05000298/FIN-2017002-01
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Finding | |
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| Title | Failure to Assess Operability of Technical Specification System Functions during Surveillance Testing |
| Description | Green . The inspectors identified a non- cited violation of Technical Specification 5.4.1.a, for the licensees fail ure to follow Station Procedure 0.26, Surveillance Program, Revision 70, and to assess the operability of alternate shutdown reactor pressure instrumentation during surveillance testing. Specifically, the licensee failed to assess the operability of the hig h pressure coolant injection turbine steam inlet pressure instrument that provides indications of reactor pressure for the alternate shutdown panel when the instrument was isolated during surveillance testing. As a result, operations personnel failed to r ecognize that the instrument was inoperable and failed to enter the appropriate technical specification action statements . As immediate corrective actions, the licensee validated that the alternate shutdown reactor pressure function was inoperable and that Technical Specification 3.3.3.2, Altern ate Shutdown System, Condition A, should have been entered, and generated a procedure change request to ensure T echnical Specification 3.3.3.2 would be entered during future surveillances . The licensee entered this deficiency into the corrective action program as Condition Report CR -CNS -2017- 02280. The licensees failure to assess the operability of alternate shutdown reactor pressure instrument ation when the high pressure coolant injection turbine inlet steam pr essure instrument was isolated for surveillance testing, in violation of Station Procedure 0.26, was a performance deficiency. The performance deficiency was determined to be more than minor , and therefore a finding, because it was associated with the hum an performance attribute of the Mitigating Systems Cornerstone, and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events. Specifically, the alternate shutdown reactor pressure instrument was inoperable when the high pressure coolant injection turbine inlet pressure instrument was isolated for surveillance testing, and the appropriate technical specification action statement was not entered. Using Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, dated June 19, 2012, the inspectors determined that the finding had very low safety significance (Green) because it: was not a design deficiency; did not repr esent a loss of system and/or function; did not represent an 3 actual loss of function; did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time; and did not result in the loss of a high safety -significant nontechnical specification train. The finding had a cross -cutting aspect in the area of human performance associated with work management. Specifically, the licensee failed to implement a process of planning, controlling, and executing work activities such that nuclear safety was the overriding priority, including the identification and management of risk commensurate with the isolation of the high pressure coolant injection turbine inlet pressure instrument during surveillance testing [H.5]. |
| Site: | Cooper  |
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| Report | IR 05000298/2017002 Section 1R13 |
| Date counted | Jun 30, 2017 (2017Q2) |
| Type: | NCV: Green |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.13 |
| Inspectors (proximate) | P Voss C Henderson P Elkmann G Pick M Phalen N Greene |
| Violation of: | Technical Specification |
| CCA | H.5, Work Management |
| INPO aspect | WP.1 |
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Finding - Cooper - IR 05000298/2017002 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Cooper) @ 2017Q2
Self-Identified List (Cooper)
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