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Category:Code Relief or Alternative
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2020-06-03
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VERBAL AUTHORIZATION FOR RELIEF REQUEST HNP-ISI-ALT-10 TEMPORARY NON-CODE REPAIR OF SERVICE WATER PIPING HATCH NUCLEAR PLANT UNIT 1 JULY 21, 2010 By letter dated July 16, 2010, Southern Nuclear Operating Company (the licensee) requested NRC review and approval of a proposed alternative in Relief Request HNP-ISI-ALT-10 to certain ASME Code requirements associated with a temporary non-Code repair of plant service water piping at Hatch Nuclear Plant Unit 1 (ADAMS Accession No. ML102000178). By letter dated July 20, 2010 (ML102010574), the licensee submitted its flaw evaluation of the pinhole at the elbow of the plant service water piping based on ASME Code Case N-513-2 , "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping,Section XI, Division 1,"
and NRC Generic Letter 90-05, "Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping".
The licensee proposed to install a 6-inch diameter branch connection at the pinhole on the 30-inch diameter plant service water piping in accordance with the requirements of ANSI B31.1. As discussed in the application, the proposed non-Code repair meets the requirements for a "full Code repair" with the exception that the defect will be left in service until the permanent repair/replacement activity can be completed. As part of the proposed temporary "non-Code repair," the licensee will perform a visual examination and dye penetrant test of the weld that joins the branch connection to the pipe. The licensee will also perform a pressure test accompanied with a visual VT-2 examination to ensure the integrity of the repair.
Further, the licensee will perform daily rounds of the non-Code repair. The repaired area of the elbow will be ultrasonically examined on a 30-day frequency to ensure that degradation outside of the encapsulated area of the pipe is not occurring and that the structural integrity of the elbow is being maintained.
The licensee indicated that performance of an ASME Code repair of the subject degradation at this time would necessitate a plant shutdown and would result in hardship without a compensating increase in the level of quality and safety.
On the basis of the NRC staff's evaluation, pursuant to 10 CFR 50.55a(a)(3)(ii), on July 21, 2010, the NRC staff authorizes the use of Relief Request HNP-ISI-ALT-10 for the temporary non-Code repair of the subject plant service water system pipe at Hatch Nuclear Plant Unit 1. The NRC authorizes the use of Relief Request HNP-ISI-ALT-10 up to the end of Hatch Unit 1 refueling outage 1R25, which is scheduled to begin in February 2012, or up to the next cold shutdown of sufficient time to perform the Code repair/replacement, whichever occurs first.
This verbal authorization does not preclude the NRC staff from requesting additional clarifying information regarding Relief Request HNP-ISI-ALT-10 while preparing the subsequent written safety evaluation.
All other requirements in ASME Code,Section XI, ANSI B31.1, Code Case N-513-2, and Generic Letter 90-05 for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
