05-11-2006 | On March 14, 2006, at approximately 0941 hours0.0109 days <br />0.261 hours <br />0.00156 weeks <br />3.580505e-4 months <br />, with Donald C. Cook Nuclear Plant ( CNP) Unit 2 in MODE 1, Maintenance test technicians performed pressure testing of the inner and outer Unit 2 Containment Airlock (2-AIRLOCK-C612) door seals. The inner airlock door was the first door to be tested and this surveillance testing was successfully completed. Pressure testing of the outer airlock door seals was not successful and air could be heard escaping during the test. Investigation revealed that on March 13, 2006, contract Maintenance personnel exited the Unit 2 Containment via 2-AIRLOCK-C612 at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />. These individuals failed to ensure the latch for the outer airlock door was fully engaged. This resulted in the equalizing air valve failing to seat. The cause of this error has been determined to be improper operation of the airlock doors associated with 2-AIRLOCK-C612 by the contract maintenance personnel. Corrective actions included the immediate closure of the outer airlock door, ensuring the responsible personnel were instructed on the proper operation of the airlock doors, issuance of a lessons learned to all maintenance personnel to alert them of the error and to refresh them on the proper operation of the airlock doors associated with 2-AIRLOCK-C612, and the verification that placards are in place at each airlock door for both the upper and lower airlocks in both Unit 1 and Unit 2 to provide guidance on the proper operation of the airlock doors. Operations, Radiation Protection, and Engineering will also complete the lessons learned to ensure these groups understand the proper operation of the airlock doors. During the time period of this event, the inner airlock door was closed and operable and 2- AIRLOCK-C612 was capable of performing its design function. This condition is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as an operational condition prohibited by Technical Specification 3.6.2, Containment Air Locks. Specifically, the contract Maintenance personnel did not verify the inner airlock door was closed within one hour of the failure to fully dose the outer airlock door. |
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Conditions Prior to Event Unit 2 — Mode 1 at 100% power.
Description of Event
On March 14, 2006, at approximately 0941 hours0.0109 days <br />0.261 hours <br />0.00156 weeks <br />3.580505e-4 months <br />, with Donald C. Cook Nuclear Plant (CNP) Unit 2 in MODE 1, Maintenance test technicians conducted routine operability testing of the inner and outer airlock doors for the Unit 2 Lower Containment Airlock (2-AIRLOCK-C612) [AL]. The inner airlock door was tested first and successfully passed its operability test. The outer airlock door was subsequently tested and audible leakage was detected by test personnel. Indiana Michigan Power Company (I&M) immediately investigated the cause of the excessive leakage and determined that the airlock door latching mechanism was not fully engaged. The lack of full engagement resulted in insufficient seating of the equalizing air valve. Upon discovery, the outer airlock door was immediately sealed dosed. Upon obtaining proper closure of the outer airlock door, the outer airlock door was re-tested, resulting in a successful leak rate of 0.0 SCCM.
l&M performed a review of the usage for 2-AIRLOCK-C612 and determined that contract Maintenance personnel last used 2-AIRLOCK-C612 on March 13, 2006, at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />.
l&M reviewed Technical Specification 3.6.2, Containment Air Locks, and determined that the requirement of Required Action A.1, which for this event required the inner airlock door be verified closed within one hour, was not met. Therefore, this event is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the plant's technical specifications. During the time period of this event the inner airlock door was closed and operable and 2-AIRLOCK-C612 was capable of performing its design function.
Cause of Event
The cause of this error has been determined to be improper operation of the airlock doors associated with 2-AIRLOCK-C612 by contract maintenance personnel.
Analysis of Event
The configuration of the partially closed outer airlock door meant that the outer airlock door for 2-AIRLOCK-C612 may not have been able to perform its design function. However, the inner airlock door was operable and properly dosed and capable of performing its designed safety function. The period of inoperability for the outer airlock door includes the time from the previous opening of the outer door on March 13, 2006, at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, and continuing to the successful completion of the operability surveillance test on March 14, 2006, at 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />.
Each air lock door has been designed and tested to certify its ability to withstand pressure in excess of the maximum expected pressure following a Design Basis Accident in containment. As such, closure of a single door supports containment operability. Each of the doors contains double-gasketed seals and local leakage rate testing capability to ensure pressure integrity. To affect a leak-tight sea!, the air lock design uses pressure- seated doors (i.e., an increase in containment internal pressure results in increased sealing force on each door).
Consequently, it is judged that this event would not have resulted in any airlock leakage from containment during an accident, and the airlock remained fully functional during this time because the inner door was in the proper closed position.
Corrective Actions
Actions Taken:
The outer airlock door of 2-AIRLOCK-C612 was immediately sealed dosed and successfully leak tested.
The inner airlock door for 2-AIRLOCKC612 and the inner and outer airlock doors for the Unit 2 upper airlock were satisfactorily tested.
Both the inner and outer airlock doors for the upper and lower Unit 1 airlocks were satisfactorily tested.
The individuals who failed to correctly seal dosed the outer door of 2-AIRLOCK-C612 were instructed on the proper method of dosing and verifying dosed the doors associated with 2-AIRLOCK-C612.
l&M issued a lessons learned (required reading) to all Maintenance personnel to alert them of the error and to refresh their knowledge of the proper operation of the airlock doors associated with 2-AIRLOCK-C612.
and Unit 2 to provide guidance on the proper operation of the airlock doors.
l&M has expanded the distribution of the lessons learned to include all Operations, Radiation Protection, and Engineering personnel.
l&M has provided copies of Lessons Learned #40 to the Work Control Center Senior Reactor Operator and incorporated them into the Unit 1 and Unit 2 Containment Entry Logbooks.
Action To Be Taken:
l&M will add the information contained in Lessons Learned #40 to the Indoctrination Training given to contractors as they come on site.
Previous Similar Events
None.
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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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