                                  those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.
 
2004-02          Deferral of Active Regulation of          02/23/2004 All holders of materials licenses Ground-Water Protection at in Situ                    for uranium and thorium recovery Leach Uranium Extraction                              facilities.
 
Facilities
2004-01          Method for Estimating Effective            02/17/2004 All U.S. Nuclear Regulatory Dose Equivalent from External                        Commission (NRC) licensees.
 
Radiation Sources Using Two Dosimeters
2003-18          Use of NEI 99-01, Methodology            10/08/2003 All holders of operating licenses for Development of Emergency                          for nuclear power reactors and Action Levels, Revision 4, Dated                    licensees that have permanently January 2003                                          ceased operations and have certified that fuel has been permanently removed from the reactor vessel.


ML040920323DOCUMENT NAME: C:\ORPCheckout\FileNET\ML040920323.wpdOFFICEEMCB:DETech EditorSC:EMCB:DEBC:EMCB:DEOES:IROB:DIPMNAMENKRayPKleeneSMCoffinWHBatemanCPetroneDATE03/01/200402/25/2004 03/02/200403/08/200403/01/2004OFFICEOGCOGCOCIOCRGRSC:OES:IROB:DIPMNAMECMHolzleRWeismanBCSt.MaryCader *emailTReisDATE03/26/200403/23/200403/25/200403/09/2004      /        /2004OFFICEC:IROB:DIPMOENAMEWDBecknerCNolandDATE04/05/200404/01/2004    /      /2004    /      /2004    /      /2004
2003-17          Complying with 10 CFR 35.59,              10/03/2003 All U.S. Nuclear Regulatory Recentness of Training, for                        Commission (NRC) medical-use Board-certified Individuals Whose                    licensees and NRC master Training and Experience Were                          materials license medical-use Completed More than 7 Years Ago                      permittees.
______________________________________________________________________________________OL = Operating License


CP = Construction PermitAttachment LIST OF RECENTLY ISSUEDNRC REGULATORY ISSUE SUMMARIES
Note:             NRC generic communications may be received in electronic format shortly after they are issued by subscribing to the NRC listserver as follows:
_____________________________________________________________________________________Regulatory Issue  Date of Summary No.      Subject  IssuanceIssued to
                  To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following command in the message portion:
_____________________________________________________________________________________2004-03Risk-informed Approach For Post-Fire Safe-Shutdown Associated Circuit Inspections03/02/2004All holders of operating licensesfor nuclear power reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.2004-02Deferral of Active Regulation ofGround-Water Protection at in SituLeach Uranium Extraction Facilities02/23/2004All holders of materials licensesfor uranium and thorium recovery facilities.2004-01Method for Estimating EffectiveDose Equivalent from External Radiation Sources Using Two Dosimeters02/17/2004All U.S. Nuclear RegulatoryCommission (NRC) licensees.2003-18Use of NEI 99-01," Methodologyfor Development of Emergency Action Levels," Revision 4, DatedJanuary 200310/08/2003All holders of operating licensesfor nuclear power reactors and licensees that have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.2003-17Complying with 10 CFR 35.59,"Recentness of Training," forBoard-certified Individuals Whose Training and Experience Were Completed More than 7 Years Ago10/03/2003All U.S. Nuclear RegulatoryCommission (NRC) medical-use licensees and NRC master materials license medical-use permittees.Note:NRC generic communications may be received in electronic format shortly after they areissued by subscribing to the NRC listserver as follows:To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the followingcommand in the message portion:subscribe gc-nrr firstname lastname
                                    subscribe gc-nrr firstname lastname
______________________________________________________________________________________
OL = Operating License CP = Construction Permit
}}
}}


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Revision as of 01:16, 24 November 2019

Use of Code Cases N-588, N-640, and N-641 in Developing Pressure-Temperature Operating Limits
ML040920323
Person / Time
Issue date: 04/05/2004
From: Beckner W
NRC/NRR/DIPM/IROB
To:
Ray, Nihar NRR/DE/EMCB, 415-2643
References
TAC MC1593 RIS-04-004
Download: ML040920323 (5)
v • d • e


UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001 April 5, 2004 NRC REGULATORY ISSUE SUMMARY 2004-04:

USE OF CODE CASES N-588, N-640, AND N-641 IN DEVELOPING

PRESSURE-TEMPERATURE OPERATING LIMITS

ADDRESSEES

All holders of construction permits or operating licenses for nuclear power reactors except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.

INTENT

The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)

to inform addressees of the NRC position on the use of American Society of Mechanical Engineers (ASME) Code Cases N-588, N-640, and N-641 in developing reactor pressure vessel pressure-temperature limits using ASME Section XI, Appendix G. This RIS does not require any action or written response on the part of an addressee.

BACKGROUND

Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix G, requires that pressure-temperature (P-T) limits be established for reactor pressure vessels (RPVs) during normal operating and hydrostatic or leak rate testing conditions. Further, Appendix G of

10 CFR Part 50 specifies that the requirements for these limits are based on the application of evaluation procedures given in Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code (Code).

Since ASME Section XI, Appendix G, was first developed, significant advances in fracture mechanics and the analysis of reactor vessel integrity have been achieved. In general, advancements in knowledge are promulgated as ASME Code Cases, for example, Code Cases N-588, N-640, and N-641, which provide alternatives to existing Code requirements for developing pressure-temperature operating limits. These alternatives to the Appendix G

methodology have been proposed and accepted as appropriate alternatives and are documented in Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME

Section XI, Division 1. The provisions of ASME Code Cases N-588, N 640, and N-641 that are applicable to P-T limit curve development were incorporated into ASME Code Section XI,

Appendix G in the 1998 edition through 2000 addenda which is the edition and addenda codified in 10 CFR 50.55a, effective October 28, 2002 (67 FR 60520).

Code Case N-588 provides an alternative procedure for assuming axially oriented reference defects in all axial welds and base metal and circumferentially oriented reference defects in all circumferential welds. Code Case N-640 allows the use of KIC ( which is the material toughness property measured in terms of stress intensity factor, Ki, which will lead to nonductile crack propagation) instead of KIA (which is the critical value of the stress intensity factor, KI, for crack arrest as a function of temperature) in the development of pressure-temperature limit curves.

Code Case N-641 presents alternative procedures for calculating pressure-temperature relationships and low-temperature overpressure protection (LTOP) system effective temperatures and allowable pressures. These procedures take into account alternative fracture toughness properties, circumferential and axial reference flaws, and plant-specific LTOP enable temperature calculations.

SUMMARY OF ISSUE

Historically, the NRC staff has taken the position that licensees are only permitted to use editions and addenda of Appendix G to Section XI of the ASME Code incorporated into a facilitys licensing basis (i.e., through their defined facility inservice inspection program) for the purpose of meeting the requirements for Appendix G to 10 CFR Part 50. For an example, if a licensee wished to use a less conservative methodology based on the use of an ASME Code Case in order to relax requirements for RPV P-T limit curve development, the licensee needed to obtain an exemption from the requirements of Appendix G to 10 CFR Part 50.

Recently, the NRC re-evaluated the relationship between 10 CFR part 50 appendix G and 10 CFR 50.55a. In summary:

 Licensees may use the provisions of any edition and addenda of ASME Code Section XI, Appendix G incorporated into 10 CFR 50.55a for RPV P-T limit curve development, up to and including the most recently incorporated edition and addenda, without the need for an exemption.

 Use of NRC approved ASME Code Cases (e.g., N-588, N-640, and N-641) in conjunction with earlier versions of the ASME Code endorsed in 10 CFR 50.55a may also be used for the development of P-T limit curves without the need for an exemption.

 However, changing the P-T limit curve methodology specified in the licensees Technical Specifications or modifying a facilitys pressure-temperature limit report (PTLR)

methodology requires NRC staff approval since this is a license amendment.

BACKFIT DISCUSSION

This RIS does not require any action or written response and, therefore, is not a backfit under

10 CFR 50.109. Consequently, the staff did not perform a backfit analysis. SMALL BUSINESS REGULATORY ENFORCEMENT FAIRNESS ACT

The NRC has determined that this action is not subject to the Small Business Regulatory Enforcement Fairness Act of 1996.

FEDERAL REGISTER NOTIFICATION

A notice of opportunity for public comment on this RIS was not published in the Federal Register because the RIS is informational.

PAPERWORK REDUCTION ACT STATEMENT

This RIS does not contain information collections and, therefore, is not subject to the requirements of Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).

Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, an information collection unless the requesting document displays a currently valid OMB control number.

If you have any questions about this matter, please contact the person listed below or the appropriate Office of Nuclear Regulatory Regulation (NRR) project manager for a specific vendor or industry group as listed on the NRC Web site.

/RA/

William D. Beckner, Chief Reactor Operations Branch Division of Inspection Program Management Office of Nuclear Reactor Regulation Technical contact: Nihar K. Ray, NRR

301-415-2643 E-mail: nkr@nrc.gov Attachment: List of Recently Issued Regulatory Issue Summaries

ML040920323 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML040920323.wpd OFFICE EMCB:DE Tech Editor SC:EMCB:DE BC:EMCB:DE OES:IROB:DIPM

NAME NKRay PKleene SMCoffin WHBateman CPetrone DATE 03/01/2004 02/25/2004 03/02/2004 03/08/2004 03/01/2004 OFFICE OGC OGC OCIO CRGR SC:OES:IROB:DIPM

NAME CMHolzle RWeisman BCSt.Mary Cader *email TReis DATE 03/26/2004 03/23/2004 03/25/2004 03/09/2004 / /2004 OFFICE C:IROB:DIPM OE

NAME WDBeckner CNoland DATE 04/05/2004 04/01/2004 / /2004 / /2004 / /2004

Attachment LIST OF RECENTLY ISSUED

NRC REGULATORY ISSUE SUMMARIES

_____________________________________________________________________________________

Regulatory Issue Date of Summary No. Subject Issuance Issued to

_____________________________________________________________________________________

2004-03 Risk-informed Approach For Post- 03/02/2004 All holders of operating licenses Fire Safe-Shutdown Associated for nuclear power reactors, except Circuit Inspections those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.

2004-02 Deferral of Active Regulation of 02/23/2004 All holders of materials licenses Ground-Water Protection at in Situ for uranium and thorium recovery Leach Uranium Extraction facilities.

Facilities

2004-01 Method for Estimating Effective 02/17/2004 All U.S. Nuclear Regulatory Dose Equivalent from External Commission (NRC) licensees.

Radiation Sources Using Two Dosimeters

2003-18 Use of NEI 99-01, Methodology 10/08/2003 All holders of operating licenses for Development of Emergency for nuclear power reactors and Action Levels, Revision 4, Dated licensees that have permanently January 2003 ceased operations and have certified that fuel has been permanently removed from the reactor vessel.

2003-17 Complying with 10 CFR 35.59, 10/03/2003 All U.S. Nuclear Regulatory Recentness of Training, for Commission (NRC) medical-use Board-certified Individuals Whose licensees and NRC master Training and Experience Were materials license medical-use Completed More than 7 Years Ago permittees.

Note: NRC generic communications may be received in electronic format shortly after they are issued by subscribing to the NRC listserver as follows:

To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following command in the message portion:

subscribe gc-nrr firstname lastname

______________________________________________________________________________________

OL = Operating License CP = Construction Permit


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