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The licensee failed to meet the requiremenThe licensee failed to meet the requirements of 10 CFR 50.71(e) to update the final safety analysis report. The final safety analysis report sections contained prior information and data that did not reflect the current plant configuration. The examples are: Chapter 3.9B, Mechanical Systems and Components (GE Scope Supply) Section 3.9.5.1.1.12B, Vent and Head Spray Nozzle described the head spray function of the reactor core isolation cooling system. However, the head spray function of the reactor core isolation cooling system had been removed from the final safety analysis report in 1998 via License Amendment Request 98-01 in which this section was erroneously omitted. Sections 2.4.2.3.1 and 12.3.2.4.5 of the updated safety analysis report describe the roofing systems on site to be sloped with built-up roofing material for construction. In 1996, a condition report was written documenting the discrepancy between design documents which indicate built-up roofing and insulation, and the actual condition of the roofs on the Auxiliary Building, Standby Cooling Tower Pump house, Radwaste Building, and Diesel Generator Building, which have neither of these materials. Title 10 CFR 50.71, Maintenance of Records, Making of Reports, Section (e) which states, in part, Each person licensed to operate a nuclear power reactor shall update periodically the final safety analysis report originally submitted as part of the application for the license, to assure that the information included in the report contains the latest information developed. This submittal shall contain all the changes necessary to reflect information and analyses submitted to the Commission by the applicant or licensee or prepared by the applicant or licensee pursuant to Commission requirement since the submittal of the original or the last update to the final safety analysis report. Contrary to the above, the licensee did not update the final safety analysis report to assure that the information included in the report contains the latest information developed. Specifically, the licensee failed to ensure the final safety analysis report reflected the current plant configuration, as evidenced by the above examples. The NRCs significance determination process considers the safety significance of findings by evaluating their potential safety consequences. The traditional enforcement process separately considers the significance of willful violations, violations that impact the regulatory process, and violations that result in actual safety consequences. Traditional enforcement applied to this performance deficiency because it involved a violation that impacted the regulatory process. Assessing the violation in accordance with the NRC Enforcement Policy, the team determined it to be a Severity Level IV violation because the lack of up-to-date information in the final safety analysis report has not resulted in any unacceptable change to the facility or procedures (NRC Enforcement Policy example 6.1.d.4). This issue was entered into the licensees corrective action program as Condition Report CR-RBS-2015-7259.gram as Condition Report CR-RBS-2015-7259.  
23:59:59, 31 December 2015  +
05000458  +
23:59:59, 31 December 2015  +
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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>.
15:53:10, 30 May 2018  +
23:59:59, 31 December 2015  +
Licensee-Identified Violation  +