05000528/FIN-2011005-06
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Finding | |
|---|---|
| Title | Licensee-Identified Violation |
| Description | Title 10 CFR 50.55a Codes and Standards states in part that Systems and components of boiling and pressurized water cooled nuclear power reactors must meet the requirements of the following standards referenced in paragraphs (b)(1), (b)(2), (b)(3), (b)(4), (b)(5), and (b)(6) of this section. Title 10 CFR 50.55a(b)(3) states in part that as used in this section, references to the OM Code refer to the ASME Code for Operation and Maintenance of Nuclear Power Plants, Subsections ISTA, ISTB, ISTC, and ISTD, Mandatory Appendices I and II, and Nonmandatory Appendices A through H and J, and include the 1995 Edition through the 2006 Addenda. Mandatory Appendix I Inservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants states in part that Class 1 pressure relief valves shall be tested at least once every 5-years, a minimum of 20 percent of the valves from each valve group shall be tested within any 24-month interval, and for replacement of a partial complement of valves, the valves removed from service shall be tested prior to resumption of electric power generation. Contrary to the above, prior to November 19, 2011, the licensee did not test a minimum of 20 percent of the valves from each valve group within any 24-month interval and valves removed from service were not tested prior to resumption of electric power generation. Specifically, the licensee failed to test a minimum of 20 percent of Class 1 thermal relief valves within any 24-month interval for Units 1 and 3 and failed to test Class 1 thermal relief valves removed from service prior to resumption of electric generation for Unit 2. The licensee entered surveillance requirement SR 3.0.3 for Units 2 and 3 and will test the affected Class 1 thermal relief valves, in accordance with Mandatory Appendix I, at the next outage for each unit respectively. Inspectors concluded that the finding is of very low safety significance (Green) because the reactor coolant system barrier remained intact. |
| Site: | Palo Verde  |
|---|---|
| Report | IR 05000528/2011005 Section 4OA7 |
| Date counted | Dec 31, 2011 (2011Q4) |
| Type: | NCV: Green |
| cornerstone | Mitigating Systems |
| Identified by: | Licensee-identified |
| Inspection Procedure: | |
| Inspectors (proximate) | L Ricketson G Guerra R Lantz M Brown B Baca D Allen J Melfi B Parks A Fairbanks E Uribe M Baquera D Reinert S Hedger |
| INPO aspect | |
| ' | |
Finding - Palo Verde - IR 05000528/2011005 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Palo Verde) @ 2011Q4
Self-Identified List (Palo Verde)
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