One of the conditions of all operating licenses for water-cooled power reactors in the United States is that the primary reactor containments shall meet the containment leakage test requirements set forth in Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, to 10 CFR Part 50.21 These test requirements provide for preoperational and periodic verification by tests of the leak-tight integrity of the primary reactor containment as well as systems and components that penetrate contain­ment of water-cooled power reactors and establish the acceptance criteria for such tests. The purpose of these tests is to ensure that (1) leakage through the primary reactor containment and the systems and components penetrating primary reactor contain­ment shall not exceed allowable leakage-rate values as specified in the technical specifications or asso­ciated bases and (2) periodic surveillance of reactor containment penetrations and isolation valves is per­formed so that proper maintenance and repairs are made during the service life of the containment as well as systems and components that penetrate pri­mary containment. Contained in this regulation are requirements pertaining to Type A, B, and C leakage- rate tests that must be performed by each licensee as a condition of their operating license. Type A tests are intended to measure the primary reactor containment overall integrated leakage rate (1) after the contain­ment has been completed and is ready for operation and (2) at periodic intervals thereafter. Type B tests are intended to detect local leaks and to measure leakage across each pressure-containing or leakage-limiting boundary for primary reactor containment penetra­tions (e. g., penetrations that incorporate resilient seals, gaskets, or sealant compounds and air lock door seals). Type C tests are intended to measure containment isolation valve leakage rates. Requirements for system pressure testing and criteria for establishing inspection programs and pressure-test schedules are contained in Appendix J.

Appendix J to 10 CFR Part 50 also requires a general inspection of the accessible interior and exterior surfaces of the containment structures and components to uncover any evidence of structural deterioration that may affect either the containment structural integrity or leak tightness. Subsection IWL of ASME Section XI addresses reinforced and post — tensioned concrete containments (Class CC). Two examination categories are provided in Subsection IWL. Examination Category L-A addresses accessi­ble concrete surfaces and examines them for evidence of damage or degradation, such as cracks. The con­crete is examined at 1, 3, and 5 years following the containment structural integrity test and every 5 years thereafter. The primary inspection method of Category L-A is visual examination (general or detailed). Examination Category L-B addresses the unbonded post-tensioning system. The unbonded post-tensioning system examination schedule is the same as for the concrete. For post-tensioned concrete containments, tendon wires are tested for yield strength, ultimate tensile strength, and elongation. Tendon corrosion protection medium is analyzed for alkalinity, water content, and soluble ion concen­trations. Prestressing forces are measured for selected sample tendons. Subsection IWL specifies accep­tance criteria, corrective actions, and expansion of the inspection scope when degradation exceeding

the acceptance criteria is found. Additional require­ments for inaccessible areas are specified in 10 CFR 50.55a(b)(2)(viii). The acceptability of concrete in inaccessible areas is to be evaluated when conditions that could indicate the presence or result in degrada­tion to such inaccessible areas exist in accessible areas. Information on aging management programs for masonry walls22,23 and water-control structures24 is available. Inspection requirements for steel con­tainments and liners of concrete containments are contained in Subsection IWE of ASME Section XI. Editions and addenda of the ASME Code acceptable to the USNRC are identified in 10 CFR 50.55a.