05-25-2005 | On April 1, 2005, a faulted lightning arrester 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 the safeguards busses as designed.
Corrective action to prevent recurrence is outlined in Section V.B. |
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LER-2005-002, Emergency Diesel Generator Start Resulting From Loss of Off-Site Power Circuit 751Docket Number |
Event date: |
04-01-2005 |
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Report date: |
05-25-2005 |
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2442005002R00 - NRC Website |
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I. PRE-EVENT PLANT CONDITIONS:
On April 1, 2005 the plant was in Mode 6 with refueling in progress. 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 1402, off-site power Circuit 751 was lost due to a distribution system lightning arrester fault at Rochester Gas & Electric (RG&E) Substation 204. 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 Emergency Diesel Generator (EDG) automatically started and supplied power to these busses as designed.
Refueling operations were immediately halted. Core cooling was momentarily interrupted and was promptly restored when the safeguard bus was re-energized. The operating Spent Fuel Pool (SFP) cooling loop was being powered from the opposite train and was not affected. The refueling cavity was flooded, and the Reactor Coolant System (RCS) temperature and SFP temperature were maintained at 74 degrees F throughout the event.
Off-site power was realigned and all plant loads were returned to off-site power on the redundant source (Circuit 767).
B. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED
TO THE EVENT:
None
C. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:
- April 1, 2005, 1402 EST: Event Date and Time, Loss of off-site power Circuit 751 and B EDG start.
- April 1, 2005, 1440 EST: Electrical system placed in the 100/0 off-site power alignment on Circuit 767
- April 1, 2005, 1450 EST: B EDG removed from service.
NRC RIRMIAPA 11-T1)11
- April 1, 2005, 1759 EST: Circuit 751 restored.
- April 3, 2005, 2103 EDST: Electrical system returned to a 50/50 alignment.
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.
III. CAUSE OF EVENT:
The cause of the event was a faulted distribution circuit lightning arrester. One of three phase lightning arresters faulted to ground on the power source distribution circuit. The lightning arrester was located on the circuit overhead line at the originating substation (204). The circuit and its .
lightning arresters are owned by the local utility. The failure of the arrester was apparently age related.
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:
NM". FrIRM 9fir,11 el -XXI/ 1 "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 offsite power sources are available to supply the engineered safety features equipment. These offsite sources each feed an independent auxiliary (startup) transformer. Offsite circuit 751 feeds transformer 12A. Offsite 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, ensuring a reliable source of power to the AC emergency busses 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 until Circuit 751 could be restored. This is consistent with Ginna Technical Specifications Section 3.8.2.
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.
- Lightning arresters were replaced on all three phases of Circuit 751.
- Circuit 751 was restored to service.
B.� ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:
The circuit and lightning arresters are owned by the local utility. The utility does not typically perform periodic diagnostic testing on distribution circuit lightning arresters, as they are considered run to failure components. Due to the importance of Circuit 751 as a Ginna Station offsite power source, the utility will perform future periodic power factor testing on the lightning arresters on the same maintenance schedule as the circuit's voltage regulator and circuit breaker. The redundant offsite circuit (767) was also reviewed to ensure its lightning arresters are tested periodically.
NRC FfIRM 'WA r1-land Ginna has performed a self assessment and risk analysis of Circuit 751, and as a result is evaluating possible modifications to the off-site power system to improve reliability.
VI.�ADDITIONAL INFORMATION:
A. FAILED COMPONENTS:
None�
B. PREVIOUS LERs ON SIMILAR EVENTS:
The following LERs were the result of the loss of Circuit 751. Although these events resulted in the auto start of an Emergency Diesel Generator, only one (2003-005) resulted in a plant trip because of the operating mode and electrical configuration at the time of the event.
- 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
- NR(` Ft-1RM "ARRA /1-7f1M1 D.� SPECIAL COMMENTS:
Ginna submitted an operating experience report on the INPO network (0E20575) to alert the industry of this issue.
NRC Ft1RM VAA /1-7(1A11
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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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