Inservice testing

An in-service test program will be developed that includes preservice (baseline) testing and a periodic inservice test program to insure that all "safety-related" valves will be in a state of operational readiness to perform their principal radionuclide control function throughout the life of the plant. The test program will be based on the ASME Boiler and Pressure Vessel Code, Section XI, Division 2, Subsection IGV (primarily IGV-1000). 

The acceptance criterion for the resolution of GSI B-63 is that the periodic inservice testing of the HP to LP system boundary valves shall meet the intent of SRP 3.9.6, Revision 2. Because SRP 3.9.6, Revision 2, endorses the requirements of the ASME B PV Code Section XI, periodic testing of these valves shall be performed in accordance with the code. 

Furthermore, with respect to assuring the integrity of boundary valves during operation, these valves will be periodically inservice tested in accordance with Section XI of the ASME B PV Code. Specifically, Code Class 1, 2 and 3 valves will be... 

Regulatory Guide 1.175 and Standard Review Plan Section 3.9.7 Inservice testing (1ST)... 

The problems with check valves have been caused by weakness in several activities relative to their performance. Check valve design has been faulty in some instances and has led to failure of internal parts. Application of the valve such as sizing, installation, and location may not be appropriate for system conditions. Because of improper categorization with respect to maintenance, some check valves important to safety have not been subject to routine testing with respect to each of their safety functions. Also, the inservice tests required by NRC regulations through reference to the ASME Boiler and Pressure Vessel Code are not fully sufficient to predict or to indicate valve degradation. Further, inadequate procedures have led to improper valve assembly. 

Generally, Class 1 SSCs are subject to operability and availability limitations as doeumented in the APIOOO Technical Specifications, Inservice Testing (1ST) Program, and Inservice Inspection (ISI) Program. 

NRC (1998). An Approach for Plant-Specific, Risk-Informed Decision Making Inservice Testing Assurance, RG-1.175, Nuclear Regulatory Commission, Washington, DC, USA. 

Provides educational presentations to pharmacy staff, students, and other health care professionals. Review of inservice presentations, evaluations, and/or scores on post-test evaluations ... 

Section XI provides requirements for the preservice and periodic inservice inspections pump, valve and snubber tests pressure tests and for the repair and replacement of pressure retaining components, including their integral attachments and component supports, classified as ASME Class 1, 2, and 3. 

Inservice inspections, tests, and repairs and replacements conducted during the ten year inspection intervals should comply with the latest edition and addenda of the Code referenced in this implementation guidance 12 months prior to the start of the next inspection interval. Later editions and addenda of the Code that are incorporated by reference into this paragraph may be used subject to any I imitations and modifications noted in this implementation guidance. 

Other appropriate requirements to minimize the probability or consequences of an accidental rupture of these lines or of lines connected to them shall be provided as necessary to assure adequate safety. Determination of the appropriateness of these requirements, such as higher quality in design, fabrication, and testing, additional provisions for inservice inspection, protection against more severe natural phenomena, and additional isolation valves and containment, shall include consideration of the population density, use characteristics, and physical characteristics of the site environs. 

Reactor Coolant Pressure Boundary Inservice Inspection and Testing... 

Inservice verification and testing of safety-related SSCs is conducted by HCF personnel in compliance with TSR surveillance requirements. These operational activities consist of Zonel-to-Zone 2A and Zone 2A-to-Zone 2 ventilation system differential pressure verification, differential pressure instrumentation channel functional testing, ventilation fan sequencing interlock operability testing, and ventilation system hot exhaust filter operability verification. Details of these TSR surveillance tasks and the frequency with which they are to be performed are formalized in an operational surveillance procedure. 

Additional inservice surveillance testing and inspections are performed for two primary purposes. The first is to determine actual facility operating conditions, and to verify the status of operating equipment and the operability of standby equipment and alarms. The second is to identify operational deficiencies that may be present and initiate appropriate corrective actions. Details of these tasks and the frequency with which they are performed are formalized in an operational surveillance procedure. 

Codes listed above are construction codes. In addition, all these components are designed and constructed to meet the test and inspection requirements of the ASME Boiler and Pressure Vessel Code, Section XI, Rules for Inservice Inspection. 

The core critical curve is intended to provide additional margins of safety during core operation. The limit is defined as 40°F above the minimum allowable temperature for heatup or cooldown nor lower than the minimum temperature allowable for inservice hydrostatic pressure test, in accordance with paragraph IV.A.3 in Appendix G to 10 CFR 50. 

The reactor coolant pump pressure boundary is nondestructively inspected as required by ASME Section III for Class 1 components. The pump casing inspections include complete radiography and liquid penetrant or ultrasonic testing. The pump receives a hydrostatic pressure test in the vendor s shop and with the Reactor Coolant System. Inservice inspection of the pump pressure boundary will be performed during plant life in accordance with ASME Section XI. 

In summary, the bolting for RCPB components and supports are selected considering their particular application and are fabricated, tested and installed in accordance with ASME Sections III. Furthermore, the owner-operator is required to comply with ASME Code, Section XI for the performance of inservice inspection. Therefore, this issue is resolved for the System 80+ Standard Design. 

The steam generators shall meet the requirements of Sections III and XI of the ASMS B PV Code for design, manufacture, test, and inspection. Also, steam generator design shall meet the intent of the guidance given in SRP Sections 5.4.2.1, Rev. 2 and 5.4.2.2, Rev. 1 (Reference 3) for steam generator materials, quality assurance, inservice tube inspection, and secondary side water chemistry. 

Specifically, these boundary valves shall comply with the requirements of the applicable IWV subarticles identified within Section XI of the ASME B PV Code. This compliance shall include the appropriate classification and/or categorization of safety-related valves and the development of the proper test procedures for pre-operational and periodic inservice valve testing. 

What Inspect all pressure hoses and couplings by performing a test with the hose extended and using the inservice maximum operating pressures to determine material deteriorations, signs of leakage, or weakness in the hose carcass or at the couplings. 

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