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The licensee identified an NCV of 10 CFR P … The licensee identified an NCV of 10 CFR Part 50, Appendix B, Criterion III, Design Control, for the failure to assure that design basis information was correctly translated into calibration procedures for both units over temperature delta temperature (OTDT) reactor trip instrumentation. On January 29, 2015, the licensee discovered that lead time-constants associated with the OTDT reactor trip function for all four channels on both units 1 and 2 were incorrect, and that the calibration procedures, 1/2ICP 04.001C, for this setting also contained the incorrect values. The licensee identified this issue in AR 02021827, which described the condition and stated that the incorrect lead time-constant values were not updated following EPUs for both units. Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires, in part, that measures be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions. Contrary to the above, from June 15, 2012 to January 29, 2015, the licensees calibration procedures 1/2ICP 04.001C did not contain the correct lead time-constant setting for the proper calibration for all channels of the TS required OTDT reactor trip instrumentation. The licensee entered this issue into the CAP as AR 02021827, realigned all eight of the affected channels (four on each unit), and initiated procedure changes to incorporate the correct values for these settings. The inspectors determined that this issue was of very low safety significance (Green) after reviewing IMC 0609, Significance Determination Process, Attachment 0609.04, Initial Characterization of Findings, dated July 1, 2012 and IMC 0609, Appendix A, The Significance Determination Process for Findings At-Power, dated July 1, 2012. Because the licensee determined that operability was maintained, the inspectors answered "No" to all questions in Exhibit 2, Section A, Mitigating Structures, Systems, Components (SSCs), and Functionality. Therefore, the finding screened as very low safety significance (Green).d as very low safety significance (Green).

Discovered date

23:59:59, 31 March 2015 +

Docket

05000266 + and 05000301 +

Equipment trip

Reactor Trip +

Event date

23:59:59, 31 March 2015 +

Finding integer

3 +

Finding type

Non-cited violation +

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Identified by

Licensee-identified +

Inspection Manual Chapter

NRC Inspection Manual 0609 + and NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +

Inspection report

IR 05000266/2015001 +

Inspector

Jamnes Cameron +, J Boettcher +, D Oliver +, Kevin Barclay + and Valerie Myers +

Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.

15:51:56, 30 May 2018 +

Person