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Describes procedures and sample requirements for surveillance testing of systems and components critical for nuclear plant safety, ensuring their ability to perform as required under operational and safety conditions.
Effective Date:
July 1, 2021
PROGRAM APPLICABILITY:
IMC 2515 A
CORNERSTONES:
Mitigating Systems, Barrier Integrity
INSPECTION BASES:
See IMC 0308 Attachment 2
Year:
2021
Region / City:
Not specified
Topic:
Nuclear safety inspection procedures
Document Type:
Inspection Procedure
Author:
NRC
Target Audience:
NRC inspectors, nuclear plant operators
Period of Validity:
Not specified
Approval Date:
July 1, 2021
Date of Amendments:
Not specified
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Effective Date:
January 1, 2023
Program Applicability:
IMC 2515 Appendix A
Cornerstones:
Initiating Events, Mitigating Systems, Barrier Integrity
Inspection Bases:
See IMC 0308, “Reactor Oversight Process Basis Document,” Attachment 2, “Technical Basis for Inspection Program”
Year:
2023
Region / City:
USA
Topic:
Nuclear Reactor Safety, Equipment Testing
Document Type:
Inspection Procedure
Author:
Nuclear Regulatory Commission (NRC)
Target Audience:
NRC Inspectors, Nuclear Plant Operators
Effective Period:
Ongoing, with updates as needed
Approval Date:
January 1, 2023
Last Revision Date:
N/A
Effective Date:
August 24, 2016
PROGRAM APPLICABILITY:
2515B, 2201B
CORNERSTONES:
ALL
INSPECTION BASIS:
This procedure provides the supplemental inspection response to Action Matrix Column 2 inputs as described in Inspection Manual Chapter (IMC) 0305, “Operating Reactor Assessment Program,” and IMC 0320, “Operating Reactor Security Assessment Program”. The governance provided in this procedure was developed with consideration of the following boundary conditions:
Note:
Supplemental inspections will only be done for significant (i.e. greater-than-green) findings and performance indicators (PIs);
Year:
2016
Region / City:
Not specified
Topic:
Supplemental Inspection Response
Document Type:
Inspection Procedure
Agency / Institution:
NRC (Nuclear Regulatory Commission)
Author:
Not specified
Target Audience:
NRC Inspectors, Licensees
Period of Validity:
Ongoing
Approval Date:
August 24, 2016
Date of Changes:
None specified
Year:
2027
Region / City:
Global
Theme:
Data Protection, Educational Research
Document Type:
Template
Organization / Institution:
International Association for the Evaluation of Educational Achievement (IEA)
Author:
IEA
Target Audience:
National Research Coordinators (NRCs)
Validity Period:
TIMSS 2027
Approval Date:
Not specified
Modification Date:
Not specified
Effective Date:
January 1, 2025
Year:
2025
Region / City:
United States
Theme:
Emergency Preparedness, Nuclear Safety
Document Type:
Inspection Manual
Organization:
NRC (Nuclear Regulatory Commission)
Author:
NRC
Target Audience:
NRC Personnel, FEMA, Emergency Response Organizations
Period of Validity:
Ongoing
Approval Date:
January 1, 2025
Amendment Date:
None
Effective Date:
07/10/2025
Year:
2025
Note:
Region / City
Theme:
Nuclear Safety / Inspection Procedures
Document Type:
Inspection Manual
Organization / Institution:
U.S. Nuclear Regulatory Commission (NRC)
Target Audience:
Nuclear plant operators, NRC inspectors, licensed operators
Date of Changes:
07/10/2025
Effective Date:
May 27, 2025
Program Applicability:
IMC 2690
Document Number:
60858-01
Issuing Organization:
U.S. Nuclear Regulatory Commission
Subject Area:
Nuclear safety regulation
Document Type:
Inspection manual chapter
Regulatory Framework:
10 CFR Parts 20, 50, 71, and 72
Facility Type:
Away-from-reactor independent spent fuel storage installation
Inspection Focus Areas:
Occupational exposure; Public exposure; Fuel damage; Confinement; Impact to plant operations
Scope:
ISFSI operations, maintenance, emergency preparedness, radiation protection, quality assurance, environmental monitoring, and aging management
Year:
2025
Region / City:
Not specified
Topic:
Nuclear Regulatory Commission Inspection and Performance Indicators
Document Type:
Inspection Manual
Organization / Institution:
U.S. Nuclear Regulatory Commission
Author:
U.S. Nuclear Regulatory Commission
Target Audience:
NRC Inspectors, Licensees of Nuclear Facilities
Period of validity:
From January 1, 2025
Approval Date:
Not specified
Date of changes:
Not specified
Effective Date:
01/01/2021
Year:
2021
Note:
Region / city
Subject:
Occupational Radiation Exposure
Document Type:
Inspection Procedure
Organization:
NRC
Target Audience:
Inspectors, Licensees
Approval Date:
01/01/2021
Effective Date:
01/01/2021
Year:
2021
Region / City:
N/A
Subject:
Safety and Risk Assessment
Document Type:
Inspection Manual
Author:
NRC (U.S. Nuclear Regulatory Commission)
Target Audience:
NRC Inspectors, Safety Analysts, and related stakeholders
Period of Validity:
Ongoing
Approval Date:
01/01/2021
Revision History:
Available in Attachment 1
Year:
2021
Region / City:
Not specified
Topic:
Nuclear Regulatory Inspection Procedure
Document Type:
Inspection Manual
Agency:
U.S. Nuclear Regulatory Commission (NRC)
Author:
Not specified
Target Audience:
NRC inspectors, nuclear facility operators
Period of validity:
Effective from 01/01/2021
Approval Date:
01/01/2021
Date of amendments:
None specified
Year:
2021
Region / city:
Not specified
Subject:
Preoperational testing of independent spent fuel storage installation
Document type:
Inspection procedure
Organ / institution:
Nuclear Regulatory Commission (NRC)
Author:
Not specified
Target audience:
NRC inspectors, licensees involved in spent fuel storage
Period of validity:
Not specified
Approval date:
01/01/2021
Date of amendments:
Not specified
Document number:
Inspection Procedure 71151
Issuing body:
U.S. Nuclear Regulatory Commission
Document type:
Inspection procedure
Program applicability:
IMC 2201A, IMC 2515A
Effective date:
July 1, 2020
Regulatory framework:
Reactor Oversight Process
Referenced standards:
NEI 99-02, IMC 0308, 10 CFR 50.9, 10 CFR 50.73
Subject matter:
Verification of nuclear power plant performance indicator data
Applicable facilities:
Operating nuclear power reactors
Inspection scope:
Periodic verification of reported performance indicators
Effective Date:
August 24, 2016
PROGRAM APPLICABILITY:
2515B, 2201B
CORNERSTONES:
ALL
INSPECTION BASIS:
This procedure provides the supplemental inspection response to Action Matrix Column 2 inputs as described in Inspection Manual Chapter (IMC) 0305, “Operating Reactor Assessment Program,” and IMC 0320, “Operating Reactor Security Assessment Program”. The governance provided in this procedure was developed with consideration of the following boundary conditions:
Note:
Supplemental inspections will only be done for significant (i.e. greater-than-green) findings and performance indicators (PIs);
Year:
2016
Region / City:
Not specified
Topic:
Supplemental Inspection Response
Document Type:
Inspection Procedure
Agency / Institution:
NRC (Nuclear Regulatory Commission)
Author:
Not specified
Target Audience:
NRC Inspectors, Licensees
Period of Validity:
Ongoing
Approval Date:
August 24, 2016
Date of Changes:
None specified
Effective Date:
10/01/2016
PROGRAM APPLICABILITY:
2515 A
Year:
2016
Region / City:
United States
Topic:
Nuclear Safety Inspection
Document Type:
Inspection Procedure
Organ / Institution:
U.S. Nuclear Regulatory Commission
Author:
U.S. Nuclear Regulatory Commission
Target Audience:
NRC Inspectors
Validity Period:
Indefinite
Approval Date:
10/01/2016
Date of Changes:
None
Note:
Contextual Description
Effective Date:
January 1, 2026
Chapter:
0308
Document Type:
Manual
Region / City:
United States
Thematic Focus:
Nuclear Reactor Security
Institution:
U.S. Nuclear Regulatory Commission (NRC)
Target Audience:
NRC licensees, nuclear reactor operators, security personnel
Date Approved:
January 1, 2026
Effective Date:
January 1, 2025
Purpose:
This attachment provides supporting information describing the heat release rate (HRR) profile (HRR versus time curve) parameters and HRR gamma distribution parameters for various fixed and transient ignition sources. The profiles and distribution parameters were used to develop the tables and plots in sets A, D, and E of Attachment 8 to the Fire Protection Significance Determination Process (SDP), IMC 0609 Appendix F. These tables and plots allow the analyst to look up the vertical and radial zone of influence (ZOI) (used in Step 2.3.2), severity factor (SF) (used in Step 2.6.1), and damage time (used in Step 2.7.1) for a specified fixed or transient ignition source, target type, and target location for fire damage state 1 (FDS1) scenarios. Guidance is also provided for determining the HRR of confined and unconfined oil fires, cable tray fires, and hot work fires.
Year:
2025
Note:
Region / City
Subject:
Fire Ignition Sources, Heat Release Rate, Fire Protection
Document Type:
Technical Manual
Organization / Institution:
NRC
Target Audience:
Fire Safety Analysts, Engineers
Period of Effectiveness:
From January 1, 2025