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11-22-2006 | On September 27, 2006 (discovery date) at approximately 0917 PDT, Unit 3 was operating at about 100 percent power when "A" train charging pump 3P190 failed to start. Upon investigation, SCE determined the pump failed to start because the supply breaker 3B0413 failed to close. Based on the cause analysis, SCE concluded the "A" train charging pump became inoperable when the breaker was last opened (September 23, 2006 at 1427 PDT). SCE is reporting this event in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the TS.
SCE determined that the supply breaker failed due to a failed shunt trip device (STD). The STD trip rod was sticking intermittently in the energized position, which prevented the breaker from closing. SCE replaced the STD in breaker 3B0413 and returned the pump to service on October 3, 2006. SCE is continuing to investigate the cause of the sticking STD. SCE plans to replace two other breaker operating mechanisms that were purchased in the same lot and that are installed in safety related applications.
The safety significance of this condition is minimal because the "B" train charging pump was operating and the swing charging pump was operable and available to be aligned to "A" train during the time the "A" train charging pump was inoperable.
,NRC FORM 366A� U.S. NUCLEAR REGULATORY COMMISSION (7-2001) Discovery Date: September 27, 2006 Reactor Vendor: Combustion Engineering Mode: Mode 1 — Power Operation Power: 100 percent |
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LER-2006-004, Station ManagerEDISON® San Onofre
An EDISON INTERNATIONAL@ Company
November 22, 2006
U.S. Nuclear Regulatory Commission
Document Control Desk
Washington, D.C. 20555-0001
Subject:DDocket No. 50-362
Licensee Event Report No. 2006-004
San Onofre Nuclear Generating Station, Unit 3
Dear Sir or Madam:
This submittal provides Licensee Event Report (LER) 2006-604, which describes an
occurrence of an inoperable breaker causing a charging pump to be inoperable longer
than allowed by Technical Specifications. This event did not affect the health and
safety of either plant personnel or the public.
If you require any additional information, please contact me.
Sincerely,
Unit 3 LER No. 2006-004
cc:DB. S. Mallett, NRC Regional Administrator, Region IV
C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 & 3
P.O. Box 128
San Clemente, CA 92674-0128
949-368-9263/PAX 89263
Fax 949-368-6183
breigdp@songs.sce.com
)
ARC FORM 366
U.S. NUCLEAR REGULATORY APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
(7-2001) COMMISSION Estimated burden per response to comply with this mandatory information collection request: 50 hours.
Reported lessons learned are incorporated into the licensing process and fed back to industry. Send
comments regarding burden estimate to the Records Management Branch (T-6 E6), U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to bjs@nrc.gov, andLICENSEE EVENT REPORT (LER) to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of
(See reverse for required number of Management and Budget, Washington, DC 20503. If a means used to impose 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.
digits/characters for each block)
1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE
San Onofre Nuclear Generating Station (SONGS) Unit 3 05000362 1 OF 4
4. TITLE
Inoperable breaker causes train "A" charging pump to be inoperable for longer than allowed by Technical
SpecificationsDocket Number |
Event date: |
09-27-2006 |
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Report date: |
11-22-2006 |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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3622006004R00 - NRC Website |
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Description of Event:
San Onofre Nuclear Generating Station (SONGS) Technical Specification (TS) 3.1.9 requires two RCS boron injection [CB] flow paths ("A" and "B" train) to be operable in Modes 1 through 4.
TS 3.1.10 requires one RCS boron injection flow path to be operable in Modes 5 and 6. Each flow path includes one charging pump. A third charging pump (swing) is capable of being aligned to either the "A" or "B" train flow path.
On September 27, 2006 (discovery date) at approximately 0917 PDT, Unit 3 was operating at about 100 percent power when "A" train charging pump 3P190 [P] was declared inoperable after failing to start and a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement was entered in accordance with TS 3.1.9. At that time, the "B" train charging pump was already operating and the swing charging pump was also aligned to "B" train. At 1607 PDT on September 27, 2006, plant operators aligned swing charging pump 3P191 to "A" train and the action statement was exited.
Upon investigation Southern California Edison (SCE) determined the "A" train charging pump failed to start because the shunt trip device (STD) on the ABB 480 V K600S supply breaker [BKR] 3B0413 failed, preventing the breaker from closing. Based on the cause analysis, discussed below, SCE concluded that the "A" train charging pump breaker became inoperable when the breaker was last opened on September 23, 2006 at 1427 PDT. The "A" train boration flow path was not restored to operable status until the swing charging pump was aligned to the "A" train on September 27, 2006 (4 days, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and 42 minutes later). Because the period of inoperability exceeded the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed outage time, SCE is reporting this event in accordance with 10 CFR 50.73(a)(2)(i)(B).
Cause of Event
SCE determined the "A" train charging pump failed to start because the supply breaker failed to close on demand from the control room due to a failed STD in the breaker. The STD opens the breaker under conditions such as demand from the control room or automatic signals not associated with an electrical fault. The STD is similar to a spring return solenoid, which when energized momentarily with 125 Vdc, produces a magnetic force that pulls up on the armature. This movement causes the trip rod to actuate the primary trip latch to open the breaker. When the voltage is removed, the STD trip rod should return to its normal position by spring tension. If the STD trip rod does not return to the normal position, the primary trip latch will also remain actuated and prevent the breaker from closing. (See attached figure.) SCE performed bench testing of the failed breaker and found the STD trip rod to be sticking intermittently in the energized position. SCE concluded the sticking STD had prevented the breaker from closing as described above. Because the STD only actuates when opening the breaker, this failure most likely occurred when the breaker was last opened. SCE is continuing to investigate the cause of the sticking STD.
'NRC FORM 366A� U.S. NUCLEAR REGULATORY COMMISSION (7-2001)
Corrective Actions
SCE replaced the STD in breaker 3B0413 and returned the "A" train charging pump to service on October 3, 2006. The defective STD was returned to the manufacturer for failure analysis.
The STD is a subpart of the breaker operating mechanism. The STD in breaker 3B0413 was installed in the plant on February 26, 2003 when the operating mechanism for 3B0413 was replaced during a breaker overhaul. The breaker operated satisfactorily between the overhaul and its failure on September 23, 2006. SCE identified four other operating mechanisms with STDs installed at the factory that were purchased in the same lot as the operating mechanism in 3B0413. Of these four, only two are installed in safety related equipment (pressurizer heater bank 2E128 and standby upper dome air circulator 2A073). The following additional actions are planned:
- SCE plans to replace the two operating mechanisms purchased in the same lot that are installed in safety related applications. (The entire operating mechanism in 3B0413 was replaced following a subsequent failure discussed below in "Additional Information".)
- The 480 volt breaker preventive maintenance and overhaul procedures will be revised to require inspection of STDs for the condition discussed above.
- Based on the results of the cause analysis performed by the breaker supplier, SCE may determine other corrective actions.
Safety Significance
The safety significance of this event was minimal because:
The "B" train charging pump was operating and the swing charging pump was operable and available to be aligned to "A" train during the time the "A" train charging pump was inoperable.
SCE performed a probabilistic risk assessment and demonstrated that the safety significance of this condition is minimal (increase in core damage probability of 6E-8 and increase in large early release probability of 6E-10) due to the short time the charging pump was inoperable and the availability of the "B" train and swing charging pumps.
Additional Information
On October 17, 2006, Unit 3 was in Mode 5 at the beginning of the Cycle 14 refueling outage when "A" train charging pump breaker 3B0413 failed to open on demand from the control room. SCE had returned the breaker to service on October 3, 2006 and plant operators had started the pump four times and stopped it three times before the breaker failed again on October 17, 2006. The failure occurred in Mode 5 when only one boration injection flow path is required. At that time, "A" train charging pump was running and "B" train flow path was operable. SCE determined the second breaker failure was caused by mechanical jamming of the operating mechanism and was not related to the first failure caused by sticking of the STD. SCE is continuing to investigate the cause of the mechanical jamming of the operating mechanism.
In the past three years, SCE has not reported any events involving inoperability of boration flow paths for longer than allowed by TSs. SCE did report the following three events involving breaker failures causing equipment to be inoperable for longer than allowed by TS:
- LER 2002-002, "Breaker failure to close renders containment emergency fan inoperable for longer than allowed by TS." This failure was caused by the inability of the closing springs for the breaker to fully charge through the end of the charge cycle.
- LER 2005-005, "Inoperable class 1 E supply breaker causes pressurizer heater to be inoperable for longer than allowed by TS." This failure was caused by misalignment and interferences between the breaker and the cubicle.
Because these earlier events were not caused by failure of a STD, prior corrective actions would not be expected to prevent the failure of the breaker reported in this LER.
Shunt Trip Device for ABB K600S Breaker Trip Rod (Adjusting Screw) Mechanism Housing Coil Armature Primary Trip Latch Latch Bar 3 inches
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05000305/LER-2006-010 | | | 05000456/LER-2006-001 | Unit 1 Reactor Coolant System Pressure Boundary Leakage Due To Inter-Granular Stress Corrosion Cracking of a Pressurizer Heater Sleeve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000454/LER-2006-001 | Technical Specification Required Action Completion Time Exceeded for Inoperable Containment Isolation Valves Due to Untimely Operability Determination | | 05000423/LER-2006-001 | Loss Of Safety Function Of The Control Room Emergency Ventilation System | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000369/LER-2006-001 | Ice Condenser and Floor Cooling System Containment Isolation Valve inoperable longer than allowed by Technical Specification 3.6.3. | | 05000353/LER-2006-001 | HPCI Ramp Generator Signal Converter Failure | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000352/LER-2006-001 | Loss Of One Offsite Circuit Due To Invalid Actuation Of Fire Suppression System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000336/LER-2006-001 | | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | 05000316/LER-2006-001 | Failure to Comply with Technical Specification 3.6.2, Containment Air Locks | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2006-001 | Plant Shutdown Required by Technical Specification Action 3.6.5.B.1 | | 05000293/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv), System Actuation | 05000289/LER-2006-001 | | | 05000287/LER-2006-001 | Actuation of Emergency Generator due to Spurious Transformer Lockout | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000251/LER-2006-001 | Turkey Point Unit 4 05000251 1 OF 6 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000247/LER-2006-001 | Manual Reactor Trip Due to Multiple Dropped Control Rods Caused by Loss of Control Rod Power Due to Personnel Error | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2006-001 | Incorrect Wiring in the Remote Shutdown Panel Results in a Fire Protection Program Violation | | 05000413/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000368/LER-2006-001 | Completion of a Plant Shutdown Required by Technical Specifications Due to Loss of Motive Power to Certain Containment Isolation Valves as a Result of a Phase to Ground Short Circuit in a Motor Control Cubicle | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000306/LER-2006-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000298/LER-2006-001 | Cooper Nuclear Station 05000298 1 of 4 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000286/LER-2006-001 | I | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000266/LER-2006-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000261/LER-2006-001 | Manual Reactor Trip Due to Failure of a Turbine Governor Valve Electro-Hydraulic Control Card | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000255/LER-2006-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000461/LER-2006-002 | Turbine Bypass Function Lost Due to Circuit Card Maintenance Frequency | | 05000458/LER-2006-002 | Loss of Safety Function of High Pressure Core Spray Due to Manual Deactivation | | 05000456/LER-2006-002 | Units 1 and 2 Entry into Limiting Condition for Operation 3.0.3 due to Main Control Room Ventilation Envelope Low Pressure | | 05000443/LER-2006-002 | Noncompliance with the Requirements of Technical Specification 6.8.1.2.a | | 05000387/LER-2006-002 | DMissed Technical Specification surveillance requirement | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000362/LER-2006-002 | Unit 3 Shutdown to Inspect Safety Injection Tank Spiral Wound Gaskets | | 05000336/LER-2006-002 | Manual Reactor Trip Due To Trip Of Both Feed Pumps Following A Loss Of Instrument Air | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000316/LER-2006-002 | | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2006-002 | Failure to Comply with Technical Specification Requirement 3.6.13, Divider Barrier Integrity | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2006-002 | | | 05000289/LER-2006-002 | | | 05000251/LER-2006-002 | Intermediate Range High Flux Trip Setpoint Exceeded Technical Specification Allowable Value | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000440/LER-2006-002 | Scaffold Built in the Containment Pool Swell Region | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000413/LER-2006-002 | Safe Shutdown Potentially Challenged by an External Flooding Event and Inadequate Design and Configuration Control | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000388/LER-2006-002 | Missed Technical Specification LCO 3.8.1 Entry for Unit 2 During Unit 1 ESS Bus Testing | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000348/LER-2006-002 | Main Steam Isolation Valve Failure to Close | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2006-002 | | 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 | 05000301/LER-2006-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000286/LER-2006-002 | 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249Entergy Tel (914) 734-6700 Fred Dacimo Site Vice President Administration September 13, 2006 Indian Point Unit No. 3 Docket No. 50-286 N L-06-084 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Subject:L Licensee Event Report # 2006-002-00, "Manual Reactor Trip as a Result of Arcing Under the Main Generator Between Scaffolding and Phase A&B of the Isophase Bus Housing" Dear Sir: The attached Licensee Event Report (LER) 2006-002-00 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-IP3-2006-02255. 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. Fred R. Dacimo Site Vice President Indian Point Energy Center Docket No. 50-286 NL-06-084 Page 2 of 2 Attachment: LER-2006-002-00 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 366 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.DReported lessons learned 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 20555-0001, or by internetLICENSEE EVENT REPORT (LER) 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 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. FACILITY NAME 2. DOCKET NUMBER I 3. PAGE
INDIAN POINT 3 05000-286 1 OF 6
4.TITLE: Manual Reactor Trip as a Result of Arcing Under the Main Generator Between
Scaffolding and Phase A&B of the Iso-phase Bus Housing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2006-002 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000269/LER-2006-002 | High Energy Line Breaks Outside Licensing Basis May Result in Loss of Safety Function | | 05000263/LER-2006-002 | | | 05000255/LER-2006-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000254/LER-2006-002 | Quad Cities Nuclear Power Station Unit 1 05000254 1 of 3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000483/LER-2006-003 | Unexpected Inoperability of the Emergency Exhaust System due to Inoperable Pressure Boundary | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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