United States Nuclear Regulatory Commission - Protecting People and the Environment

Reactor License Renewal Guidance Documents

These documents can be found below (if available) or by using NRC's on-line document retrieval system ADAMS located in the NRC Library. Should you need assistance in locating documents of interest, we encourage you to contact the reference staff in our Public Document Room.

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In 2010 the following license renewal guidance documents were updated: the “Generic Aging Lessons Learned (GALL) Report,” and the “Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants.” NUREG-1950, “Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800” was updated in 2011. NUREG-1950 supersedes NUREG-1832, “Analysis of Public Comments on the Revised License Renewal Guidance Documents,” and NUREG-1833, “Technical Bases for Revision to the License Renewal Guidance Documents.”

For additional information about the 2010 guidance document updates, see Guidance, Updates, Schedule and Background.

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Generic Aging Lessons Learned (GALL)

The purpose of the GALL Report is to provide the technical basis for the Standard Review Plan for License Renewal. GALL contains the staff's generic evaluation of the existing plant programs and documents the technical basis for determining where existing programs are adequate without modification and where existing programs should be augmented for the extended period of operation. The evaluation results documented in the GALL report indicate that many of the existing programs are adequate to manage the aging effects for particular structures or components for license renewal without change. The GALL report also contains recommendations on specific areas for which existing programs should be augmented for license renewal.

Generic Aging Lessons Learned (GALL) Report, NUREG-1801

Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800, NUREG-1950

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Inspection Manual Chapters (IMCs) and Procedures (IPs)

The purpose of the IMCs and IPs is to guide the staff in conducting inspections to ensure that licensees meet the NRC's regulatory requirements:

  • IMC 2515, “Light-Water Reactor Inspection Program — Operations Phase,” provides guidance to NRC headquarters and regional office staff, as well as consultant personnel, regarding review and inspection activities to ensure the safe operation of light-water reactors, including post-approval site inspections associated with license renewal (see IP-71003, below).

  • IMC 2516, "Policy and Guidance for the License Renewal Inspection Programs," provides guidance to NRC headquarters and regional office staff, as well as consultant personnel, regarding review and inspection activities associated with an applicant's license renewal program.

  • IP-71002, "License Renewal Inspections," provides the procedures for inspecting and verifying the documentation, implementation, and effectiveness of the programs and activities associated with an applicant's license renewal program. For additional information, see Frequently Asked Questions on License Renewal of Nuclear Power Reactors (NUREG-1850).

  • IP-71003, "Post-Approval Site Inspection for License Renewal," provides the procedures for inspecting and verifying the completion of license renewal commitments and license conditions that have been added as part of the renewed license, and ensuring that selected aging management programs (AMPs) are implemented in accordance with the license renewal regulations. For additional information, see Frequently Asked Questions About License Renewal Inspection Procedure (IP) 71003.

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License Renewal Interim Staff Guidance (LR-ISG)

License renewal guidance documents, such as NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," Revision 2, NUREG-1801 and "Generic Aging Lessons Learned (GALL) Report," Revision 2, have been developed to enhance the license renewal application process. As lessons are learned during license renewal application reviews, it is expected that these guidance documents may need to be revised to capture new insights or to address emerging issues. To document these lessons learned, the NRC staff develops LR-ISG in accordance with LR-ISG Process, Revision 2, which involves stakeholders. LR-ISG improves the efficiency and effectiveness of the license renewal process by providing guidance to license renewal applicants and other interested stakeholders until that guidance can be incorporated into a license renewal guidance document revision. For more information, such as a list of the current LR-ISGs, please view the Web page for License Renewal Interim Staff Guidance.

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Regulatory Guide 1.188, Revision 1

Regulatory Guide 1.188, Revision 1, provides format and content for applications and endorses NEI 95-10, Rev 6. However, applicants may elect to use other suitable methods or approaches for satisfying the Rule's requirements and completing a license renewal application.

  • "Industry Guidelines for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule," NEI 95-10, provides potential applicants with guidelines for identifying the systems, structures, and components with the scope of 10 CFR Part 54 and their functions; identifying structures and components subject to aging management review; assuring that effect of aging are maintained, application of inspections for license renewal; identifying and resolving time-limited aging analyses; and identifying and evaluating exemptions containing time-limited aging analyses.

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Office Instructions (OIs)

The NRC Office of Nuclear Reactor Regulation (NRR)’s OI program defines the processes by which NRR staff and managers develop and maintain OIs and thereby improve NRR's efficiency and consistency in performing its various activities and functions. The pertinent license renewal OIs establish procedures for the license renewal application review process, define the roles and responsibilities of the staff organizations involved in a license renewal application review, and provide guidance for the consideration of environmental issues.

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Regulatory Guides (RGs)

The purpose of the RG is to provide guidance to licensees and applicants on implementing specific parts of the NRC's regulations, techniques used by the NRC staff in evaluating specific problems or postulated accidents, and data needed by the staff in its review of applications.

  • Standard Format and Content for Applications to Renew Nuclear Power Plant Operating License, Regulatory Guide 1.188, endorses the industry license renewal document NEI 95-10, Revision 6.
  • Preparation of Supplemental Environmental Reports for Applications To Renew Nuclear Power Plant Operating Licenses, Supplement 1 to Regulatory Guide 4.2, provides guidance on the format and content of an environmental report to be submitted as part of a license renewal application.

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Standard Review Plans (SRP)

The purpose of the SRP is to assure quality and uniformity of staff reviews and to present a well defined base from which to evaluate a licensee's application.

  • Standard Review Plan for License Renewal, NUREG-1800, incorporates by reference the Generic Aging Lessons Learned Report and Regulatory Guide 1.188.

  • Environmental Standard Review Plan, NUREG-1555, Operating License Renewal Supplement 1, provides guidance in implementing the 10 CFR Part 51, related to new site/plant applications and license renewal.

  • Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800, NUREG-1950

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Technical Reports in the NUREG Series (NUREGs)

Note – See all NUREGs for plant license renewal safety evaluation reports.

Document Identifier Title
NUREG-1412 "Foundation for the Adequacy of the Licensing Basis," describes the regulatory process that assures that any plant-specific licensing bases will provide reasonable assurance that the operation of nuclear power plants will not be inimical to the public health and safety to the end of the renewal period.
NUREG-1437 and plant supplements "Generic Environmental Impact Statement for License Renewal of Nuclear Plants," examines the possible environmental impacts that could occur as a result of renewing licenses of individual nuclear power plants under 10 CFR Part 54.
NUREG-1555 "Standard Review Plans for Environmental Reviews For Nuclear Power Plants," provides guidance to the staff in implementing provisions of 10 CFR 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions," related to new site/plant applications.
NUREG-1555, Supplement 1 "Standard Review Plans for Environmental Reviews For Nuclear Power Plants - Operating License Renewal," provides guidance to the staff in implementing provisions of 10 CFR 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions," related to reactor operating license renewals.
NUREG-1568 "License Renewal Demonstration Program: NRC Observations and Lessons Learned," is a summary of NRC staff's observations and lessons learned from nuclear plant site visits performed under the License Renewal Demonstration Program (LRDP). The LRDP was a program established by the NEI to assess the effectiveness of NEI 95-10.
NUREG-1611 "Aging Management of Nuclear Power Plant Containments for License Renewal," reconciles the technical information and agreements resulting from NUMARC/NRC industry report reviews and the in-service inspection requirements of Subsection IWE and IWL as promulgated in 10 CFR 5.55a for license renewal.
NUREG-1739 "Analysis of Public Comments on the Improved License Renewal Guidance Documents," contains the NRC staff's analysis of the stakeholders' comments on the license renewal guidance documents, which are Regulatory Guide-1.188, Standard Review Plan for License Renewal, Generic Aging Lessons Learned Report, and the NEI 95-10, Rev. 3.
NUREG-1800 "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," provides guidance to the NRC staff reviewers in performing safety reviews of applications to renew nuclear power plant licenses in accordance with 10 CFR Part 54.
NUREG-1801 "Generic Aging Lessons Learned (GALL) Report, Summary and Tabulation of Results," contains the NRC staff's generic evaluation of the existing plant programs and documents the technical basis for determining where existing programs are adequate without modification and where existing programs should be augmented for the extended period of operation.
NUREG-1832 "Analysis of Public Comments on the Revised License Renewal Guidance Documents," contains the NRC staff's analysis of the stakeholders' comments on the revised license renewal guidance documents 9/30/05)
NUREG-1833 "Technical Bases for Revision to the License Renewal Guidance Documents" contains the NRC staff explanation of technical changes to the SRP-LR (NUREG-1800) and the GALL Report (NUREG-1801) from Rev.0 to Rev.1 (10/28/05).
NUREG/CR-5382 Screening of Generic Safety Issues for License Renewal Considerations
NUREG/CR-6490
Vol. 1
Vol. 2 part 1
Vol. 2 part 2
"Nuclear Power Plant Generic Aging Lessons Learned (GALL)," contains the review results of the Nuclear Plant Aging Research Program and related information pertaining to nuclear power plant aging effects and plant impact.
NUREG/CR-6679 "Assessment of Age-Related Degradation of Structures and Passive Components for U.S. Nuclear Power Plants."
NUREG-1950 Disposition of Public Comments and Technical Bases for Changes in the License Renewal Guidance Documents NUREG-1801 and NUREG-1800

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NPAR Reports

Nuclear Plant Aging Research (NPAR) Reports is a collection of literature on mechanical, structural, and thermal-hydraulic components and systems providing a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors.

Document Identifier Title
BNL Tech Reports:
A-3270-11-26-84
Scoping Test on Containment Purge and Vent Seal Material
BNL Tech Reports:
A-3270-12-86
Aging and Life Extension Assessment Program (ALEAP) Systems Level Plan
BNL Tech Reports:
A-3270R-2-90
Interim Report - Aging Effects of Important Balance of Plant Systems in Nuclear Power Plants
BNL Tech Reports:
TR-3270-6-90
Maintenance Team Inspection Results: Insights Related to Plant Aging
BNL Tech Reports:
TR-3270-9-90
An Operational Assessment of the Babcock & Wilcox and Combustion Engineering Control Rod Drives
BNL Tech Reports:
A-3270-6-21-91
Degradation Modeling: Extensions and Applications
BNL Tech Reports:
EGG-SSRE-8972
Estimating Hazard Functions for Repairable Components
BNL Tech Reports:
EGG-SSRE-9017
User's Guide to PHAZE, a Computer Program for Parametric Hazard Function Estimation
BNL Tech Reports:
EGG-SSRE-9777
Isolation Valve Assessment (IVA) Software Version 3.10, User's Manual
BNL Tech Reports:
EGG-SSRE-9926
Evaluation of EPRI Draft Report NP-7065-Review of NRC/INEL Gate Valve Test Program
BNL Tech Reports:
EGG-SSRE-10039
An Evaluation of the Effects of Valve Body Erosion on Motor-Operated Valve Operability
BNL Tech Reports:
Letter Report
Summaries of Research Reports Submitted in Connection with the Nuclear Plant Aging Research (NPAR) Program
NUREG-1144, V3 Nuclear Plant Aging Research (NPAR) Program Plan, Status and Accomplishments, Rev. 2
NUREG/CP-0100 Proceedings of the International Nuclear Power Plant Aging Symposium
NUREG/CP-0105 Vol. 3 Proceedings of the Seventeenth Water Reactor Safety Information Meeting (aging session only)
NUREG/CR-2641
(ORNL/TM-8271)
The In-Plant Reliability Data Base for Nuclear Power Plant Components: Data Collection and Methodology Report
NUREG/CR-3154
(ORNL/TM 8647)
The In-Plant Reliability Data Base for Nuclear Power Plant Components: Interim Report - The Valve Component
NUREG/CR-4144
(PNL-5389)
Importance Ranking Based on Aging Consideration of Components Included in Probabilistic Risk Assessments
NUREG/CR-4279 V1
(PNL-5479)
Aging and Service Wear of Hydraulic and Mechanical Snubbers Used on Safety-Related Piping and Components of Nuclear Power Plants
NUREG/CR-4302 V1
(ORNL-6193)
Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants
NUREG/CR-4302 V2
(ORNL-6193)
Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants
NUREG/CR-4380
(ORNL-6226)
Evaluation of the Motor-Operated Valve Analysis and Test System (MOVATS) to Detect Degradation, Incorrect Adjustments, and Other Abnormalities in Motor Operated Valves
NUREG/CR-4597 V1
(ORNL-6282)
Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants, Vol. 1: Operating Experience and Failure Identification
NUREG/CR-4597 V2
(ORNL-6282)
Aging and Service Wear of Auxiliary Feedwater Pumps for PWR Nuclear Power Plants, Vol. 2: Aging Assessment and Monitoring Method Evaluations
NUREG/CR-4652
(ORNL/TM-10059)
Concrete Component Aging and Its Significance Relative to Extension of Nuclear Power Plants
NUREG/CR-4692
(ORNL/NOAC-233)
Operating Experience Review of Failures of Power Operated Relief Valves and Block Valves in Nuclear Power Plants
NUREG/CR-4731 V1
(EGG-2469)
Residual Life Assessment of Major Light Water Reactor Components, Vol. 1
NUREG/CR-4731 V2
(EGG-2469)
Residual Life Assessment of Major Light Water Reactor Components - Overview, Vol. 2
NUREG/CR-4747 V1
( EGG-2473)
An Aging Failure Survey of Light Water Reactor Safety Systems and Components, V1
NUREG/CR-4747 V2
( EGG-2473)
An Aging Failure Survey of Light Water Reactor Safety Systems and Components, V2
NUREG/CR-4819 V1 (ORNL/SUB/83-28915/4) Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants
NUREG/CR-4819 V2
(ORNL/TM-12038)
Aging and Service Wear of Solenoid-Operated Valves Used in Safety Systems of Nuclear Power Plants: Evaluation of Monitoring Methods
NUREG/CR-4967
(EGG-2514)
Nuclear Plant Aging Research on High Pressure Injection Systems
NUREG/CR-4977 V1
(EGG-2505 V1)
SHAG Test Series: Seismis Research on an Aged United States Gate Valve and on a Piping System in the Decommissioned Heissdampfreaktor (HDR): Summary, V1
NUREG/CR-4977 V2
(EGG-2505 V2)
SHAG Test Series: Seismis Research on an Aged United States Gate Valve and on a Piping System in the Decommissioned Heissdampfreaktor (HDR): Appendices, V2
NUREG/CR-5057
(PNL-6397)
Aging Mitigation and Improved Programs for Nuclear Service Diesel Generators
NUREG/CR-5159
(KEI-1559)
Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems
NUREG/CR-5248
(PNL-6701)
Prioritization of TIRALEX-Recommended Components for Further Aging Research
NUREG/CR-5314 V3
EGG-2562)
Life Assessment Procedures for Major LWR Components
NUREG/CR-5378
(EGG-2567)
Aging Data Analysis and Risk Assessment - Development and Demonstration Study
NUREG/CR-5379 V1
(PNL-6560)
Nuclear Plant Service Water System Aging Degradation Assessment: Phase I, Vol. 1
NUREG/CR-5379 V2
(PNL-6560)
Nuclear Plant Service Water System Aging Degradation Assessment: Phase II, Vol. 2
NUREG/CR-5386
(PNL-6911)
Basis for Snubber Aging Research: Nuclear Plant Aging Research Program
NUREG/CR-5404 V1
(ORNL-6566, V1)
Auxiliary Feedwater System Aging Study, V1
NUREG/CR-5404 V2
(ORNL-6566, V2)
Auxiliary Feedwater System Aging Study, Phase I Follow-On Study
NUREG/CR-5406 V1
(EGG-2569, V1)
BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption Test, V2: Analysis and Conclusions
NUREG/CR-5406 V2
(EGG-2569, V2)
BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption Test, V2: Data Report
NUREG/CR-5406 V3
(EGG-2569, V3)
BWR Reactor Water Cleanup System Flexible Wedge Gate Isolation Valve Qualification and High Energy Flow Interruption Test, V3: Review of Issues Associated with the BWR Containment Isolation Valve Closure
NUREG/CR-5419
(BNL-NUREG-5221)
Aging Assessment of Instrument Air Systems in Nuclear Power Plants
NUREG/CR-5479
(ORNL/TM/11398)
Current Applications of Vibration Monitoring and Neutron Noise Analysis: Detection and Analysis of Structural Degradation of Reactor Vessel Internals from Operational Aging
NUREG/CR-5490 V1
(PNL-7190)
Regulatory Instrument Review: Management of Aging of LWR Major Safety Components
NUREG/CR-5507
(BNL-NUREG-52222)
Results from the Nuclear Plant Aging Research Program: Their Use in Inspection Activities
NUREG/CR-5510 Evaluations of Core Melt Frequency Effects due to Component Aging Maintenance
NUREG/CR-5515
(ETEC 88-01)
Light Water Reactor Pressure Isolation Valve Performance Testing
NUREG/CR-5519 V1
(ORNL-6607/V1)
Aging of Control and Service Air Compressors and Dryers Used in Nuclear Power Plants
NUREG/CR-5555 Aging Assessment of the Westinghouse PWR Control Rod Drive System
NUREG/CR-5558
(EGG-2600)
Generic Issue 87: Flexible Wedge Gate Valve Test Program: Phase II Results and Analysis
NUREG/CR-5583
(KEI No. 1656)
Prediction of Check Valve Performance and Degradation in Nuclear Power Plant Systems-Wear and Impact Tests
NUREG/CR-5587
(SAIC-92/1137)
Approaches for Age-Dependent Probabilistic Safety Assessments With Emphasis on Prioritization and Sensitivity Studies
NUREG/CR-5646
(EGG-2655)
Piping System Response During High Level Simulated Seismic Tests at the Heissdampfreaktor Facility (SHAM Test Facility)
NUREG/CR-5693
(BNL-NUREG-52283)
Aging Assessment of Component Cooling Water Systems in Pressurized Water Reactors-Phase II
NUREG/CR-5699 V1
(ORNL-6666/V1)
Aging and Service Wear of Control Rod Drive Mechanisms for BWR Nuclear Plants - V1
NUREG/CR-5706
(ORNL-6671)
NRC Bulletin 88-04: Potential Safety-Related Pump Loss- An Assessment of Industry Data
NUREG/CR-5720
(EGG-2643)
Motor-Operated Valve Research Update
NUREG/CR-5754
(ORNL/TM-11876)
Boiling-Water Reactor Internals Aging Degradation Study-Phase I
NUREG/CR-5779 V1
(ORNL-6687)
Aging of Non-Power-Cycle Heat Exchangers Used in Nuclear Power Plants
NUREG/CR-5783
(BNL-NUREG-52299)
Aging Assessment of the Combustion Engineering and Babcock & Wilcox Control Rod Drives
NUREG/CR-5807 Improvements in Motor Operated Gate Valve Design and Prediction Models for Nuclear Power Plant Systems
NUREG/CR-5848 Recordkeeping Needs to Mitigate the Impact of Aging Degradation
NUREG/CR-5870
(PNL-8051)
Results of LWR Snubber Aging Research
NUREG/CR-5944
(ORNL-6734)V2
A Characterization of Check Valve Degradation and Failure Experience in the Nuclear Power Industry
NUREG/CR-6001
(PNL-8020)
Aging Assessment of BWR Standby Liquid Control Systems
NUREG/CR-6029 Aging Assessment of Nuclear Air Treatment System HEPA Filters and Adsorbers - Phase 1
NUREG/CR-6043 V1
(PNL-8614)
Phase I Aging Assessment of Essential HVAC Chillers Used in Nuclear Power Plants
NUREG/CR-6048
(ORNL-TM-12371)
Pressurized-Water Reactor Internals Aging Degradation Study --A Phase I Report
ORNL/NRC/LTR-91/25 Throttled Valve Cavitation and Erosion
PNL-5722 Operating Experience and Aging Assessment of ECCS Pump Room Coolers
PNL-6287 Study Group Review of Nuclear Service Diesel Generator Testing and Aging Mitigation
PNL-7516 Emergency Diesel Generator Technical Specifications Study Results
PNL-7823 Maintenance Practices to Manage Aging: A Review of Several Technologies
PNL-SA-20219 ASME Subsection ISTD Recommendations Based upon NPAR Snubber Aging Research Results

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Page Last Reviewed/Updated Thursday, April 25, 2013