04-09-2009 | On September 2, 2008, the 1A Essential Service Water ( SX) pump discharge strainer differential pressure increased significantly during a pump surveillance. The 1A SX train was declared inoperable due to strainer fouling. On September 4, 2008, the 2A SX train was declared inoperable due to the inability to manually backwash the 2A SX strainer. Subsequent inspection identified the presence of live bryozoa in the Circulating Water (CW) forebays (i.e., SX pump suction source). Following cleaning of the forebays, on September 4, 2008, the 1A SX train was restored to operable status, and on September 6, 2008, the 2A SX train was restored to operable status.
On October 8, 2008, it was determined that the 2A SX train should have been considered inoperable at the same time the 1A SX train was declared inoperable, based on the 1A and 2A pumps sharing a common suction source. Since the 2A SX train was not returned to an operable status until September 6, 2008, the Limiting Condition for Operation 3.7.8, Condition A, 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time was exceeded.
The causes of this event are: 1) the site organization did not understand the bryozoa life cycle and the bryozoa deposition and growth mechanism downstream of the CW forebay traveling screens, and 2) a lack of questioning attitude existed regarding the SX strainer design to address rapid fouling challenges. The corrective actions include:
development and implementation of a lake macro-biological program; and establishment of a process for utilization of a Devil's Advocate in situations where key decisions are made for the performance of the safety related systems.
There were no actual safety consequences impacting plant or public safety as a result of this event. This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B). |
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LER-2008-001, 2A Essential Service Water Train Inoperable due to Strainer Fouling from Bryozoa Deposition and GrowthDocket Number |
Event date: |
09-02-2008 |
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Report date: |
04-09-2009 |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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Initial Reporting |
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4572008001R01 - NRC Website |
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A. Plant Operating Conditions Before The Event:
Event Date:�September 2, 2008 Event Time: 08:45 Unit: 2� MODE: 1 Reactor Power: 99.9 percent Unit 2 Reactor Coolant System (RCS) [AB] Temperature:
�581 degrees F. Pressure: 2236 psig
B. Description of Event:
There were no structures, systems or components inoperable at the beginning of the event that contributed to the severity of the event.
On September 2, 2008, the lA Essential Service Water (SX) [BI] pump discharge strainer differential pressure increased significantly and pump flow decreased during performance of the American Society of Mechanical Engineers (ASME) pump surveillance. During this surveillance, the auto backwash function of the SX strainers was secured per procedure. Operations suspended the performance of the ASME surveillance and restored strainer backwash function and the SX system flow to normal conditions. The 1A SX train was declared inoperable at 08:45 hours and Condition A of Limiting Condition for Operation (LCO) 3.7.8 was entered.
Condition A requires the inoperable unit-specific SX train to be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Subsequent inspection identified the presence of live bryozoa in the Circulating Water (CW) [KE] forebays (i.e., SX pump suction source) which caused the fouling of the 1A SX pump strainer. Following cleaning of the 1B CW forebay and aligning the 1A SX pump suction to this forebay, the 1A SX train was declared operable and LCO 3.7.8 Condition A was exited on September 4, 2008, at 23:34 hours.
On September 4, 2008, at 05:36 hours, the 2A SX train was declared inoperable due to the inability to manually backwash the 2A SX pump strainer with high strainer differential pressure. Condition A of LCO 3.7.8 was entered for the 2A SX train. Following cleaning of the lA CW forebay and restoration of the 2A SX strainer power supply, the 2A SX train was declared operable on September 6, 2008 at 03:38 hours and Condition A was exited.
Braidwood's SX system is designed such that the lA SX and the 2A SX trains take suction from the lake via the Unit 1 CW forebays, and the 1B SX and the 28 SX trains take suction from the lake via the Unit 2 CW forebays.
On October 8, 2008, during a past operability review, it was determined that the 2A SX train should have been considered inoperable at the same time the 1A SX train was declared inoperable. This conclusion was based on the 1A and 2A SX pumps sharing a common suction source (i.e, Unit 1 CW forebays). Therefore, the 2A SX train was considered inoperable as of 08:45 hours on September 2, 2008. Since the 2A SX train was not returned to an operable status until 03:38 hours on September 6, 2008, the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time of LCO 3.7.8 Condition A was exceeded.
Therefore, this event is reportable under 10 CFR 50.73(a)(2)(i)(B), any operation or condition which was prohibited by the Technical Specifications.
C. Cause of Event
Following the 1A SX strainer fouling events on September 2, 2008, a sample of the fouling material was collected.
The sample confirmed the presence of live bryozoa in the CW forebays. Bryozoans are small, aquatic animals that grow on submerged surfaces and can grow and branch and form mats that are loosely attached to surfaces and itself. As a result, both units' CW forebays were inspected and cleaned. Additionally, a temporary modification was completed adding safety related essential power [EB] to the SX strainer backwash system.
The CW forebay inspection identified live bryozoa colonies in all six CW forebays (1A/B/C and 2A/B/C). The inspection results indicated that significant bryozoa mass existed in the Unit 1 forebays immediately upstream of the intakes that supply the 1A and 2A SX pumps. The bryozoa mass in the Unit 2 forebays immediately upstream of the intakes that supply the 1B and 2B SX pumps was approximately 30% less than the Unit 1 side.
Live bryozoa was discovered previously in the CW forebays in October 2005 and in September 2002. During the previous events, all forebays indicated the presence of bryozoan colonies to varying degrees. In those instances, however, the amount of bryozoa present did not result in failure of flow rate surveillances, or a declaration of system inoperability. The corrective actions following the 2005 bryozoa event included mechanical cleaning of the forebays, completion of a lake bryozoa study for control and mitigation of bryozoa, development of an adverse condition monitoring plan, and additional forebay inspections prior to and after the summer months.
Following the events of September 2008, a root cause evaluation was performed. This evaluation determined two causes of the 2008 event:
1. The site organization did not understand the bryozoa life cycle and the bryozoa deposition and growth mechanism downstream of the CW forebay traveling screens. The previously established bryozoa monitoring plans did not inspect for byrozoa during peak growth periods, and sampling skids installed on the bar racks just outside the forebays were not indicative of the bryozoa growth and deposition near the SX pump intakes.
2. A lack of questioning attitude existed regarding the SX strainer design's ability to address rapid fouling challenges. Previous reviews for re-affirming the SX strainer design basis did not fully consider what could occur to cause rapid strainer fouling events nor how these events could negate the compensatory actions that the station could take to restore the strainers.
D. Safety Consequences:
There were no actual safety consequences as a result of this event. Both units remained at 100% power and non-essential power [EA] was available to support the SX strainer backwash function.
The impacts of bryozoa on safety related heat exchangers were reviewed using current and five year historical data. There has been no reporting of live bryozoa in safety related plant systems. Periodic maintenance inspections of the safety related heat exchangers confirm that current chemical treatment, flushing, and operating practices are sufficient to maintain equipment in a condition that meets the requirements of NRC Generic Letter (GL) 89-13, "Service Water System Problems Affecting Safety-Related Equipment," and ASME Code Inservice Inspection (ISI) standards.
The evaluation of the effects of the bryozoa fouling indicates that both units and trains of SX strainers were capable of mitigating the effects of bryozoa into the SX system when non-essential power was maintained to the SX strainer backwash components.
Further analysis, performed to support the Significance Determination Process, determined the SX system was capable of performing its safety function. Therefore, this event did not result in a safety system functional failure.
The risk evaluation showed that the incremental increase in core damage probability was less than 1E-06 and therefore considered to be of very low risk significance. This risk evaluation is being reviewed by the NRC.
�
Corrective Actions:
Corrective actions to prevent recurrence include:
1. Development and implementation of a lake macro-biological program, to include; 1) monitoring, 2) inspection, and 3) mitigation. This will provide the strategies and bases for monitoring of bryozoa and other biological challenges in the lake and the forebays, inspections of forebays, and forebay cleaning threshold ensuring that the GL 89-13 program requirements are met.
2. Establishment of a process for utilization of a Devil's Advocate in situations where key decisions are made for the performance of the safety related systems.
Additional Corrective Actions include:
1. Installation of a mechanical debris removal system such as a sparger to provide flushing capability to prevent accumulation of bryozoa (and other materials) downstream of the traveling screens during summer months.
2. Evaluate use of a non-intrusive forebay monitoring system for monitoring bryozoa growth and deposition in the forebays.
3. Develop actions to improve the design of the SX pump discharge strainers by providing the SX pump discharge strainers' power supply, alarms and controls with a permanent safety related power source.
4. Development of a case study of this event, and provide in continuing training for appropriate Braidwood Station personnel.
Previous Occurrences:
There have been no similar Licensee Event Report events at Braidwood Station in the last three years.
Two other events occurred at Braidwood Station relating to SX strainer differential pressure and bryozoa growth in the circulating water forebays:
- September 2002: During forebay inspections, silt buildup and bryozoa growth was found.
- October 2005: Bryozoan growth discovered following SX strainer differential pressure alarms. An equipment apparent cause evaluation was performed. Corrective actions included mechanical cleaning of the forebays, completion of a lake bryozoa study for control and mitigation of bryozoa, development of an adverse condition monitoring plan, and additional forebay inspections prior to and after the summer months.
. Component Failure Data:
Manufacturer Nomenclature Model Mfg. Part Number N/A N/A N/A N/A
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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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