05000440/FIN-2009007-03

Finding

Title

Failure to Provide Required Electrical Isolation for Post-Fire Safe Shutdown Electrical Circuits

Description

The inspectors identified a finding of very low safety significance and associated NCV of the Perry Nuclear Power Plant, Unit 1, Facility Operating License Condition 2.C.(6)and 10 CFR Part 50, Appendix R, Section III.G.3, for failure to provide the required electrical isolation in the design of the post-fire safe shutdown control logic circuitry. Specifically, the control logic for the Division 1 diesel generator building ventilation fan1M43-C001A did not have the required physical isolation to isolate control room fire induced electrical faults when transferring control to the remote shutdown station. This is required to ensure that postulated fire-induced electrical faults would not result in the loss of post-fire alternative safe shutdown equipment. The licensees immediate corrective action was to perform a preliminary evaluation of the electrical circuitry and cables. The licensee entered this finding into their corrective action program as CR 09-60873. The control room area, which is susceptible to this condition, is continuously manned; therefore making a compensatory action of a fire watch unnecessary. The finding was determined to be more than minor because the finding was associated with the mitigating systems cornerstone attribute of protection against external factors(Fire) and affected the cornerstones objective of ensuring the capability of systems that respond to initiating events to prevent undesirable consequences. The violation is associated with degradation of a fire protection feature. In accordance with IMC 0609,Significance Determination Process, Attachment 0609.04, Phase 1 - Initial Screening and Characterization of Findings, Table 3b, the inspectors determined the finding degraded the fire protection defense-in-depth strategies. Therefore, screening under IMC 0609, Appendix F, Fire Protection Significance Determination Process, was required. Using Part 1 of the Fire Protection SDP Phase 1 Worksheet in Manual Chapter0609, Significance Determination Process (SDP), the performance issue was determined to be in the post-fire safe shutdown category. The degradation rating was low based on FirstEnergy Nuclear Operating Companys (FENOCs) engineering evaluation that concluded that there were no fire induced electrical faults resulting from a control room fire that would prevent the plant from achieving and maintaining a safe shutdown in the event of a control room fire. Therefore, the finding screened as Green or of very low safety-significance in the Phase 1 Worksheet. This violation is being treated as a NCV consistent with Section VI.A of the Enforcement Policy. The cause of the finding related to the cross-cutting aspect of problem identification and resolution

03
Site:	Perry
Report	IR 05000440/2009007 Section 1R05
Date counted	Jun 30, 2009 (2009Q2)
Type:	NCV: Green
cornerstone	Mitigating Systems
Identified by:	NRC identified
Inspection Procedure:	IP 71111.05
Inspectors (proximate)	Z Falevits R Daley R Winter G Hausman D Passehl
CCA	P.2, Evaluation
INPO aspect	PI.2
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Finding - Perry - IR 05000440/2009007

14(0)16(0)1(0)2(7)3(14)4(6)5(5)6(1)7(3)8(0)301(0)402(0)403(0)404(0)501(0)13(0)

IR 05000440/2009007: 1 2 3

Finding List (Perry) @ 2009Q2

CCA Matrix: 2009Q2

	Q	CCA	Title
05000440/FIN-2008004-07	2008Q3	H.8	Loss of Configuration Control of the Hydrogen Water Chemistry Injection System Resulting in High Radiation Levels (Section 4OA3.3)
05000440/FIN-2008004-06	2008Q3	H.11 H.12	Failure to Adequately Manage Risk Associated With Working Around a Risk-Significant Underground Vault
05000440/FIN-2008004-05	2008Q3	H.7	Adequacy of Airlock Ball Valve Maintenance (4OA2.3)
05000440/FIN-2008004-04	2008Q3	H.12	Failure to Use Procedures for Work Affecting Safety
05000440/FIN-2008004-03	2008Q3	H.5	Failure to Implement a Procedurally-Required Risk Management Activity for a Protected Train (Section 1R13.2)
05000440/FIN-2008004-01	2008Q3	H.11 H.12	Impaired Fire Barrier for Safety-Related Building
05000440/FIN-2008004-02	2008Q3	H.5	Failure to Implement Compensatory Measures for a Risk-Management Activity
05000440/FIN-2008005-04	2008Q4	P.2	Failure To Report All 10 CFR 50.73 Reportable Events Associated With the Discovery of Loose Containment Grating
05000440/FIN-2008005-03	2008Q4	P.1 P.1(a)	Loss of the V-1F and V-2F Non-Vital Buses Resulting in the Loss of Technical Support Center Computers
05000440/FIN-2008005-02	2008Q4		Containment Polar Crane Trolley Seismic Restraints Did Not Meet Seismic Category I Requirements
05000440/FIN-2008005-05	2008Q4		Unplanned Unavailability of the Motor Feedwater Pump After it was Placed in 10 CFR 50.65(a)(1) status
05000440/FIN-2008005-01	2008Q4	H.7	Inspection Procedure for RPV Head Strongback Omitted Non-Destructive Testing of Structural Welds
05000440/FIN-2009002-04	2009Q1	H.2	Failure to Perform an Adequate Evaluation to Determine the Use of Respiratory Protection Equipment and/or Engineering Controls
05000440/FIN-2009006-01	2009Q1	H.2	Failure to Adhere to Procedures for Scaffold Affecting Containment Systems (Section 4OA2.1)
05000440/FIN-2009002-01	2009Q1	P.2	Ineffective Corrective Actions Associated with the Motor Feedwater Pump in 10 CFR 50.65(a)(1) Status
05000440/FIN-2009002-02	2009Q1	P.2	Inadequate Inspections on the RPV Head Strongback Lifting Device Major Load-Carrying Welds and Critical Areas
05000440/FIN-2009002-03	2009Q1	H.4 H.5	Loss of Service Air to Main Steam Line Plugs
05000440/FIN-2009002-05	2009Q1		Failure to Document All Applicable Hazards on Shipping Manifest
05000440/FIN-2009002-06	2009Q1	H.5	Maintenance on HPCS System resulted in Emergency Operating Procedure Entry
05000440/FIN-2009003-11	2009Q2	P.2	RHR System Over-pressurization Due to Failure to Implement Corrective Actions for a Condition Adverse to Quality
05000440/FIN-2009003-07	2009Q2		Employee Disregarded portal Monitor Alarm
05000440/FIN-2009007-01	2009Q2		Failure to Maintain Procedures for Post-Fire Operation of Control Room HVAC Fans and Control of Remote Shutdown Room Toolbox Inventory
05000440/FIN-2009003-09	2009Q2	H.5	Loss of Shutdown Cooling Water Flow to Reactor Vessel
05000440/FIN-2009007-02	2009Q2		Failure to Assure That Systems Structures and Components Necessary to Achieve and Maintain Hot Shutdown Conditions Were Free of Fire Damage Without Repair Actions
05000440/FIN-2009007-03	2009Q2	P.2	Failure to Provide Required Electrical Isolation for Post-Fire Safe Shutdown Electrical Circuits
05000440/FIN-2009003-04	2009Q2	H.11 H.12	Failure to Prevent Contact of Energized Components Renders RCIC System Inoperable
05000440/FIN-2009003-01	2009Q2	H.5	RCS Temperature Below Minimum Allowed by TS Due to Inadequate Station Procedures
05000440/FIN-2009003-02	2009Q2	H.2 H.5	Failure to Follow Industrial Safety Manual Results in Damage to Fuel Handling Building Roll-up Door
05000440/FIN-2009003-03	2009Q2	H.2	Inability to Operate the RHR Common Suction Line Valve
05000440/FIN-2009003-05	2009Q2	H.14	Failure to Implement Adequate Compensatory Measures Associated with Moving Burned Fuel Coincident with Workers on the 360 Platform
05000440/FIN-2009003-06	2009Q2	H.4 H.5	Failure to Barricade and Conspicuously Post a High Radiation Area
05000440/FIN-2009003-08	2009Q2		Dose Overrun on RWP 09-6035 for the Alternate Decay Heat Removal Project
05000440/FIN-2009003-10	2009Q2	H.11 H.12	Work on Wrong Relay Affecting Shutdown Cooling

Self-Identified List (Perry)

	Q	Title
05000440/FIN-2008004-08	2008Q3	Licensee-Identified Violation
05000440/FIN-2008004-09	2008Q3	Licensee-Identified Violation
05000440/FIN-2008004-10	2008Q3	Licensee-Identified Violation
05000440/FIN-2008005-06	2008Q4	Licensee-Identified Violation
05000440/FIN-2008005-07	2008Q4	Licensee-Identified Violation
05000440/FIN-2009002-07	2009Q1	Licensee-Identified Violation
05000440/FIN-2009003-14	2009Q2	Licensee-Identified Violation
05000440/FIN-2009003-12	2009Q2	Licensee-Identified Violation
05000440/FIN-2009003-13	2009Q2	Licensee-Identified Violation

[Perry Findings full list]

05000440/FIN-2009007-03

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