06-13-2008 | On March 28, 2008, with Unit 1 in a refueling outage, an Engineer identified a potential operability issue with the containment floor drain sump flow monitor (i.e., 1RF008). He noticed that the sump's cover was flush with the containment floor and had two instrument tubetrack penetrations through its cover with each having an approximately five linear inch narrow gap on its perimeter. These gaps, open to the sump below, would allow Reactor Coolant system ( RCS) leakage to flow directly into the sump and bypass the collection system and weir box. With this bypass path, the 1 RF008 could potentially not fulfill its design function to detect a one gpm RCS leak within one hour. An investigation revealed that the original design and construction of 1RF008 in the 1976 timeframe should have had it installed three inches higher such that the sump cover would be three inches above floor elevation. This installation detail would have ensured, by being three inches higher than the floor, that an RCS leak to the containment floor in the vicinity of the containment sump cover would be directed to the 1RF008 leakage collection system and weir box and not allowed to bypass it through the penetration openings in the cover. Due to the time frame the installation error was made (i.e., 1976), the investigation was unable to determine the cause for this installation error. The 1RF008 penetration openings have been blocked such that RCS leakage could not enter the sump via the sump cover and the design drawings for the Unit 1 and Unit 2 RF008 will be revised to indicate the as-built installation. |
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LER-2008-001, Technical Specification Non-Compliance of Containment Sump Monitor Due to Improper Installation During Oriainal constructionDocket Number |
Event date: |
03-28-2008 |
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Report date: |
06-13-2008 |
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4542008001R00 - NRC Website |
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A. Plant Condition Prior to Event:
Event Date: March 28, 2008 Unit 1 was in Mode 6, Refueling No structures, systems, or components were inoperable at the start of this event that contributed to the initiation or mitigation of this event.
Background:
This report involves the Unit 1 Reactor Coolant System (RCS) [AB] leakage detection Instrumentation.
The Limiting Condition for Operations (LC[}) for Unit 1 Technical Specifications (TS) 3.4.15, "RCS Leakage Detection Instrumentation," requires one containment sump (RF) [IJ] monitor and one containment atmosphere particulate radioactivity monitor (PR) [IL] (i.e., 1PRO11A). The RF monitor consists of the containment floor drain sump flow monitor (i.e., 1RF008) and the reactor cavity sump flow monitor (i.e., 1RF010). TS 3.4.15 is applicable in Modes 1 through 4. If the required RF sump is inoperable, Condition A requires the performance of the RCS leak rate surveillance once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restoration to operable status within 30 days.
For the Unit lcontainment sump monitor to accurately quantify RCS leakage, the RCS leakage is collected and directed to the weir (measurement) box in each sump. This allows the detection of a RCS leak of one gallon per minute (gpm) within one hour.
B. Description of Event:
On March 28, 2008, with Unit 1 in a refueling outage, an Engineer (non-licensed) identified a potential operability issue with the 1RF008. He noticed that the sump's cover was flush with the containment floor and had two instrument tubetrack penetrations through its cover with each having an approximately five linear inch narrow gap on its perimeter. These gaps, open to the sump below, would allow RCS leakage to flow directly into the sump and bypass the collection system and weir box. The issue was placed into the Corrective Action Program and the condition was corrected by installing plates around each of the penetration gaps to block the flow path. This was completed prior to entering the mode of applicability for TS 3.4.15. In addition, an action was assigned to the Engineering Department to assess the status o past operability of the 1RF008.
On April 14, 2008, the past operability assessment concluded that the tubetrack gaps caused the 1RF008 to be inoperable dating back to installation. RCS leakage flowing through these gaps could, adversely impact the 1RF008 design requirement to detect a one gpm leak within an hour.
An investigation revealed that the original design and construction of 1RF008 in the 1976 timeframe should have had it installed three inches higher, such that the sump cover would be three inches above the floor elevation. This installation detail would have ensured, by being three inches higher than the �NRC FORM 366A (9-2007) PRINTED ON RECYCLED PAPER floor, that an RCS leak to the containment floor in the vicinity of the containment sump cover would be directed to the 1 RF008 leakage collection system and weir box and not allowed to bypass through the penetration openings in the cover.
The 1 RF008 was in an inoperable condition longer than allowed by TS 3.4.15. 10 CFR 50.73 (a) requires the reporting of events that occurred within three years from the time of discovery.
Consequently, since this condition existed since April 14, 2005, then it is reportable to the NRC in accordance with 10 CFR 50.73 (a)(2)(i)(B). The 60 day time clock for submitting a Licensee Event Report to the NRC began on April 14, 2008, when it was concluded the 1 RF008 was inoperable in the past.
The same installation error for 2RF008 occurred on Unit 2, however a GEMS level instrumentation modification installed in Spring 2004 changed the design such that all RCS leakage is measured regardless of the flow path taken to the sump.
C. Cause of the Event:
Due to the time frame the installation error was made (i.e., 1976), the investigation was unable to determine the cause for this installation error. The most probable cause was inadequate quality control oversight of the installation process.
Throughout Unit 1 service life there were several design changes to various aspects of 1 RF008, however the review of the 1 RF008 design during these modifications did not identify this installation error. These missed opportunities to identify this deficiency are attributable to human performance weaknesses such as inattention to detail and having too narrow a focus of the task.
In the 2004 on Unit 2 timeframe, during a design change review for the GEMS level instrumentation modification, it was identified that this three inch installation discrepancy existed. However, only the structural impact was reviewed and it was found to be acceptable. The adverse impact on operability of the 1 RF008 was not recognized.
D. Safety Analysis:
There was minimal safety significance to this condition. A RCS leak in Modes 1 through 3 and most of Mode 4 would flash to steam. Most of this steam would be condensed in the Reactor Containment Fan Cooler System [BK] and the condensation directed to the 1RF008 collection system as designed.
In Mode 4 RCS temperature ranges where RCS may not flash completely to steam then only a leak in the vicinity of the 1RF008 cover could have had any significant portion of its flow diverted through the open gaps. Since the identified bypass area is small in relation to intended design path area to the collection system, it is reasonable to assume that a much greater portion of the leakage would be correctly collected and directed to the weir box. If one conservatively assumes of 50 percent of the leakage flow was diverted through these gaps, then the 1RF008 would not detect a one gpm leak rate � until the actual leak was at two gpm. Based on engineering judgment, this is still considered small enough for Operators to take appropriate actions to place Unit 1 in a safe condition (i.e., Mode 5) The TS required 1PRO11A was capable of detecting a RCS leak of one gpm within an hour. During the brief periods of time when both 1RF008 and 1PRO11A were inoperable, Operators had several additional means to identify RCS unidentified leakage. These include the RCS Volume Control Tank level indicators, post accident containment sump [IP] level instruments, containment pressure and temperature indicators, and Pressurizer [AB] Level indicators.
E. Corrective Actions:
The 1RF008 penetration openings were blocked such that RCS leakage could not enter the sump via the sump cover.
The design drawings for the Unit 1 and Unit 2 RF008 will be revised to indicate the as-built installation.
The Engineering lessons learned from the missed opportunities in identifying this condition will be communicated to the Engineering staff.
F.Previous Occurrences:
Issue Report (IR) 113088 dated June 24, 2002, describes incorrect installation issue with the RF008 instrumentation.
IR 522160 dated August 21, 2006, describes the removal of the six inch lip at the bottom of the ECCS sump outer screen, which could result in online RCS leakage spilling into the ECCS sump instead of the RF sump.
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05000413/LER-2008-001 | | 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 | 05000334/LER-2008-001 | Control Room Envelope Air Intake During Normal Operation Higher Than Assumed In Design Basis Accident Dose Calculations | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2008-001 | Unit 1 Manual Reactor Trip due to Main Turbine Vibrations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000272/LER-2008-001 | Inadvertent Start of an Emergency Diesel Generator During Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000251/LER-2008-001 | Manual Reactor Trip due to High Level in the 4A Steam Generator | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000247/LER-2008-001 | Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Loss of Feedwater Flow as a Result of Feedwater Pump Speed Control Malfunction | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000530/LER-2008-001 | Manual Reactor Trip when Removing a Degraded CEDM MG Set from Service | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000457/LER-2008-001 | 2A Essential Service Water Train Inoperable due to Strainer Fouling from Bryozoa Deposition and Growth | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000454/LER-2008-001 | Technical Specification Non-Compliance of Containment Sump Monitor Due to Improper Installation During Oriainal construction | | 05000440/LER-2008-001 | ' Condition Prohibited by Technical Specifications Due to Unrecognized Reactor Core Isolation Cooling Inoperability | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000483/LER-2008-001 | Containment Cooler Inoperability | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000412/LER-2008-001 | Unplanned Actuation of the Auxiliary Feedwater System During Plant Startup | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000374/LER-2008-001 | High Pressure Core Spray System Declared Inoperable Due to Failed Room Ventilation Supply Fan | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000323/LER-2008-001 | Reactor Trip Due to Main Electrical Transformer Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2008-001 | Pressurizer PORV and Reactor Coolant System Vent Valves Appendix R Spurious Operation Concern | | 05000271/LER-2008-001 | Crane Travel Limit Stops not Installed as Required by Technical Specifications due to an Inadequate Procedure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000269/LER-2008-001 | Gas Void Found in High Pressure Injection System Suction Piping | | 05000263/LER-2008-001 | | | 05000261/LER-2008-001 | Appendix R Pathway Impassable due to Lock Configuration | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | 05000361/LER-2008-001 | Valid actuation of Emergency Feedwater system following Main Feedwater pump trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000335/LER-2008-001 | Unattended Ammunition Discovered Inside Protected Area | | 05000456/LER-2008-001 | Technical Specification Non-Compliance Due to Inadequate Design of Auxiliary Feedwater (AF) Tunnel Access Covers Causing AF Valves Within the Tunnel to be Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000423/LER-2008-001 | Postulated Fire Scenario Results in Unanalyzed Condition - Pressurizer Overfill | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000369/LER-2008-001 | Potential Failure of Containment Isolation Valves (CIV) to Remain Fully Closed and Ino erable loner than allowed bCTechnical S ecification 3.6.3. | | 05000220/LER-2008-002 | Manual Reactor Scram Due to Loss of Reactor Pressure Control | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000261/LER-2008-002 | Manual Reactor Trip due to High Turbine Vibrations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000270/LER-2008-002 | Main Steam Relief Valves Exceeded Lift Setpoint Acceptance Band 050002 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2008-002 | 5 . Blocked Open Steam Exclusion Door Results in Postulated Inoperability of Safety Systems | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000336/LER-2008-002 | Unplanned LCO Entry - Three Charging Pumps Aligned for Injection With the Reactor Coolant System Temperature Less than 300 Degrees F. | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000354/LER-2008-002 | BLOWN lE INVERTER MAIN FUSE WITH ONE EMERGENCY DIESEL GENERATOR INOPERABLE CAUSES LOSS OF CONTROL ROOM EMERGENCY FILTRATION LOSS OF SAFETY FUNCTION | | 05000395/LER-2008-002 | Control Room Normal and Emergency Air Handling Systems Inoperable Due to Pressure Boundary Breach | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000382/LER-2008-002 | Inoperable Steam Generator Narrow Range Level Channels | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000369/LER-2008-002 | 'Energy® BRUCE H HAMILTON Vice President McGuire Nuclear Station Duke Energy Corporation MGOIVP 112700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.corn August 21, 2008
U.S. Nuclear Regulatory Commission
ATTENTION: Document Control Desk
Washington, D.C. 20555
Subject: Duke Energy Carolinas, LLC
McGuire Nuclear Station, Unit 1
Docket No. 50-369
Licensee Event Report 369/2008-02, Revision 0
Problem Investigation Process No.: M-08-03862
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached
is Licensee Event Report (LER) 369/2008-02, Revision 0,
regarding the Unit 1 Reactor trip on June 26, 2008 due to
the 1B Reactor Coolant Pump Motor trip which was caused by
a failed surge capacitor.
This report is being submitted in accordance with 10 CFR
50.73 (a)(2)(iv)(A). 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 Lee A. Hentz
at 704-875-4187.
Very truly yours,
Bruce H. Hamilton
Attachment
www. duke-energy. corn U.S. Nuclear Regulatory Commission
August 21, 2008
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. F. Stang, Jr. (Addressee Only)
Senior Project Manager (McGuire)
U.S. Nuclear Regulatory Commission
Mail Stop O-8G9A
Washington, DC 20555
J. B. Brady
Senior Resident Inspector
U.S. Nuclear Regulatory Commission
McGuire Nuclear Station
B. 0. Hall, Section Chief
Radiation Protection Section
1645 Mail Service Center
Raleigh, NC 27699
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVEDBYOMB:NO.3150-0104 EXPIRES: 08/31/2010 (9-2007) Estimated burden per response to comply with this mandatory collection request: 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send ' LICENSEE EVENT REPORT (LER) 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 (See reverse for required number of means used to impose an information collection does not display a currently valid OMB control digits/characters for each block) number, the NRC may not conduct or sponsor, and a person is not required to respond to,' the information collection. 1, FACILITY NAME 2. DOCKET NUMBER I 3. PAGE 05000- ' 1 8McGuire Nuclear Station, Unit 1 _ 0369' OF .4, TITLE . . Unit 1 Reactor Trip due to the 1B Reactor Coolant Pump Motor Trip which was caused by a
failed Surge Capacitor | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2008-002 | Inoperable Emergency Closed Cooling System Results In Condition Prohibited By Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000454/LER-2008-002 | Technical Specification Non-Compliance Due to Inadequate Design of Auxiliary Feedwater (AF) Tunnel Access Covers Causing AF Valves Within the Tunnel to be Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000298/LER-2008-002 | Technical Specification Prohibited Condition Due to Safety Relief Valve Test Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000237/LER-2008-002 | Unit 2 High Pressure Coolant Injection System Declared Inoperable | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000272/LER-2008-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000361/LER-2008-002 | Disturbance on the Pacific DC Intertie cause offsite power frequency to dip below operability limits | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000362/LER-2008-003 | Missed TS completion time results in TS Violation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000220/LER-2008-003 | Power Supplies for Drywell Pressure Indication not Qualified for Required Post-Accident Operating Duration | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000529/LER-2008-003 | Technical Specification - Limiting Condition for Operation 3.0.3 for Greater Than 1 Hour | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2008-003 | | | 05000263/LER-2008-003 | | | 05000423/LER-2008-003 | Automatic Reactor Trip During Shutdown for Refueling Outage 3R12 ., | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000251/LER-2008-003 | . Class 1 Weld Leak Due to Fatigue and Completion of Technical Specification Required Shutdown | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000282/LER-2008-003 | Loss of AFW Safety Function and Condition Prohibited by Technical Specifications Due to Mispositioned Isolation Valve | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000286/LER-2008-003 | Automatic Actuation of Emergency Diesel Generator 33 During Surveillance Testing Caused by .Inadvertent Actuation of the Undervoltage Sensing Circuit on 480 Volt AC Safeguards Bus 5A | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000361/LER-2008-003 | Disturbance on the Pacific DC Intertie cause offsite power frequency to dip below operability limits | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000305/LER-2008-003 | Door Bottom Seal Failure Results in Inoperability of Control Room Ventilation System | 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 |
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