CSA N287.7-17 pdf download

CSA N287.7-17 pdf download – In-service examination and testing requirements for concrete containment structures for nuclear power plants

CSA N287.7-17 pdf download – In-service examination and testing requirements for concrete containment structures for nuclear power plants.
4 Operating organization responsibilities The operating organization shall be responsible for a) documenting the station in-service containment examination and testing program; b) implementing a comprehensive examination program in accordance with the requirements of this Standard; c) the approval of the in-service test specifications (see Clause 8); d) updating the test specifications relative to the results of the preceding in-service examinations and tests; e) the approval of the in-service test procedures (see Clause 9); f) ensuring that personnel performing examinations and testing functions are competent and knowledgeable to the degree specified in Clause 5.3.1; g) the performance of in-service examinations and tests in accordance with the requirements for in-service test specifications and procedures; h) notifying the AHJ upon the discovery of i) a breach in containment; ii) deterioration in excess of the operating organizations’ acceptance criteria; or iii) measured leakage rates in excess of leakage-rate limits in the test plan;
i) issuing the following test information, within a time period agreed upon by the operating organization and AHJ, after completion of the examinations and tests: i) the preliminary test results; ii) an evaluation of examination and test results and, where required, the disposition of such results; iii) problems encountered and deviations from the test plan; and iv) repairs to the containment boundary; Note: The time period for issuing test information in Item i) after completion of the examinations and tests is typically 30 days. j) the preparation of the final test report (see Clause 10); k) initiating a corrective action plan to remove or disposition the anomalies discovered during the examinations in a timely and efficient manner; and l) maintaining all files of the in-service examination and test reports and any additional relevant documentation for a period of not less than the life of the nuclear power plant. 5 General requirements 5.1 General 5.1.1 Concrete containment structures and their parts, as applicable, shall be examined in accordance with the requirements of Clause 6. 5.1.2 Concrete containment structures shall be leakage-rate tested in accordance with the requirements of Clause 7. 5.1.3 Proof and leakage-rate tests shall be performed prior to returning the concrete containment structures to service in accordance with the requirements of CSA N287.6 after a) the completion of major modifications to the concrete containment structures or to parts of the containment structures that cannot be tested separately; and b) a major event that could negatively impact the integrity of the structure.
Notes: 1) The containment structure is initially proof and leakage-rate tested in accordance with the requirements of CSA N287.6 prior to first being declared in-service. 2) A major modification is that which could impact the integrity of the structure. 3) Examples of major events include a) the containment system being subjected to elevated pressure differentials as a result of an accident; or b) the containment system being subjected to any severe environmental effects beyond its design basis. 5.2 Basis of comparison The observations of the in-service examinations and tests shall be compared to the monitored results of the pre-operational proof and leakage-rate tests and to the results of the preceding examinations and tests, and shall be made available to the AHJ for review. Trending of the test results shall be provided in the test report.
5.3 Personnel 5.3.1 Responsibilities of organization or personnel performing in-service examinations and ILRT 5.3.1.1 The responsibilities of the in-service examination lead shall include, but not be limited to, the following: a) preparing and updating, as necessary, the in-service examination program; b) reviewing examination reports and ILRT results pertaining to the overall leakage and location of the leaks; c) interpreting and evaluating environmental, inspection, instrumentation, non-destructive, and destructive testing data, as applicable; d) assessing degradation and recommending follow-up actions, as applicable; e) defining mitigation, repair, and replacement actions or additional examination methods, or both, to be implemented, as applicable; f) preparing requirements for repair; g) overseeing and accepting repairs, including re-inspection; and h) preparing the closeout report, documenting the activities in Items c) to g), for each in-service examination. Notes: 1) Additional examination methods can include a) destructive testing; b) non-destructive testing; c) instrumented monitoring; and d) measurements of environmental parameters. 2) Any responsibility of the in-service examination lead may be delegated to a person with qualifications equal or greater than those specified in Clause 5.3.2.CSA N287.7-17 pdf download.

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