05-26-2006 | On January 9, 2006, Millstone Power Station Unit 2 was operating in Mode 1 at 100% power. At approximately 0435, with one charging pump running, operators received a charging pump discharge pulsation dampener failure alarm. At 0455 charging header flow indication began to drop. The operators evaluated this as a loss of both facilities of the charging system. All charging pumps were declared inoperable at 0455. Additional investigation indicated potential gas binding of the charging pumps. At 0554 the operators vented and started one charging pump and declared it operable, restoring one train of the charging system.
The failure of a discharge pulsation dampener bladder allowed the contained gas volume to expand into the system piping, including the suction header. The cause of the bladder failure resulted from operating the bladder at a high pre charge pressure combined with changes made to the dampener shell during fabrication, which allowed improper seating of the bladder at the point of contact with the shell. The root cause of the event was attributed to an over reliance on industry operating experience and faulty design assumptions. Together these two factors resulted in a conclusion that passive failure of a bladder with the potential for a common mode loss of charging was not a credible event.
The charging pumps have two credited safety functions associated with normal operation and shutdown of the reactor plant. These functions are Inventory Control, and Boration for Reactivity Control. For this reason the failure of the charging system is considered reportable under the provisions of 10 CFR 50.73(a)(2)(v)(A), as an event or condition that could have prevented fulfillment of a safety function of structures or systems needed to shutdown and maintain the reactor in a safe shutdown condition. |
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1. Background The charging portion of the Millstone Power Station Unit 2 (MPS 2) Chemical Volume Control System (CVCS) [CB] is comprised of three positive displacement pumps. The charging pumps have two credited safety functions associated with normal operation and shutdown of the reactor plant. These functions are Inventory Control, and Boration for Reactivity Control. One pump is usually in service with the other two pumps automatically starting, as necessary, in response to the pressurizer level control. The design basis safety analyses in Chapter 14 of the Final Safety Analysis Report (FSAR) demonstrate acceptable results without credit for charging.
The suction and discharge of each charging pump is equipped with a pulsation dampener. In November 2003 the liquid filled swirl type pulsation dampeners on the discharge piping for each pump were replaced with nitrogen pressurized bladder/shell type pulsation dampeners to mitigate the cracking of socket welded piping joints. The bladder is designed with a metallic grommet/button on the bottom to prevent the extrusion of the bladder into the shell nozzle. In March 2004 Dominion Nuclear Connecticut (DNC) changed the bladder precharge pressure from 1800 psig to 2000 psig. The 2000 psig pre-charge pressure is at the upper limit of pressure recommended by the vendor. This change was intended to improve the dampening function and provide increased margin to allow for gas leakage from the bladder fill connection. This in turn would allow extending the frequency of bladder pressure monitoring.
2. Event Description On January 9, 2006, MPS 2 was operating in Mode 1 at 100% power. At approximately 0435, with one charging pump [P] running, operators received a charging pump discharge pulsation dampener failure alarm. At 0455, charging header flow indication began to drop. The operators evaluated this as a loss of both facilities of the charging system. All charging pumps were declared inoperable at 0455.
Additional investigation indicated potential gas binding of the charging pumps. At 0554 the operators vented and started one charging pump and declared it operable, restoring one train of the charging system.
The failure of the charging system is reportable under the provisions of 10 CFR 50.73(a)(2)(v)(A), as an event or condition that could have prevented fulfillment of a safety function of structures or systems needed to shutdown and maintain the reactor in a safe shutdown condition.
2. Cause The direct cause of the loss of charging was failure of a discharge pulsation dampener bladder which allowed the contained gas volume to leak into the dampener shell. Upon securing the pump, discharge pressure decayed thereby allowing the gas to expand into the system piping, including the suction header. The cause of the bladder failure is attributed to operating the bladder at the higher pre-charge pressure combined with changes made to the dampener shell during fabrication which allowed improper seating of the bladder at the point of contact with the shell.
The root cause of the event was attributed to an over reliance on industry operating experience and faulty design assumptions. Together these two factors resulted in a conclusion that passive failure of a bladder with the potential for a common mode loss of charging was not a credible event.
3. Assessment of Safety Consequences There were no safety consequences associated with this event. The unit remained at power throughout the event.
The charging system has two credited safety functions:
1. Inventory Control 2. Boration for Reactivity Control The impacts of a loss of charging on these safety functions are as follows.
1. Inventory Control: As an alternative to charging, inventory control can be achieved by Reactor Coolant System (RCS) depressurization and High Pressure Safety Injection (HPSI).
2. Boration for Reactivity Control: Like Inventory Control, Boration can be achieved using (HPSI) following RCS depressurization.
4. Corrective Action The following corrective actions have been entered into the Millstone Station's Corrective Action Program:
1. Formal training on failure mode identification and evaluation techniques to support design change preparation will be developed.
2. Key lessons learned from this event will be provided in Engineering Support (ES) continuing training.
3. DNC will develop and implement modifications to the charging system to prevent nitrogen intrusion into the common pump suction header from a postulated bladder failure.
4. The design of the discharge dampener assembly will be changed to address the shell geometry discrepancy.
5. Future purchase orders with Energy Steel (the discharge piiisation dampener shell manufacturer) will include DNC holdpoints requiring use-as-is and repair nonconformance dispositions to be reviewed and approved by DNC prior to commencing with further fabrication.
Additional corrective actions are being taken in accordance with the station's corrective action program.
5. Previous Occurrences A previous event occurred on Unit 2 on March 7, 2003, which resulted in the loss of the charging function. This was reported in LER 2003-003-00 and supplemented in LER 2003-003-01 Energy Industry Identification System (EDS) codes are identified in the text as [XX].
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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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