On September 16, 2008, at 00:03 Mountain Standard Time ( MST), Unit 2 was at 100 percent power when the 120 VAC class lE channel C instrumentation and control distribution panel was de-energized to troubleshoot and repair the associated 120 VAC Class1E inverter that had automatically transferred the panel's power supply to the backup voltage regulator on September 15, 2008. This resulted in a loss of the required redundant position indication for 67 of the 89 Control Element Assemblies ( CEAs). As a result, LCO 3.0.3 was entered, which required initiation of action within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. LCO 3.0.3 was exited at 01:31 after the required redundant CEA position indication was restored.
No power decrease was initiated.
The root cause investigation of the inverter transfer is in progress. Troubleshooting identified the inverter's DC-DC converter circuit board (+)15 VDC voltage regulator did not meet vendor acceptance criteria. The board was replaced and the inverter was returned to OPERABLE status.
DC converter and resulted in the unit remaining in LCO 3.0.3 for longer than one hour on April 24, 2008. |
All times are Mountain Standard Time (MST) and approximate unless otherwise indicated.
1. REPORTING REQUIREMENT(S):
This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) to report a condition prohibited entered Limiting Condition for Operation (LCO) 3.0.3 and remained in LCO 3.0.3 for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
TS LCO 3.1.5, Control Element Assembly (CEA) Alignment, (EIIS: AA), does not have a condition for multiple CEAs within a group that have less than two OPERABLE CEA position indicators. This condition requires entry into LCO 3.0.3, which requires action be initiated within 1-hour to place the unit in MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
2. DESCRIPTION OF STRUCTURE(S), SYSTEM(S) AND COMPONENT(S):
Class 1E 120 VAC Instrument (EllS: EF) Power System (PN) The PN system consists of four redundant independent sub-systems each consisting of an inverter (EIIS: INVT) that converts 125 VDC (EIIS Code: EJ) supply to 120 VAC, a transfer switch (EIIS: ASU), a backup voltage regulator (regulating transformer) (EIIS: XFMR) and a 120 VAC distribution panel (EIIS: PL). In Units 2 and 3, the transfer switch will automatically transfer loads from the inverter to the voltage regulator during a faulted condition on the inverter. In Unit 1, the transfer switch is manually actuated to transfer loads. Each of the four sub-systems provides class lE 120 VAC power to one of the four channels of the reactor protection system (EIIS: JC) and engineered safety features actuation system instrumentation and controls (EIIS:
JE).
CEA Position Indication Each CEA has three separate position indications. A CEA pulse counter (EIIS: CTR) determines the CEA position by providing a 0.75 inch position change for each step change signal received from the plant computer but does not directly measure CEA position. Actual movement in CEA position is indicated on the Reed Switch Position Transmitters (RSPTs) (EIIS: ZT) which feed indication to CEA position processors. Two RSPTs provide CEA position indication by using reed switches located every 1.5 inches which are activated by a magnet assembly located at the top of the CEA extension shaft.
The 120 VAC class1E channel C instrumentation and control distribution panel 2E-PNC-D27 provides power for one of the two RSPTs (RSPT channel 2) and the pulse counter for 67 CEAs.
The remaining 22 CEAs receive power for their respective pulse counters and channel 2 RSPTs from 2E-PND-D28. RSPT1 position indications are powered from the A and B class 1E distribution panels.
3. INITIAL PLANT CONDITIONS:
On September 15, 2008, Unit 2 was in MODE 1 at 100 percent power. There were no other structures, systems, or components that were inoperable at the time of the event that contributed to the event.
4. EVENT DESCRIPTION:
On September 15, 2008, at 04:22, a transient on class1E Inverter 2E-PNC-N13 resulted in the automatic transfer of the power supply for the 120 VAC class1E channel C instrumentation and control distribution panel 2E-PNC-D27 from the inverter to the alternate power supply, Class lE 480 / 120 VAC voltage regulator 2E-PNC-V27. The unit entered LCO 3.8.7 (Inverters-Operating) Condition A for the inoperable inverter, which required restoration of the inverter to OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The subsequent inverter troubleshooting plan required distribution panel 2E-PNC-D27 to be de energized which requires entry into LCO 3.0.3 because de-energizing the panel results in only one of the two required CEA positions indicators for 67 of the 89 CEAs being OPERABLE. De energizing the panel also requires entry into LCO 3.8.9 (Distribution Systems-Operating) Condition B for the inoperable instrument bus. This LCO action required restoration of the bus to OPERABLE within two hours.
At 00:03 on September 16, 2008, APS operating staff de-energized panel 2E-PNC-D27 to perform the required troubleshooting and the unit entered LCOs 3.0.3 and 3.8.9 Condition B.
At 00:37, power was restored to panel 2E-PNC-D27 from its backup voltage regulator supply and the unit exited LCO 3.8.9 condition B. Following restoration of power, additional time was required to reset CEA pulse counter position indications and to perform surveillance testing to verify two CEA position indications per CEA were OPERABLE. After these actions were completed, the unit exited LCO 3.0.3 at 01:31 (one hour and 28 minutes after the LCO 3.0.3 entry).
At 04:22 the unit entered LCO 3.8.7 Condition B to be in Mode 3 in six hours because the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> completion time for Condition A had elapsed.
After completion of corrective maintenance and testing, inverter 2E-PNC-N13 was declared OPERABLE at 08:16 on September 16, 2008 and the unit exited LCO 3.8.7 Conditions A and B.
During the periods while Unit 2 was in LCO 3.0.3 and 3.8.7 Condition B, preparations were initiated to shutdown, but no power reductions were made.
5. ASSESSMENT OF SAFETY CONSEQUENCES:
The event did not result in any challenges to the fission product barriers or result in the release of radioactive materials. The plant remained within safety limits throughout the event. The primary system and secondary pressure boundary limits were not approached and no violations of the specified acceptable fuel design limits (SAFDL) occurred. No Engineered Safety Feature actuations occurred and none were required. There were no adverse nuclear safety consequences as a result of this event and the event did not adversely affect the safe operation of the plant or health and safety of the public. The event did not result in a transient more severe than those analyzed in the updated Final Safety Analysis Report Chapters 6 and 15.
There were no other failures that rendered a train of a safety system inoperable. The condition would not have prevented the fulfillment of the safety function, and the condition did not result in a safety system functional failure as defined by 10 CFR 50.73(a)(2)(v).
6. CAUSE OF THE EVENT:
The root cause investigation of the automatic transfer of panel 2E-PNC-D27 to its backup voltage regulator supply is in progress. Troubleshooting identified the inverter's DC-DC converter circuit board (+)15 VDC voltage regulator (Silicon General #SG7815ACK) on the DC-DC converter circuit board (Elgar #62813540) did not meet vendor specifications.
If information is subsequently developed that would significantly affect a reader's understanding or perception of this event, a supplement to this LER will be submitted.
7. CORRECTIVE ACTIONS:
The degraded circuit board was replaced and normal power was restored to the distribution panel.
Any additional corrective actions taken as a result of this event will be implemented in accordance with the APS corrective action program.
8. PREVIOUS SIMILAR EVENTS:
Since 2005, five other failures of the class 1E 120 VAC inverters have occurred.
panel 2E-PNA-D25 automatically transferred from the 2E-PNA-N11 inverter to the voltage regulator 2E-PNA-V25. The investigation for this event is included as part of the investigation for the September 16th event reported in this LER. This event did not require entry into LCO 3.0.3 because RSPT2 and pulse counter CEA position indicators remained OPERABLE.
On July 23, 2008, a Unit 2 inverter 2E-PNB-N12 failed and power to the panel 2E-PNB-D26 automatically transferred from the inverter to the voltage regulator 2E-PNB-V26. Trouble shooting found a blown A2 bridge fuse, one failed silicon controlled rectifier (SCR), and three degraded SCRs. The SCRs and the fuse were replaced. The SCRs are undergoing laboratory testing to determine the cause of the failure. The respective class bus remained energized throughout the troubleshooting and repair. The corrective actions for this event would not have prevented the conditions reported in this LER.
On April 24, 2008, Unit 1 inverter 1E-PNC-N13 failed and power to the class distribution panel 1E-PNC-D27 was manually transferred from the inverter to the class voltage regulator 1E-PNC- V27. Troubleshooting found a failed (-)15 VDC voltage regulator in the DC-DC converter card.
This event was reported in LER 05000528-2008-002-00 because Unit 1 entered LCO 3.0.3 for longer than one hour on two occasions during troubleshooting and repair. Restoration and verification of CEA position indications precluded exit of the LCO within one hour.
On October 30, 2005, a Unit 1 inverter 1E-PNB-N12 failed and power to the class distribution panel 1E-PNB-D26 was manually transferred from the inverter to the class voltage regulator 1E- PNB-V26. Troubleshooting found internal short circuits inside output filter capacitors that were the result of a manufacturing process defect. This event did not result in an LCO 3.0.3 entry because only RSPT1 position indicators were affected; RSPT2 and pulse counter CEA position indicators remained OPERABLE. This event was reported in LER 05000528-2005-008-01 as a condition prohibited by Technical Specifications because the defective capacitors had been installed for six years. The corrective actions for this event would not have prevented the conditions reported in this LER for the September 16th event.
On May 5, 2005, with the reactor de-fueled, a Unit 2 inverter 2E-PNB-N12 failed and power to the class distribution panel 2E-PNB-D26 automatically transferred from the inverter to the class voltage regulator 2E-PNB-V26. Troubleshooting found the A2 bridge fuse was blown, three SCRs were degraded, and the J4 circuit board was not fully seated. The SCRs and circuit board were replaced. The apparent cause of the failure was the circuit board was not fully seated and caused an intermittent connection. This resulted in the blown fuse. CEA position indicators were not required to be OPERABLE while the reactor was de-fueled. The corrective actions for this event would not have prevented the conditions reported in this LER.
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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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