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| Title | Reporting criterion | |
|---|---|---|
| 05000247/LER-2005-002 | DTechnical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for One Inoperable Train of ECCS Caused by Gas Intrusion from a Leaking Check Valve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000244/LER-2005-002 | Emergency Diesel Generator Start Resulting From Loss of Off-Site Power Circuit 751 | |
| 05000370/LER-2005-002 | Ice Condenser Lower Inlet Door Failed Surveillance Testing | |
| 05000331/LER-2005-002 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| 05000311/LER-2005-002 | Reactor Coolant Instrument Line Through-Wall Leak | 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded |
| 05000306/LER-2005-002 | 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 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | |
| 05000305/LER-2005-002 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | |
| 05000286/LER-2005-002 | • Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249Entergy Buchanan. NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration July 5, 2005 Indian Point Unit No. 3 Docket Nos. 50-286 N L-05-078 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Subject:L Licensee Event Report # 2005-002-00, "Automatic Reactor Trip Due to 32 Steam Generator Steam Flow/Feedwater Flow Mismatch Caused by Low Feedwater Flow Due to Inadvertent Condensate Polisher Post Filter Bypass Valve Closure." Dear Sir: The attached Licensee Event Report (LER) 2005-002-00 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-IP3-2005-02478. 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. Sincerely, 4F-/t R. Dacimo Vice President Indian Point Energy Center Docket No. 50-286 NL-05-078 Page 2 of 2 Attachment: LER-2005-002-00 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 3660 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.RReported lessons teamed 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 29555-0001, or by InternetLICENSEE EVENT REPORT (LER) e-mail to Infocoilectsenrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-l0202, (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. FACIUTY NAME 2. DOCKET NUMBER 3. PAGE INDIAN POINT 3 05000-286 10OF06 4. TITLE Automatic Reactor Trip Due to 32 Steam Generator Steam Flow/Feedwater Flow Mismatch Caused by Low Feedwater Flow Due to Inadvertent Condensate Polisher Post Filter Bypass Valve Closure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000263/LER-2005-002 | ||
| 05000255/LER-2005-002 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000456/LER-2005-003 | Licensed Maximum Power Level Exceeded Due to Feedwater Heater Transient | |
| 05000454/LER-2005-003 | Technical Specification (TS) 3.9.4 Violation Due to Imprecise Original TS and TS Bases Wording | |
| 05000423/LER-2005-003 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | |
| 05000395/LER-2005-003 | PLANT TRIP AND ASSOCIATED FIRE IN S' CONDENSATE PUMP MOTOR | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000369/LER-2005-003 | Containment Closure Requirements Not Met During Core Alterations | |
| 05000352/LER-2005-003 | Scram Due To Invalid Actuation Of Main Generator Output Breaker Position Monitor Circuit | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000333/LER-2005-003 | Entergy Nuclear Operations, Inc. James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093Entergy Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan Site Vice President - JAFDecember 13, 2005 JAFP-05-0185 United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555 Subject: Docket No. 50-333 LICENSEE EVENT REPORT: LER-05-003-01 (CR-JAF-2005-02593) Plant Shutdown Due to Through-Wall Crack in Torus Dear Sir: LER-05-003 revision 0 was submitted in accordance with 10 CFR 50.73(a)(2)(i)(A), "The completion of any nuclear plant shutdown required by the plant's Technical Specifications" and 10 CFR 50.73(a)(2)(ii)(A), "The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded." The formal risk evaluation was completed subsequent to the submittal of the original LER. In addition, a calculation used to quantify leakage rates through the Torus crack was subsequently revised. The LER has been revised to incorporate the pertinent information from the risk evaluation and revised calculation. There are no commitments contained in this report. Questions concerning this report may be addressed to Mr. Jim Costedio at (315) 349 -6358. Very truly yours, TAS:DD:dd Enclosure cc: USNRC, Region 1 USNRC, Project Directorate USNRC Resident Inspector INPO Records Center U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2007NRC FORM 366 (6-2004) COMMISSION Estimated burden per response to comply with this mandatory information collection request 50 hours. Reported 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,LICENSEE EVENT REPORT (LER) or by Internet 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,(See reverse for required number of ! ' ! digits/characters for each block) DC 20503. If a means used to impose 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 3. PAGE James A. FitzPatrick Nuclear Power Plant 05000333 16OF 6 4. TITLE Plant Shutdown due to Through-Wall Crack in Torus _ | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
| 05000298/LER-2005-003 | Cooper Nuclear Station 05000298 1 of 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000293/LER-2005-003 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000247/LER-2005-003 | Automatic Start of Both Motor Driven Auxiliary Feedwater Pumps Due to Trip of 22 Main Feedwater Pump Caused by Low Lube Oil Pressure Due to an Inadequate Procedure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000244/LER-2005-003 | Emergency Diesel Generator Start Resulting From Loss of Off-Site Power Circuit 751 | |
| 05000440/LER-2005-003 | Lack of Suction Flow Path Causes High Pressure Core Spray to be Inoperable | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
| 05000388/LER-2005-003 | UReactor Manual Scram due to Loss of Main Transformer Cooling | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000370/LER-2005-003 | Containment Closure Requirements Not Met During Core Alterations | |
| 05000346/LER-2005-003 | Containment Electrical Penetration Not Equipped With Backup'Electrical Fault Protection | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
| 05000336/LER-2005-003 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000331/LER-2005-003 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000306/LER-2005-003 | 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 | |
| 05000305/LER-2005-003 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | |
| 05000286/LER-2005-003 | Inadvertent Actuation and Automatic Start of the Auxiliary Feedwater Pumps During Reactor Protection Logic Testing Due to Personnel Error | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000263/LER-2005-003 | ||
| 05000443/LER-2005-004 | Noncompliance with the Technical Specification for Offsite AC Sources | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000423/LER-2005-004 | ||
| 05000369/LER-2005-004 | Ice Condenser Lower Inlet Door Failed Surveillance Testing | |
| 05000353/LER-2005-004 | Automatic Scram Due To EHC Malfunction That Closed The Main Turbine Control Valves | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000247/LER-2005-004 | Automatic Start of both Motor Driven Auxiliary Feedwater Pumps Due to 22 Steam Generator High-High Level Signal Caused by Overfeeding Due to Personnel Error | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000237/LER-2005-004 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000454/LER-2005-004 | ethnical Specification Required Action Not Satisfied Due to Ambiguous Implementing Procedure. | |
| 05000370/LER-2005-004 | Actuation of Main Steam Isolation Valves Due to Human Error. | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000346/LER-2005-004 | Containment Hydrogen Analyzers Inoperable due to Presence of Check Valves in Moisture Removal System | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000331/LER-2005-004 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| 05000305/LER-2005-004 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | |
| 05000286/LER-2005-004 | Manual Reactor Trip Due to a Service Water Leak Inside the Main Generator Exciter Enclosure Caused by Exciter Cooler Gasket Leaks | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000266/LER-2005-004 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | |
| 05000263/LER-2005-004 | ||
| 05000423/LER-2005-005 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | |
| 05000369/LER-2005-005 | Inoperable source range neutron flux monitors during mode 6 and core alterations. | |
| 05000352/LER-2005-005 | Missed Surveillance Resulted In A Condition Prohibited By Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000333/LER-2005-005 | Automatic Reactor Scram on Low Reactor Vessel Water Level During Reactor Feed Pump Control Reset | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000388/LER-2005-005 | Reactor Automatic Scram due to a Main Generator Lockout | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |