12-04-2006 | his voluntary LER is being submitted to report a condition that may be of generic interest for licensees.
n October4, 2006, at 0138, the tvlain Control Room (MCR) received an annunciator alarm for MCR low pressure.
Operations entered the applicable alarm response and instructed a Non-licensed Operator (NLO) to adjust Auxiliary Building pressure. At 0220, an NLO adjusted pressure in the Auxiliary Building, raising it to above the minimum required alue. Operations personnel continued to investigate the reason for the MCR annunciator alarm. At 0247, Operations personnel reported to the MCR that the door that connects Division 21 Miscellaneous Equipment Electric Room and the rain B Control Room Ventilation Room was found open. Operations personnel promptly shut the door and the MCR low pressure annunciator cleared. A late log entry was made to enter Technical Specification (TS) 3.7.10 conditions A & E and TS 3.0.3 for both units at the point of discovery of the door being found open, which was at 0247. The LCOs were subsequently exited immediately after the door was closed at 0247. This did not result in a dual unit shutdown.
here were no safety consequences impacting plant or public safety as a result of this event.
Braidwood Station is reporting this as a voluntary Licensee Event Report.
NRC FORM 36 2004) PRINTED ON RECYCLED PAPER |
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LER-2006-002, Units 1 and 2 Entry into Limiting Condition for Operation 3.0.3 due to Main Control Room Ventilation Envelope Low PressureDocket Number |
Event date: |
10-04-2006 |
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Report date: |
12-04-2006 |
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Initial Reporting |
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4562006002R00 - NRC Website |
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Plant Operating Conditions Before The Event:
Event Date: October 4, 2006 Event Time: 0247 Unit: 1 MODE: 1 Reactor Power: 100 percent Unit: 2 MODE: 1 Reactor Power: 87 percent Unit 1 Reactor Coolant System (RCS) [AB] Temperature: 587 degrees F. Pressure: 2233 psig Unit 2 Reactor Coolant System (RCS) [AB] Temperature: 575 degrees F. Pressure: 2241 psig . Description of Event:
There were no additional structures, systems or components inoperable at the beginning of the event that contributed to the severity of the event.
On October 3, 2006, at 0730, Maintenance began a load test of a new constant voltage transformer (CVT). The testing continued into October 4, 2006. Two electricians that were assigned to complete the CVT test were alternating responsibilities of taking test readings on the CVT every 30 minutes.
On October 4, 2006, The first electrician (EMD1) was in the testing area between 0030 and 0130. During this time, EMD1 noted the increase of heat in the room. Several times during EMD1's duties, he opened the door between the Division 21 Miscellaneous Equipment Electric Room and the Train B Control Room Ventilation Room [VI], standing in the archway to cool himself, and then closed the door. The door was held open for no more than three minutes. At approximately 0130, a second electrician (EMD2) relieved EMD1. EMD2 placed a roll of tape between the door and the door casing to allow cooler outside air to enter the room.
At 0138, the Main Control Room (MCR) received an annunciator alarm for MCR low pressure. Operations entered the applicable alarm response and instructed a Non-licensed Operator (NLO) to adjust Auxiliary Building pressure.
At 0220, an NLO adjusted pressure in the Auxiliary Building, raising it above the minimum required value.
Operations personnel continued to investigate the reason for the MCR annunciator alarm.
At 0247, Operations personnel reported to the MCR that the door that connects Division 21 Miscellaneous Equipment Electric Room and the Train B Control Room Ventilation Room was found open. Operations personnel promptly shut the door and the MCR low pressure annunciator cleared.
A late log entry was made to enter Technical Specification (TS) 3.7.10 conditions A & E and TS 3.0.3 for both units at the point of discovery of the door being found open, which was at 0247. The LCOs were subsequently exited immediately after the door was closed at 0247. This did not result in a dual unit shutdown.
This information is being transmitted to the NRC as a voluntary Licensee Event Report to report a condition that may be of potential generic interest for licensees and to describe the fact that the station entered TS Limiting Condition for Operation (LCO) 3.0.3 for the aforementioned condition. NUREG 1022 (Revision 2) states: TS LC(} 3.0.3 establishes requirements for actions when: (1) an LCO is not met and the associated ACTIONS are not met; (2) an associated ACTION is not provided, or (3) as directed by the associated ACTIONS themselves. Entry into TS LCO 3.0.3 is not necessarily reportable under this criterion. However, it should be considered reportable under this criterion if the condition is not corrected within an hour, such that it is necessary to initiate actions to shutdown, cool down, etc.
Entry into TS LCO 3.0.3 did not result in a reportable condition because it was not necessary to initiate actions to shutdown within one hour as Operations personnel were fully aware of the MCR low pressure annunciator and were taking the appropriate action to identify the cause of the alarm condition. Had the duration of the investigation by Operations exceeded the allowed outage time established in TS LCO 3.0.3, this event would have been reportable under 50.73(a)(2)(i)(B), "Operation or Condition Prohibited by Technical Specifications.
Cause of Event
The cause of the event was due to an electrician (EMD2) improperly propping open the door between the Division 21 Miscellaneous Equipment Electric Room and the Train B Control Room Ventilation Room.
To conduct the test of the new CVT, a resistive load bank is wired to the CVT to simulate an electrical load. As with all resistive loads, this bank produced a great deal of heat, which began to affect ambient temperatures inside the room. The closest door to the work site connects the Division 21 Miscellaneous Equipment Electric Room and the OB Control Room Ventilation Room. EMD2 placed a roll of tape between the door and the door casing to allow cooler outside air to enter the room.
On the door is signage that states "DO NOT IMPAIR this HVAC Boundary before referring to PBI procedure BwAP 1110-3.
This signage was not noticed by EMD2 because of his positioning at the work location. During the investigative interviews, EMD2 stated he did not recognize the sign on the door; therefore he felt propping open the door was not wrong because he was in attendance. This decision was not discussed with the EM Supervisor or with Operations.
This was an improper decision, as there are very few doors that are allowed to be propped open in the plant. It is an expectation for all employees to question procedural compliance before propping any door.
Safety Consequences:
There were no safety consequences impacting plant or public safety as a result of this event. Actions taken in response to the annunciator alarm for low pressure restored the pressure differential in the Auxiliary Building. The opened door was located and closed. For the duration of the event (70 minutes), the MCR pressure remained positive.
This event did not result in a safety system functional failure.
Corrective Actions:
Corrective actions in response to this issue included coaching and counseling of the individuals involved in the issue, initiating a Training Review to evaluate adding FBI criteria to 2007 annual training for all maintenance departments, and holding a station-wide stand down to communicate human performance errors recently encountered at the station.
Previous Occurrences:
There have been no previous similar events at Braidwood Station.
Component Failure Data:
Manufacturer � Nomenclature � Model � Mfg. Part Number N/A � N/A � N/A � N/A
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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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