05000458/LER-2006-002

03-27-2006

On January 24, 2006, at 7:32 p.m. CST, the high pressure core spray (HPCS) system was Inadvertently initiated during surveillance testing. The plant was operating at 100 percent power at the time. The HPCS injection valve was open for approximately 40 seconds before the operators manually closed the valve. The Division 3 diesel generator (DG) also automatically started in response to the actuation signal. The DG did not automatically connect to the Division 3 switchgear since there was not a low voltage condition on that bus. The manual closure of the injection isolation valve caused the system to be incapable of responding to an automatic actuation signal. The manual override of the injection isolation valve was reset approximately 97 minutes after the event, restoring the system to its standby condition. This event was caused by lack of procedural guidance concerning test leads needed for the surveillance. The affected procedures were subsequently revised and successfully completed.

This event is being reported in accordance with 10CFR5073(a)(2)(1v) as an invalid actuation of the HPCS system, and with 10CFR50.73(b)(3)(v)(d) as a condition that caused the loss of function of the HPCS system. This event is also reportable pursuant to River Bend Station TechniCal Requirements Manual Section 5.6.9.2., "ECCS Systems Actuations.

0NRC FORM 366 (6-2004) PRINTED ON RECYCLED PAPER

LER-2006-002, Loss of Safety Function of High Pressure Core Spray Due to Manual Deactivation
Docket Number
Event date:	01-24-2006
Report date:	03-27-2006
4582006002R00 - NRC Website
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Licensee Event Report

Docket Number

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		Reporting criterion
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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05000458/LER-2006-002

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