05000457/LER-2009-003

06-15-2010

identified two occurrences in which residual heat removal (RH) suction vent and drain valves were open while the containment sump isolation valve (SI8811) was capable of automatically opening during Operating Modes 1 through 4.

These occurrences were Unit 2 RH Train B (2SI8811B) on December 7, 2006, and Unit 2 RH Train A (2SI8811A) on September 30, 2009. The events occurred during on-line planned work windows for the RH suction lines to replace the water as a dose reduction effort and to perform required valve stroke tests on the SI8811 valve for the respective train.

The SI8811 valve receives an automatic open signal during a loss of coolant accident (LOCA) to switch the train-specific emergency core cooling system pumps' suction to the sump. Braidwood Operating Procedure (BwOP) RH-4, "Draining of the RH System," was initiated to drain the RH suction line. BwOP RH-4 requires the SI8811 valve to be closed, but it does not require it to be de-energized. Therefore, during the draining evolution, the SI8811 valve was still capable of opening in response to a LOCA. This would create a leak path of radioactive sump water outside of containment into the auxiliary building while the drain and vent valves were open. The cause was determined to be an inadequate drain procedure in that it did not require the SI8811 to be de-energized while the RH suction line was breached. Corrective actions include revising the procedure and performing an extent of condition assessment. This condition was subsequently determined to be an unanalyzed condition; however there were no actual safety consequences since at no time was an SI8811 valve open when the suction line was breached.

LER-2009-003, Drain Procedure for ECCS Suction Line Creates an Unanalyzed Condition Due to Inadequate Configuration Requirements
Docket Number
Event date:	11-10-2009
Report date:	06-15-2010
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
4572009003R01 - NRC Website
v • d • e

Background:

The emergency core cooling system (ECCS) [BQ/BP] has two 100% redundant trains. Each train has three phases of operations: injection, cold leg recirculation, and hot leg recirculation. In the injection phase, borated water from the refueling water storage tank (RWST) is injected into the reactor coolant system (RCS) [AB] through the cold legs.

When sufficient borated water has been removed from the RWST to maintain the reactor subcritical and the sumps can supply the required net positive suction head to the ECCS pumps, suction is switched to the sumps for cold leg recirculation. rhis is accomplished, in part, by an RWST low level signal automatically opening the sump isolation valve (i.e., SI8811) for each ECCS train, Though normally the SI8811 remains open during a design basis loss of coolant accident (LOCA), the valve is also considered an isolation valve in the event of a faulted line outside of containment during the accident should the line need to be isolated.

Technical Specification (TS) 3.5.2. "ECCS - Operating." is applicable in Modes 1 through 4 and allows for one train of ECCS to be inoperable for seven days. To faciiitate maintenance on SIII veinal�aciivities on the low head subsystem.

of the ECCS (i.e., residual heat removal (RH) [BP]), Braidwood Operating Procedure (Bw0P) RH-4, "Draining the RH System- drains the appropriate section/s of piping, when needed. BwOP RH-4 does not restrict its use to any particular operating mode. However, historically, maintenance on the RH system which required draining was performed in a refueling outage. BwOP RH-4 requires the S

Licensee Event Report

Docket Number

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 |

		Reporting criterion
05000410/LER-2009-001	Momentary Loss of Control Power to High Pressure Core Spray, Pump Due to Degraded Fuse Block Connection	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000266/LER-2009-001	Component Coolina Water PumD Inoperable In Excess of Technical Specification Allowed Completion Time	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000263/LER-2009-001	Containment Overpressure Not Ensured in the Appendix R Analysis	10 CFR 50.73(a)(2)(ii)
05000250/LER-2009-001	Procedure Inadequacy Causes Control Room Ventilation Isolation Technical Specification Noncompliance	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000237/LER-2009-001	Common Mode Failure of Reactor Building Isolation Dampers	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000530/LER-2009-001	Manual Reactor Trip Due to a Loss of Instrument Air to the Containment Building
05000457/LER-2009-001	Reactor Trip on Over Temperature Delta Temperature due to a Signal Spike on One Channel With Another Channel Placed in the Tripped Condition for Surveillance Testing	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000413/LER-2009-001	Both Trains of Chemical and Volume Control, Auxiliary Feedwater and Containment Spray Systems were Inoperable due to a Component Failure	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000412/LER-2009-001	Equipment Operability for Steam Generator Tube Rupture Safety Analysis Not Met	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vi)
05000461/LER-2009-001	Safety Function Lost Due to Capacitor Failure on Circuit Card	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000382/LER-2009-001	Waterford 3 Steam Electric Station 05000382 1 OF 3
05000370/LER-2009-001		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000346/LER-2009-001	Containment Air Cooler Fans Inoperable Due to Misapplication of Potter and Brumfield Rotary Relays	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000336/LER-2009-001	Reactor Trip Due to High Pressurizer Pressure	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000305/LER-2009-001		10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000281/LER-2009-001	Manual Reactor Trip Initiated to Replace a Rod Control Data Logging Card	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000261/LER-2009-001	Emergency Diesel Generator Inoperable in Excess of Technical Specifications Allowed Completion Time	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000220/LER-2009-001	Failure to Implement Required Technical Specification Actions Associated with Failed Surveillance Test	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000389/LER-2009-001	Unit 2 Main Feedwater Isolation Valves Stroke Time Potentially Affected by Temperature	10 CFR 50.73(a)(2)(I)(B)
05000321/LER-2009-001	Pump Suction Swap for HPCI and RCIC Non-Conservative With Respect To Technical Specification Requirements	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000334/LER-2009-001	Surveillance Test Inadvertently Violates Technical Specification 3.6.1 for Containment Operability	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000369/LER-2009-001	III Duke Energy® BRUCE H HAMILTON Vice President McGuire Nuclear Station Duke Energy Corporation MGO1VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.com June 24, 2009 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555 Subject: Duke Energy Carolinas, LLC McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369, 50-370 Licensee Event Report 369/2009-01, Revision 0 Problem Investigation Process (PIP) M-09-02216 Pursuant to 10 CFR 50.73 Sections (a) (1) and (d), attached is Licensee Event Report 369/2009-01, Revision 0, regarding the past inoperability of the Nuclear Service Water System "A" Trains due to potential for strainer fouling. This report is being submitted in accordance. with 10 CFR 50.73 (a) (2) (i)- (B), an Operation Prohibited by Technical Specifications, and 10 CFR 50.73 (a) (2) (v) (B), any Event. or Condition That Could Have Prevented Fulfillment of the Safety Function. This event is considered to be of no significance with respect to the health and safety of the public. There are no regulatory commitments contained in this LER. If questions arise regarding this LER, contact Rick Abbott at 980-875-4685. Very truly yours, Bruce H. Hamilton Attachment www.duke-energy.corn m U.S. Nuclear Regulatory Commission Date Page 2 CC: L. A. Reyes, Regional Administrator •U.S. Nuclear Regulatory Commission, Region.II Sam Nunn Atlanta Federal Center •61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303 J. H. Thompson, Jr. (Addressee Only) Senior Project Manager (McGuire) U.S. Nuclear Regulatory Commission Mail Stop 0-8G9A Washington, DC 20555 J. B. Brady Senior Resident Inspector U.S. Nucle'ar Regulatory Commission- McGuire Nuclear Station B. 0. Hall, Section Chief Radiation Protection Section 1645 Mall Service Center. Raleigh, NC 27699 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104t EXPIRES: 08/31/2010 (9-2007) Estimated burden per response to comply with this mandatory collection request: 50 hours. Repoded lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information (See reverse for required number of collection does not display a currently valid OMB control number, the NRC may not conduct or digits/characters for each block) sponsor, and a person is not required to respond to, the information collection. LICENSEE EVENT REPORT (LER) 1. FACILITY NAME 2. DOCKET NUMBER I 3. PAGE _McGuire Nuclear Station, . 0369 8 Unit 1 05000- OF 4. TITLE Nuclear Service Water System (NSWS)d "A" Trains Past Inoperable when aligned to the Standby Nuclear Service Water Pond due to'corrosion. (SNSWP)	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
05000456/LER-2009-001	Steam Generator Tube Exceeding Plugging Criteria Remained In Service During Previous Cycle	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000395/LER-2009-001	Inadequate Procedure Results In EDG Not Obtaining Maximum Load Required By Technical Specification	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000336/LER-2009-002	Reactor Coolant System Pressure Boundary Leakage	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000373/LER-2009-002	Loss of Shutdown Cooling Due to Spurious Closure of the Shutdown Cooling Suction Isolation Valve	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
05000382/LER-2009-002	Waterford 3 Steam Electric Station 05000382 10OF 4
05000278/LER-2009-002	Inoperable 'A' Wide Range Neutron Monitor Results in Condition Prohibited by Technical Specifications	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000287/LER-2009-002	Unit 3 Trip Due to Generator Phase Differential Lockout	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000263/LER-2009-002
05000412/LER-2009-002	Unacceptable Indications Identified During Reactor Vessel Head Inspection	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000354/LER-2009-002	As Found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000346/LER-2009-002	Vibration Induced Failure of Temperature Instrument Results in Operation above Licensed Power Limit	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000261/LER-2009-002	Failure to Complete Technical Specifications Required Action Within the Allowed Completion Time	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000334/LER-2009-002	Feedwater Isolation Initiates Auxiliary Feedwater System During Refueling Shutdown	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000254/LER-2009-002	Quad Cities Nuclear Power Station Unit 1 05000254 1 OF 5	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000305/LER-2009-002	Steam Exclusion Door Blocked Open During Maintenance Activities	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000250/LER-2009-002	Turkey Point Unit 3 05000250 1 of 10	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000220/LER-2009-002	High Pressure Coolant Injection System Initiation Following a Manual Turbine Trip Due to High Turbine Bearing Vibrations	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000298/LER-2009-002	Manual Scram On Low Water Level Caused By Turbine Trip From Hydraulic Fluid Leak	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000305/LER-2009-003	Containment Spray Pump A Inoperable At Degraded Voltage Protection Setpoint	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000395/LER-2009-003	..Potential Loss of Residual Heat Removal System Safety Function In Mode 4 Due To An Unanalyzed Condition0	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
05000389/LER-2009-003	RCP 2B2 Lower Seal Cavity Line Leak	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000323/LER-2009-003	Containment Sump Recirculation Valve Position Interlock Failure Due to Inadequate Testing
05000263/LER-2009-003		10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000261/LER-2009-003	Manual Reactor Trip Due to Failure of 'A' Steam Generator Level Module	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000440/LER-2009-003	Reactor Recirculation Pump Failure Results in Manual Reactor Protection System Actuation	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000361/LER-2009-003	Pressurizer Auxiliary Spray Failed Inservice Test	10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
05000457/LER-2009-003	Drain Procedure for ECCS Suction Line Creates an Unanalyzed Condition Due to Inadequate Configuration Requirements	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000237/LER-2009-003	Emergency Diesel Generator Oil Leak	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
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05000457/LER-2009-003

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