emergency diesel generator (D6) from service for planned maintenance. Technical Specification (TS) 3.8.1, " AC Source - Operating," Condition B, "One DG inoperable," was entered. TS Required Action 3.8.1.B.4 requires D6 be restored to operable status with a Completion Time of 7 days. The planned maintenance activities included replacing two sets of two pistons, rings and cylinder liners on Engine 2 of D6 (D6 is a tandem-engine diesel generator). Return-to-service testing was initiated on February 3, 2006, and at approximately 0000 CST on February 4, 2006, the test was halted due to high-indicated crankcase pressure on Engine 1 (not the engine that was worked on). The test procedure specified shutting down the diesel generator if crankcase pressure on either engine exceeds 30mm for more than a few minutes (the setpoint for the crankcase pressure trip is 52 mm).
Initial investigation of the cause of the high-indicated crankcase pressure on Engine 1 attributed the crankcase pressure to abnormal blow-by. Evaluation of the scope of work to return D6 to operable status and the schedule for completing the work indicated that repairs could not be completed within the remainder of the 7-day Completion Time. NMC commenced shutdown of Unit 2 on February 5, 2006. |
FACILITY NAME (1) � DOCKET NUMBER (2) LER NUMBER (6)� PAGE (3) 06 -- 01 -- 0
EVENT DESCRIPTION
emergency diesel generator' (D6) from service for planned maintenance. Technical Specification (TS) 3.8.1, "AC Source - Operating," Condition B, "One DG inoperable," was entered. TS Required Action 3.8.1.B.4 requires D6 be restored to operable status with a Completion Time of 7 days. The planned maintenance activities included replacing two sets of two pistons, rings and cylinder liners on Engine 2 of D6 (D6 is a tandem-engine diesel generator). Return-to-service testing was initiated on February 3, 2006, and at approximately 0000 CST on February 4, 2006, the test was halted due to high-indicated crankcase pressure on Engine 1 (not the engine that was worked on). The test procedure specified shutting down the diesel generator if crankcase pressure on either engine exceeds 30mm for more than a few minutes (the setpoint for the crankcase pressure trip is 52 mm).
Initial investigation of the cause of the high-indicated crankcase pressure on Engine 1 attributed the crankcase pressure to abnormal blow-by. Evaluation of the scope of work to return D6 to operable status and the schedule for completing the work indicated that repairs could not be completed within the remainder of the 7-day Completion Time. NMC commenced shutdown of Unit 2 on February 5, 2006.
EVENT ANALYSIS
Since Unit 2 was shut down in accordance with TS LCO 3.8.1, this event is required to be reported per 10 CFR 50.73(a)(2)(i)(A).
Impact on Safety System Functional Failure Performance Indicator The bounding accident load for D6 is a station blackout (3650 kW). The D6 Engine 1 crankcase pressure excursion occurred at a significantly higher load (between 5100 kW and 5300 kW) and crankcase pressure decreased when load was reduced (between 3800 kW and 4000 kW). This load dependency is consistent with all prior crankcase pressure excursions on D5 and D6. The team that investigated the as-found condition of D6 concluded there was reasonable assurance that D6 would have been able to provide the bounding accident load in the as-found condition without crankcase pressure elevating to the point it threatened engine operation. Therefore, the as-found condition does not represent a loss of safety function. Consequently, this event is not reportable per 10CFR 50.73(a)(2)(v).
1 (EIIS System Code: EK; EIIS Component Identifier: DG) FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 06 -- 01 -- 0
SAFETY SIGNIFICANCE
As noted above, there was reasonable assurance that D6 would have been able to provide the bounding accident load in the as-found condition without crankcase pressure elevating to the point it threatened engine operation. Therefore, this event did not affect the health and safety of the public.
CAUSE
The Unit 2 shutdown is a result of the D6 Engine 1 issue occurring during return to service testing following maintenance on Engine 2. Considering the time spent on D6 Engine 2 maintenance, the Technical Specification Completion Time for D6 being inoperable would have expired before repairs on Engine 1 could have been completed, thus, Unit 2 was shutdown as required by Technical Specifications. NMC conducted a Root Cause Evaluation (RCE) of the February 4, 2006, D6 crankcase pressure excursion. The equipment root cause was determined to be long-term, inadequate control of lube oil level in the engine crankcase. Prolonged operation with lube oil level too high:
(1) adversely affected proper operation of the crankcase breather system, (2) adversely affected readings of the crankcase manometer, (3) increased lube oil carryover through the intake manifold as evidenced by oil in the under pressure regulator filter, and (4) increased lube oil deposits on the piston crowns and top lands.
Contributors to this cause include:
(1) inappropriate setting of low lube oil level switch2 causes over filling of crankcase, (2) the practice of routinely allowing engine operation with oil level above the maximum dipstick reading, and (3) less than adequate manometer connection to the crankcase that allows lube oil to fill the Tygon tubing affecting accuracy.
Two potential contributing causes were identified that require more detailed study were also identified:
(1) Piston top ring "pinch" at high load operation — additional information (i.e., Finite Element analysis of UD45 piston to determine the effect of engine load on geometry of top ring groove) will be needed to support or refute this potential contributing cause, and (2) Breather system may not be fully capable of exhausting the crankcase when the crankcase lube oil level is at or above the maximum level.
Additionally, the root cause evaluation assessed the human performance and organizational factors that led to this event.
2 (EIIS Component Identifier: LS) FACILITY NAME (1)� DOCKET NUMBER (2) LER NUMBER (6� PAGE (3) 06 -- 01 -- 0
CORRECTIVE ACTION
Completed actions include:
1. Replaced all the cylinder liners and piston rings on D6 Engine 1 and Engine 2 (with the exception of the liners and rings that had just been replaced on the four cylinders on Engine 2). D6 was returned to operable status on February 16, 2006 after completing a return-to-service surveillance run.
2. Reduced normal operating band for lube oil levels in all D5/D6 engines to engineering recommended level. Indicating scribe lines on the engine dipsticks were modified to reflect the proper crankcase oil level.
3. Implemented control of the reduced oil level through procedure enhancement and training of operators.
4. The manometer connection was modified to prevent problems with oil getting into the manometer tubing.
Planned actions include:
5. Submit a License Amendment Request to reduce the load at which D5 and D6 must be tested in order to meet Technical Specification Surveillance Requirements.
6. A finite element analysis of the D5/D6 (UD45) piston design is being performed to determine definitively if ring-pinch is a significant contributor to the crankcase pressure excursion. Initial results indicate that the top ring groove does close at higher load, but the closure would not appear to cause a ring pinch unless combined with another issue (e.g., deposits).
7. A study to confirm the adequacy of the current breather system will be initiated.
8. In addition, corrective actions have been initiated to address the human performance and organizational root causes.
PREVIOUS SIMILAR EVENTS
Both trains of Unit 2 emergency diesel generators have had issues with crankcase pressure excursions in the past that led to a Unit 2 shutdown. Refer to Licensee Event Report (LER) 2-01-03 and LER 2-05-02.
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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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