On June 10, 2005, a lightning strike resulted in the loss of off-site Circuit 751. With the electrical system in a 50/50 alignment, the loss of Circuit 751 resulted in the loss of safeguards busses 16 and 17. The B Emergency Diesel Generator ( EDG) started automatically and re-energized Bus 16. The Bus 17 feeder breaker from the B EDG failed to close resulting in the temporary loss of Bus 17. The A Service Water Pump (SWP) motor faulted and tripped when manually started per procedure.
Corrective action to prevent recurrence is outlined in Section V.B. |
LER-2005-003, Emergency Diesel Generator Start Resulting From Loss of Off-Site Power Circuit 751Docket Number |
Event date: |
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2442005003R00 - NRC Website |
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I. PRE-EVENT PLANT CONDITIONS:
On June 10, 2005 the plant was in Mode 1 at approximately 100% power. The on-site electrical system was in a 50/50 lineup configuration, meaning that each off-site circuit was providing power to two (2) of the four (4) 480 volt 'safeguards busses.
II. DESCRIPTION OF EVENT:
A. EVENT:
At approximately 1351, off-site power Circuit 751 was lost due to a distribution system lightning strike. Because the plant's electric distribution system was in a 50/50 lineup, this resulted in the temporary loss of two (2) of the four (4) safeguards busses (Bus 16 and Bus 17). The B EDG automatically started and supplied power to Bus 16. The Bus 17 supply breaker from the B EDG failed to close. While responding to the event per the applicable Abnormal Operating Procedure (AP), the A SWP was manually started. Approximately two (2) minutes after starting, the A SWP motor faulted and tripped, resulting in only one SWP supplying the entire service water loop. To minimize the heat load on the service water system, as required by the AP, operators shut down non-essential components, and in the case of the "B" EDG, installed alternate cooling to the jacket and lube oil heat exchangers from the fire main system. Following evaluation, all plant loads were returned to off-site power on the redundant source (Circuit 767), with the B and C SWPs running. The plant remained stable in Mode 1 at approximately 100% power during the event.
B. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED
TO THE EVENT:
None
C. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:
- June 10 2005, 1351 EDST: Event Date and Time, Loss of off-site power Circuit 751 and B EDG start. Bus 17 breaker from B EDG fails to close.
- June 10, 2005, 1353 EDST: SWP A trips
- June 10, 2005, 1454 EDST: Electrical system placed in the 100/0 off-site power alignment on Circuit 767
- June 10, 2005, 1531 EDST: Bus 17 returned to service.
- June 10, 2005, 2001 EDST: Off-site power circuit 751 returned to service.
D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:
None, since there were no failures of any components with multiple functions.
E. METHOD OF DISCOVERY:
The condition was immediately apparent from plant indications and response in the Control Room.
F. SAFETY SYSTEM RESPONSES:
- All safety systems functioned as designed with the exception of the following:
- The B EDG feeder breaker to Bus 17 failed to close
- The A SWP faulted and tripped III.CCAUSE OF EVENT:
The initial circuit walk down by Rochester Gas and Electric (RG&E) personnel (off-site distribution system owner) found the end bell insulators holding the west side phase conductor to Circuit 751 pole T-30 were blown apart. The end bells attach the conductor to the pole cross bar. When they failed the conductor dropped, made contact with a grounded device and tripped the circuits feeder breaker. RG&E attributed the failure to a lightning strike that exceeded the withstand capability of the insulator. The end bell assembly was replaced and the circuit restored to service.
A subsequent walk down by the Ginna system engineer and distribution system experts from Baltimore Gas and Electric (BG&E) and Constellation Energy Corporate was performed on 6/27/05.
The pole T-30 cross arm was noted to be charred between the pole's top guy wire and the cross arm standoff insulator. The guy wire on this pole was being used to ground the static wire at this pole.
The guy wire was routed between the cross arms and was in contact with the arm that was charred.
This construction practice decreased the basic impulse level (BIL), capability of the pole design to withstand lightning surges, and was the root cause for the failure of the insulator and subsequent loss of Circuit 751.
The failure of the end bell insulator caused the supported conductor to fault to ground. This resulted in a feeder breaker trip and a loss of Circuit 751 power to the plant.
This event is NUREG-1022 Cause Code (C), "External Cause" IV.� ASSESSMENT OF THE SAFETY CONSEQUENCES OF THE EVENT:
This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv)(A), which requires a report of, "Any event or condition that resulted in manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B) of this section, except when:
(1)The actuation resulted from and was part of a pre-planned sequence during testing or reactor operation; or (2)The actuation was invalid and; (i) Occurred while the system was properly removed from service; or (ii) Occurred after the safety function had been already completed.
UFSAR 8.3.1.2.4.1 states in part:
- "The electrical system equipment is arranged so that no single contingency can inactivate enough engineered safety features equipment to jeopardize the plant safety.
"Two independent off-site power sources are available to supply the engineered safety features equipment. These off-site sources each feed an independent auxiliary (startup) transformer. Off-site circuit 751 feeds transformer 12A. Off-site circuit 767 feeds transformer 12B. Each transformer is capable of supplying all plant engineered safety features equipment.
The B EDG operated as designed throughout the event, providing a reliable source of power to Bus 16. Bus 17, although de-energized for a limited period of time, had a reliable source of power available from off-site circuit 767 at all times.
One off-site power Circuit (767) was not affected and remained in service. It was subsequently aligned to carry all off-site loads. This is consistent with Ginna Technical Specifications Section 3.8.2.
One service water train was operable at all times. This configuration is addressed by the Ginna Technical Specifications Section 3.7.8, which maintains the plant within the current licensing basis.
Therefore, it was determined that the plant responded within it's design and licensing basis, and that the public's health and safety was assured at all times.
V.� CORRECTIVE ACTIONS:
A.� ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL
STATUS:
- Off-site power was restored to Bus 16 and Bus 17.
- Service water system was returned to a normal at power pump configuration.
- Circuit 751 was restored to operable status.
B.� ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:
The failed end bell insulator was replaced on pole T-30. There are five additional end bell insulators on this pole and they were replaced as a precautionary measure. This was performed by RG&E on 6/10/2005. Circuit 751 was returned to operable status.
Circuit 751 was walked down by a BG&E distribution circuit engineer. The circuit construction with a grounded static wire provides adequate protection to the phase conductors of the protected circuit provided the conductors are within a 45 degree protection zone from the static wire. Circuit construction design is being obtained from RG&E to verify the 45 degree protection zone.
The BG&E engineer walk down identified inadequate clearance existed between a grounded guy wire and the energized circuit conductor on poles T-21, T-29 and T-30. The inadequate clearance on poles T-29 and T-30 was corrected by RG&E on June 30, 2005. RG&E is evaluating the inadequate clearances on pole T-21, and corrective action will be taken as necessary.
The BG&E engineer did not identify any additional enhancements that could be taken to improve Circuit 751's reliability. Circuit 767 at Station 13A was walked down and no enhancements for additional reliability were noted.
RG&E performed a condition assessment of Circuit 751. Visual inspection and thermography of Circuit 751 are performed annually with the last performance in June 2005 with no anomalies noted. Tree trimming is performed annually, scheduled for August/September this year. A one time corona inspection was completed on July 1, 2005 with no findings. Station 204 insulator inspection and washing is performed annually, scheduled for September this year.
Plant Change Request (PCR) 2004-0028 will reconfigure Circuit 751 to originate from Station 13A with underground construction to Ginna Station, similar to Circuit 767. This will significantly increase this off-site power source reliability by eliminating overhead line failure mechanisms. This reconfiguration is anticipated to occur in 2006.
VI.�ADDITIONAL INFORMATION:
A.�FAILED COMPONENTS:
Circuit Breaker (B EDG supply to Bus 17), Westinghouse, Model DB-50 Motor (A SWP), US Electric, Model H02443 .� 7.
- B.�PREVIOUS LERs ON SIMILAR EVENTS
- � .
I The following LERs were the result of the loss of Circuit 751.�' .�
- 1991-002 C.�THE ENERGY INDUSTRY IDENTIFICATION SYSTEM (EIIS) COMPONENT FUNCTION
IDENTIFIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO
IN THIS LER:
COMPONENT IEEE 803 IEEE 805
FUNCTION IDENTIFIER SYSTEM IDENTIFICATION
Off-Site Power Circuit 751 JX EA Emergency Diesel Generators DG EK Insulator , INS EA Electric Motor MO BI Circuit Breaker BKR EK
' The failure of the B EDG supply breaker to Bus 17 was caused by lack of sufficient lubrication. Technician coaching has been performed, and steps to identify and lubricate other susceptible breakers have been initiated per the Ginna Corrective Action Process.
The failure of the A SWP motor was caused by motor insulation failure. The cause of the insulation failure is under extensive evaluation per the Ginna Corrective Action Process.
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05000328/LER-2005-001 | Unit 2 Reactor Trip Following Closure of Main Feedwater Upon Inadvertent Opening of Control Breakers | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000388/LER-2005-001 | DDegradation of Primary Coolant Pressure Boundary due to Recirculation Pump Discharge Valve Bonnet Vent Connection Weld Flaw | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000423/LER-2005-001 | | 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 | 05000455/LER-2005-001 | Unit 2 Automatic Reactor Trip Due to Low Steam Generator Level resulting from a Software Fault on the Turbine Control Power Runback Feature | | 05000370/LER-2005-001 | Automatic Actuation of Motor Driven Auxiliary Feedwater Pumps During Outage | | 05000244/LER-2005-001 | Failure of ADFCS Power Supplies Results in Plant Trip | | 05000247/LER-2005-001 | 0Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for One Inoperable Train of ECCS Caused by an Inoperable Auxiliary Component Cooling Water Check Valve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000529/LER-2005-001 | REACTOR HEAD VENT AXIAL INDICATIONS CAUSED BY DEGRADED ALLOY 600 COMPONENT | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000336/LER-2005-001 | | | 05000266/LER-2005-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000269/LER-2005-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000289/LER-2005-001 | | | 05000293/LER-2005-001 | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000298/LER-2005-001 | Reactor Scram due to Reactor Level Transient and Inadvertent Rendering of High Pressure Coolant Injection Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000331/LER-2005-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000315/LER-2005-001 | Reactor Trip Following Intermediate Range High Flux Signal | | 05000316/LER-2005-001 | Reactor Trip from RCP Bus Undervoltage Signal Complicated by Diesel Generator Output Breaker Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000317/LER-2005-001 | Main Feedwater Isolation Valve Inoperability Due to Handswitch Wiring | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000323/LER-2005-001 | TS 3.4.10 Not Met During Pressurizer Safety Valve Surveillance Testing Due to Random Lift Spread | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000333/LER-2005-001 | Inoperable Offsite Circuit In Excess of Technical Specifications Allowed Out of Service Time | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000352/LER-2005-001 | Loss Of Licensed Material In The Form Of A Radiation Detector Calibration Source | | 05000353/LER-2005-001 | Core Alterations Performed With Source Range Monitor Alarm Horn Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000306/LER-2005-001 | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000361/LER-2005-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000362/LER-2005-001 | Emergency Diesel Generator (EDG) 3G003 Declared Inoperable Due to Loose Wiring Connection on Emergency Supply Fan | | 05000263/LER-2005-001 | | | 05000456/LER-2005-001 | Potential Technical Specification (TS) 3.9.4 Violation Due to Imprecise Original TS and TS Bases Wording | | 05000454/LER-2005-001 | Failed Technical Specification Ventilation Surveillance Requirements During Surveillance Requirement 3.0.3 Delay Period | | 05000282/LER-2005-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000286/LER-2005-001 | Plant in a Condition Prohibited by Technical Specifications due to Error Making Control Room Ventilation System Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000400/LER-2005-001 | Reactor Auxiliary Building Emergency Exhaust System Single Failure Vulnerability | | 05000395/LER-2005-001 | Emergency Diesel Generator Start and Load Due To A Loss Of Vital Bus | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000382/LER-2005-001 | RCS Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking of a Pressurizer Heater Sleeve | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000305/LER-2005-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000369/LER-2005-001 | Reactor Coolant System Leakage Detection Instrumentation Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000266/LER-2005-002 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000255/LER-2005-002 | | 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 | 05000361/LER-2005-002 | Missing Taper Pins on CCW Valve Cause Technical Specification Required Shutdown | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000370/LER-2005-002 | Ice Condenser Lower Inlet Door Failed Surveillance Testing | | 05000353/LER-2005-002 | High Pressure Coolant Injection System Inoperable due to a Degraded Control Power Fuse Clip | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000263/LER-2005-002 | | | 05000454/LER-2005-002 | One of Two Trains of Hydrogen Recombiners Inoperable Longer Than Allowed by Technical Specifications Due to Inadequate Procedure | | 05000244/LER-2005-002 | Emergency Diesel Generator Start Resulting From Loss of Off-Site Power Circuit 751 | | 05000362/LER-2005-002 | Emergency Containment Cooling Inoperable for Longer than Allowed by Technical Specifications | 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 | 05000247/LER-2005-002 | DTechnical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for One Inoperable Train of ECCS Caused by Gas Intrusion from a Leaking Check Valve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000306/LER-2005-002 | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000265/LER-2005-002 | Main Steam Relief Valve Actuator Degradation Due to Failure to Correct Vibration Levels Exceeding Equipment Design Capacities | 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 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000286/LER-2005-002 | • Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249Entergy Buchanan. NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration July 5, 2005 Indian Point Unit No. 3 Docket Nos. 50-286 N L-05-078 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Subject:L Licensee Event Report # 2005-002-00, "Automatic Reactor Trip Due to 32 Steam Generator Steam Flow/Feedwater Flow Mismatch Caused by Low Feedwater Flow Due to Inadvertent Condensate Polisher Post Filter Bypass Valve Closure." Dear Sir: The attached Licensee Event Report (LER) 2005-002-00 is the follow-up written report submitted in accordance with 10 CFR 50.73. This event is of the type defined in 10 CFR 50.73(a)(2)(iv)(A) for an event recorded in the Entergy corrective action process as Condition Report CR-IP3-2005-02478. There are no commitments contained in this letter. Should you or your staff have any questions regarding this matter, please contact Mr. Patric W. Conroy, Manager, Licensing, Indian Point Energy Center at (914) 734-6668. Sincerely, 4F-/t R. Dacimo Vice President Indian Point Energy Center Docket No. 50-286 NL-05-078 Page 2 of 2 Attachment: LER-2005-002-00 CC: Mr. Samuel J. Collins Regional Administrator — Region I U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspector's Office Resident Inspector Indian Point Unit 3 Mr. Paul Eddy State of New York Public Service Commission INPO Record Center NRC FORM 3660 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004) Estimated burden per response to comply with this mandatory collection request 50 hours.RReported lessons teamed 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 29555-0001, or by InternetLICENSEE EVENT REPORT (LER) e-mail to Infocoilectsenrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-l0202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person Is not required to respond to, the Information collection. 1. FACIUTY NAME 2. DOCKET NUMBER 3. PAGE INDIAN POINT 3 05000-286 10OF06 4. TITLE Automatic Reactor Trip Due to 32 Steam Generator Steam Flow/Feedwater Flow Mismatch Caused by Low Feedwater Flow Due to Inadvertent Condensate Polisher Post Filter Bypass Valve Closure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000287/LER-2005-002 | Unit 3 trip with ES actuation due to CRD Modification Deficiencies | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000336/LER-2005-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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