05000368/FIN-2014003-05
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Finding | |
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| Title | |
| Description | Introduction. The inspectors identified an unresolved item pertaining to characterizatio
of a potential performance deficiency for design control for the reactor coolant samplin system. The original specifications for the system specified stainless steel components but carbon steel components were used in the system. Description. Two through wall leaks in the supply line to the Unit 2 reactor coolant sample cooler E30 were identified on February 3, 2014. The two flaws were in the weld metal or heat affected zone of the weld and were approximately 1/8 inch apart. One flaw was a pinhole near the center of the fillet weld and the second flaw was linear in nature, starting at the toe of the fillet weld and continuing transverse across the weld. The proper classification of the system needs to be determined to correctly characterize the use of the carbon steel components in the system. Regulatory Guide 1.26, Quality Group Classifications And Standards For Water-,Steam-, and Radioactive-Waste-Containing Components Of Nuclear Power Plants Section C.2.c, Regulatory Position, states, in part, The Group C quality standards given in Table 1 of this guide should be applied to water-, steam-, and radioactivewaste- containing pressure vessels, heat exchangers (other than turbines and condensers), storage tanks, piping, pumps, and valves not part of the reactor coolant pressure boundary or included in quality Group B, but part of: systems or portions of systems that are connected to the reactor coolant pressure boundary and are capable of being isolated from that boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure. (Note 6)" Note 6 states, Components in influent lines may be classified as Group D provided they are capable of being isolated from the reactor coolant pressure boundary by an additional valve which has high leak tight integrity. The quality standards given in Table 1 for piping are ASME Code,Section III, Class 3. The reactor coolant sampling system meets the description of Group C quality standards. There is confusion as to the current classification of the system, some documents indicate it is ASME Code,Section III, Class 3, others indicate that it is B31.1 piping which would be the quality standards for Group D piping. At the time of the inspection, the licensee could not provide documentation demonstrating that the system was capable of being isolated from the reactor coolant pressure boundary by an additional valve which has high leak tight integrity. The licensee was researching microfilm documents to locate the necessary information. This issue is being tracked as URI 05000368/2014003-05. |
| Site: | Arkansas Nuclear  |
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| Report | IR 05000368/2014003 Section 1R08 |
| Date counted | Jun 30, 2014 (2014Q2) |
| Type: | URI: |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.08 |
| Inspectors (proximate) | M Young N Greene P Jayroe R Latta A Fairbanks B Baca B Tindell G Werner J Melfi J O'Donnell L Carson L Ricketsonb Tindellj Drake L Carson M Phalen M Williams M Young N O'Keefe Z Hollcraft |
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Finding - Arkansas Nuclear - IR 05000368/2014003 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Arkansas Nuclear) @ 2014Q2
Self-Identified List (Arkansas Nuclear)
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