05000458/FIN-2015007-03

Finding

Title

Licensee-Identified Violation

Description

The 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.

03
Site:	River Bend
Report	IR 05000458/2015007 Section 4OA7
Date counted	Dec 31, 2015 (2015Q4)
Type:	NCV: Green
cornerstone	Mitigating Systems
Identified by:	Licensee-identified
Inspection Procedure:
Inspectors (proximate)	J Watkins L Brandt M Williams T Farnholtz
Violation of:	10 CFR 50.71(e)
INPO aspect
'
v • d • e

Finding - River Bend - IR 05000458/2015007

1(3)2(2)3(2)4(7)5(0)6(0)7(3)8(4)9(6)10(5)301(0)401(0)402(0)403(2)405(1)406(3)409(0)501(0)

IR 05000458/2015007: 1 2 3

Finding List (River Bend) @ 2015Q4

CCA Matrix: 2015Q4

	Q	CCA	Title
05000458/FIN-2015001-01	2015Q1	H.11	Failure to Perform Adequate Operability Evaluations on Degraded High Pressure Core Spray System
05000458/FIN-2015001-03	2015Q1	H.4	Failure to Operate Condensate Demineralizer System Following Reactor Scram Results in Loss of All Feedwater
05000458/FIN-2015001-02	2015Q1	H.4	Inadequate Engineering Change and Work Instruction Review Results in Reactor Recirculation Pump Trip
05000458/FIN-2015009-01	2015Q2		Vendor and Industry Recommended Testing Adequacy on Safety-related and Safety-significant Circuit Breakers
05000458/FIN-2015009-05	2015Q2	P.2	Failure of the Plant-Referenced Simulator to Demonstrate Expected Plant Response
05000458/FIN-2015002-02	2015Q2		Failure to Maintain Design Control for 18 Upgraded Hydraulic Control Unit Accumulators
05000458/FIN-2015009-06	2015Q2	H.8	Failure to Identify and Classify Operator Workarounds that Impacted Scram Recovery Actions
05000458/FIN-2015009-04	2015Q2	H.12	Failure to Identify High Reactor Water Level as a Condition Adverse to Quality
05000458/FIN-2015009-03	2015Q2	P.2	Failure to Provide Adequate Procedures for Post-scram Recovery
05000458/FIN-2015406-01	2015Q2	H.9	Security
05000458/FIN-2015002-01	2015Q2		Inadequate Operating Margin for Reactor Protection System A Motor Generator Set for Overvoltage Protection Results in Loss of Shutdown Cooling
05000458/FIN-2015009-02	2015Q2	P.2	Failure to Establish Adequate Procedures to Perform Maintenance on Equipment that can Affect Safety-Related Equipment
05000458/FIN-2015406-02	2015Q2	H.14	Security
05000458/FIN-2015406-03	2015Q2	H.1	Security
05000458/FIN-2015008-01	2015Q3	H.1	Failure to Recognize Violations of Contamination Control Requirements as Adverse Conditions
05000458/FIN-2015008-02	2015Q3	H.9	Failure to Promptly Document Adverse Conditions in the Corrective Action Program
05000458/FIN-2015003-01	2015Q3	H.12	Failure to Operate the Unit 1 Feedwater System In Accordance With Procedures
05000458/FIN-2015405-01	2015Q3		Security
05000458/FIN-2015008-04	2015Q3	H.1	Failure to Identify an Adverse Trend in the Performance of Post Maintenance Testing on High Critical Components
05000458/FIN-2015008-03	2015Q3	H.2	Failure to Preclude Repetition of Consequential Gaps in Operator Performance
05000458/FIN-2015007-02	2015Q4		Failure to Obtain Prior NRC Approval for a Change in Reactor Core Isolation Cooling Injection Point
05000458/FIN-2015403-01	2015Q4		Security
05000458/FIN-2015004-01	2015Q4	H.8	Failure to Ensure Work Hours are Within Work Hour Limits
05000458/FIN-2015004-02	2015Q4	H.3	Failure to Properly Implement Surveillance Testing of Penetration Valve Leakage Control System Leads to Inoperability in Excess of Technical Specification Allowed Outage Time
05000458/FIN-2015004-03	2015Q4	H.5	Failure to Conduct Operations and Control Work Practices to Minimize Residual Radioactivity into the Site, including the Subsurface
05000458/FIN-2015004-05	2015Q4	H.12	Failure to Follow Procedure Results in Inadvertent Draindown of Reactor Pressure Vessel
05000458/FIN-2015004-06	2015Q4	H.8	Failure to Restore Main Steam Positive Leakage Control System to Operable Prior to Changing Modes
05000458/FIN-2015004-04	2015Q4		Failure to Make a Notification to NRC Operations Center Regarding a Radioactive Spill Reported to Another Government Agency
05000458/FIN-2015007-01	2015Q4	P.1	Failure to Establish Adequate Procedures for Severe Weather Operations

Self-Identified List (River Bend)

	Q	Title
05000458/FIN-2015003-02	2015Q3	Licensee-Identified Violation
05000458/FIN-2015007-03	2015Q4	Licensee-Identified Violation
05000458/FIN-2015004-07	2015Q4	Licensee-Identified Violation
05000458/FIN-2015403-02	2015Q4	Licensee-Identified Violation

[River Bend Findings full list]

05000458/FIN-2015007-03

Navigation menu

Search