10CFR50 Appendix J Program
The Primary Reactor Containment Leakage Testing (Appendix J) Program is used to ensure that leakage through the primary reactor containment, and systems and components that penetrate primary containment, shall not exceed established limits. The primary reactor containment and associated systems and components that penetrate containment are to provide the final barrier in preventing the release of quantities of radioactive material that would have a significant radiological effect on the health of the public. This program uses periodic surveillance testing to demonstrate the leak tightness of the primary reactor containment (vessel), and systems and components that penetrate the primary containment.
Appendix J Programs utilize either the prescriptive requirement (Option A) or the performance-base requirement (Option B) within 10CFR50 Appendix J. Each program provides unique compliance requirements that can be advantageous, or unfavorable to an operating nuclear station.
The prescriptive requirements of Option A include Type A, Type B, and Type C surveillance tests. These surveillance tests specify the minimum leakage testing requirements to ensure leak tightness of the primary reactor containment, and systems and components that penetrate the primary containment. These tests are required to be performed at routine intervals.
The performance-based requirements of Option B identify Type A, Type B, and Type C testing. These requirements may be adopted by a station on a voluntary basis. Surveillance testing specified in Option B will substitute for those contained in Option A. Performance based testing establishes criteria and standards against which test results are to be compared for establishing extended test intervals.
Altran Solutions can help you develop an effective and compliant Appendix J Program.
Altran Solutions has successfully established both Option A and Option B program scopes for the primary reactor containment leakage testing programs at both Boiling Water Reactor (BWR), and Pressurized Water Reactor (PWR) facilities. These programs satisfy both 10CFR50 Appendix J requirements and specific site Technical Specification and/or associated basis documents.
Altran Solutions can also successfully provide the following programs and surveillances associated with Loss of Coolant Accidents or Fission Product Barriers.
- Maximum Pathway Leakage Rate Surveillance Total Calculation for Systems and Components That Penetrate Primary Containment (required for plant startup)
- Minimum Pathway Leakage Surveillance Rate Total Calculation for Systems and Components That Penetrate Primary Containment (required for Licensee Event Report submittals)
- Secondary Containment Bypass Leakage Program
- Primary Coolant Leakage Outside Containment Program
- Drywell Containment Bypass Leakage Program (BWRs only)
- Reactor Coolant System Pressure Isolation Valve Leakage Program
- Pressure Testing Program In Accordance With ASME Section XI, Subsection IWE/IWL
- Appendix A of 10CFR50 (General Design Criteria 55, 56, and 57) Safety Analysis Report Assessments
- Technical Specification Surveillance Requirements for primary reactor containment vessels, and systems and components that penetrate primary containment (ensure that facility operation is within safety limits and that the Limited Condition for Operability will be met).