05000269/FIN-2010002-05

Finding

Title

Licensee-Identified Violation

Description

10 CFR 50.65(a)(4), Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants, requires in part, that prior to performing maintenance activities, the licensee shall assess and manage the increase in risk that may result from the proposed maintenance activities. Nuclear System Directive (NSD) 415, Operational Risk Management (Modes 1-3) per 10 CFR 50.65(a)(4), implements the requirements set forth in 10 CFR 50.65(a)(4) during power operation. Contrary to the above, on November 30, 2009, with Unit 1 in Mode 3, the licensee failed to assess emergent work and allowed the Unit 1 Power Operated Relief Valve and Pressurizer Spray Valve to be concurrently out of service. This configuration resulted in the licensee entering an unplanned Red ORAM-Sentinel condition. The safety significance of this violation was assessed using IMC 0609, Appendix K and determined to be of very low safety significance (Green) based on the calculated incremental core damage probability increase for the exposure period of approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> being 1.8E-7. The licensee entered the finding into their CAP as PIP O-09-8959.

05
Site:	Oconee
Report	IR 05000269/2010002 Section 4OA7
Date counted	Mar 31, 2010 (2010Q1)
Type:	NCV: Green
cornerstone	Mitigating Systems
Identified by:	Licensee-identified
Inspection Procedure:
Inspectors (proximate)	K Ellis A Sabisch M King G Ottenberg R Chou E Riggs
INPO aspect
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v • d • e

Finding - Oconee - IR 05000269/2010002

2(5)3(3)4(8)5(6)6(0)7(2)8(0)9(2)201(0)301(0)402(0)403(0)404(0)501(0)502(0)301(0)

IR 05000269/2010002: 1 2 3 4 5

Finding List (Oconee) @ 2010Q1

CCA Matrix: 2010Q1

	Q	CCA	Title
05000269/FIN-2009004-01	2009Q3	H.5	Inadequate Assessment and Management of Risk During SSF ASW Inoperability
05000269/FIN-2009004-02	2009Q3	H.11 H.12	Unit 3 Trip Due to Generator Phase Differential Lockout
05000269/FIN-2009006-01	2009Q3	H.14	Failure to Provide Margin Between the LPI Relief Valve Set Point and the Peak Discharge Pressure of the LPI System
05000269/FIN-2009403-01	2009Q3		Security
05000269/FIN-2009005-03	2009Q4	P.5 P.2(b)	Failure to Establish and Implement an Adequate Procedure for Performing Core Alignment Verification
05000269/FIN-2009005-02	2009Q4		SSF Reactor Coolant Letdown Line Discharge Test
05000269/FIN-2009005-01	2009Q4	H.4 H.5	Inadequate Implementation of Risk Management Actions Associated With Modification Work Activities on the BWSTs for all Three Oconee Units
05000269/FIN-2009005-05	2009Q4	H.13	Inappropriate Removal of Workers Associated With Modification Work Activities on the BWST\'s from Work Hour Controls
05000269/FIN-2009005-04	2009Q4	H.11 H.12	Failure to Comply with Radiological Postings and the Requirements for Entering a Posted High Radiation Area
05000269/FIN-2010002-02	2010Q1	H.14	Failure to Promptly Identify and Correct an Adverse Condition Affecting Operability of the Unit 2 and Unit 3 Standby Shutdown Facility
05000269/FIN-2010002-01	2010Q1	H.8	Failure to Identify and Correct Fire Brigade Performance Weaknessess
05000269/FIN-2010002-04	2010Q1		Failure to Establish a Test Program to Verify SSF Letdown Line Required Flow
05000269/FIN-2010002-03	2010Q1		Materially Inaccurate Information Provided to NRC Regarding SSF Event Mitigation Capability

Self-Identified List (Oconee)

	Q	Title
05000269/FIN-2009004-03	2009Q3	Licensee-Identified Violation
05000269/FIN-2010002-05	2010Q1	Licensee-Identified Violation

[Oconee Findings full list]

05000269/FIN-2010002-05

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