05000458/FIN-2015004-02
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Finding | |
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Title | Failure to Properly Implement Surveillance Testing of Penetration Valve Leakage Control System Leads to Inoperability in Excess of Technical Specification Allowed Outage Time |
Description | The inspectors identified a non-cited violation of Technical Specification 3.6.1.9, Main Steam-Positive Leakage Control System, for the licensees failure to take required actions for an inoperable subsystem of the main steam positive leakage control system. Specifically, after rendering Division II of the main steam positive leakage control system inoperable for a period of time in excess of the 30-day allowed outage time, the licensee failed to place the unit in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The licensee entered this issue into their corrective action program as Condition Report CR-RBS-2015-03622. The licensee restored compliance by restoring Division II of main steam positive leakage control system to operable status. Corrective actions included modifying surveillance procedures for main steam positive leakage control system to ensure that they are carried out correctly. The performance deficiency was more than minor, and therefore a finding, because it was associated with the barrier performance attribute of the Barrier Integrity Cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the plant was operated at power for an extended period of time with one subsystem of a system designed to prevent radioactive leakage across the main steam isolation valves inoperable. The inspectors performed the initial significance determination using NRC Inspection Manual Chapter 0609, Appendix A, Exhibit 3, Barrier Integrity Screening Questions. The inspectors determined that the finding was of very low safety significance (Green) because (1) the finding did not represent an actual open pathway in the physical integrity of reactor containment (valves, airlocks, etc.), containment isolation systems (logic and instrumentation), or heat removal components and (2) the finding did not involve an actual reduction in function of hydrogen igniters in the reactor containment. This finding had a cross-cutting aspect in the area of human performance associated with change management because leaders failed to use a systematic process for evaluating and implementing change so that nuclear safety remains the overriding priority. |
Site: | River Bend |
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Report | IR 05000458/2015004 Section 1R22 |
Date counted | Dec 31, 2015 (2015Q4) |
Type: | NCV: Green |
cornerstone | Barrier Integrity |
Identified by: | NRC identified |
Inspection Procedure: | IP 71111.22 |
Inspectors (proximate) | B Parks G Warnick J Sowa L Brandt L Carson M Hayes M Phalen M Stafford N Greene P Hernandez |
Violation of: | Technical Specification - Procedures Technical Specification |
CCA | H.3, Change Management |
INPO aspect | LA.5 |
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Finding - River Bend - IR 05000458/2015004 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (River Bend) @ 2015Q4
Self-Identified List (River Bend)
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