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| Title | Reporting criterion | |
|---|---|---|
| 05000361/LER-2004-002 | Manual Reactor Trip and Initiation of Auxiliary Feedwater in Response to Loss of Main Feedwater | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000316/LER-2004-002 | Unplanned Automatic Reactor Protection System Actuation Due to Feedwater Transient During a Power Reduction | |
| 05000263/LER-2004-003 | ||
| 05000364/LER-2004-003 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000301/LER-2004-003 | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | |
| 05000528/LER-2004-003 | MANUAL REACTOR TRIP - SLIPPED CONTROL ELEMENT ASSEMBLY | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000255/LER-2004-003 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000354/LER-2004-003 | Both Trains of Control Room Emergency Filtration (CREF) Declared Inoperable | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident |
| 05000305/LER-2004-003 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| 05000387/LER-2004-003 | Manual Scram Following Main Turbine High Vibration | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000400/LER-2004-003 | Automatic Reactor Trip Due to Rod Control Card Failure | |
| 05000237/LER-2004-003 | Exelon Generation Company, LLCw www.exeloncorp.com Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 Nuclear 10 CFR 50.73 June 28, 2004 SVPLTR: #04-0040 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DRP-19 and DRP-25 NRC Docket Nos. 50-237 and 50-249 Subject:RLicensee Event Report 2004-003-00, "Units 2 and 3 Control Room Emergency Ventilation System Inoperable Due To Damper Failure To Close" Enclosed is Licensee Event Report 2004-003-00, "Units 2 and 3 Control Room Emergency Ventilation System Inoperable Due To Damper Failure To Close," for Dresden Nuclear Power Station. This event is being reported in accordance with 10 CFR 50.73(a)(2XIXB), "Any operation or condition which was prohibited by the plant's Technical Specifications," and 10 CFR 50.73(a)(2)(v)(D), "Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident." Should you have any questions concerning this report, please contact Jeff Hansen, Regulatory Assurance Manager, at (815) 416-2800. Respectfully, Danny G. Bost Site Vice President Dresden Nuclear Power Station Enclosure cc:RRegional Administrator — NRC Region NRC Senior Resident Inspector — Dresden Nuclear Power Station . NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OBM NO. 3150-0104 EXP 741-2004 (7-2001) 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 Management Branch 0%LICENSEE EVENT REPORT (LER) 6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e mail to bisienrc.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 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, tie information collection. 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Dresden Nuclear Power Station Unit 2 05000237 1 of 4 4. TrrLEUUnits 2 and 3 Control Room Emergency Ventilation System Inoperable Due To Damper Failure To Close | 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 |
| 05000220/LER-2004-003 | Inadequate Environmental Qualification Barrier Considerations Resulting in an Unanalyzed Condition | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
| 05000247/LER-2004-003 | Plant in a Condition Prohibited by Technical Specifications due to Error Making Gaseous Radiation Monitor Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000249/LER-2004-003 | UUnit 3 Scram Due to Loss of Offsite Power and Subsequent Inoperability of the Standby Gas Treatment System for Units 2 and 3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000413/LER-2004-003 | Unanalyzed Condition Due To Inadequate Evaluation of Fire Interactions | |
| 05000265/LER-2004-003 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | |
| 05000395/LER-2004-003 | Emergency Diesel Generator Start and Load Due to Inadvertent Actuation of 1DA Undervoltage Test Switch | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000362/LER-2004-003 | Invalid Actuation of Emergency Diesel Generator due to an Invalid Signal | |
| 05000293/LER-2004-003 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | |
| 05000316/LER-2004-003 | Failure To Comp y With Containment Ventilation Operability Requirements Specified In Technical Specifications 3.0.4, 3.9.4, and 3.9.9 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(V)(C) |
| 05000364/LER-2004-004 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | |
| 05000461/LER-2004-004 | An Delon Company Clinton Power Station R. R. 3, Box 228 Clinton, IL 61727 10 CFR 50.73 U-603690 September 10, 2004 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Subject:LLicensee Event Report 2004-004-00 Enclosed is Licensee Event Report (LER) No. 2004-004-00: Reactor Scram While Placing Residual Heat Removal B into Shutdown Cooling. This report is being submitted in accordance with the requirements of 10CFR50.73. Should you have any questions concerning this report, please contact Mr. William Iliff, Regulatory Assurance Manager, at (217)-937-2800. Respectfully, /401e R. . Bement Si e Vice President Clinton Power Station JLP/blf Enclosure:LLicensee Event Report 2004-004-00 cc:LRegional Administrator — NRC Region III NRC Senior Resident Inspector — Clinton Power Station Office of Nucleai- Facility Safety — IEMA Division of.Nuclear Safety U. APPROVED BY OMB NO. 3150-0104 EXPIRES 7-31-2004NRC FORM 366 • U.S. NUCLEAR REGULATORY Estimated burden per response to comply with this mandatory information collection request: 50 (7-2001) COMMISSION hours. Reported lessons learned are incorporated Into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch (T-6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to LICENSEE EVENT REPORT (LER)b bjs1@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(See reverse for required number of information collection does not display a currently valid OMB control number, the NRC may notdigits/characters or each block) conduct or sponsor, and a person is not required to respond to, the information collection. , 1.FACILITY NAME I 2. DOCKET NUMBER I 3. PAGE 1 Clinton Power Station I 05000461 I 1 OF 3 • IT I4. T LE Reactor Scram While Placing Residual Heat Removal S' Into Shutdown Cooling | |
| 05000293/LER-2004-004 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| 05000269/LER-2004-004 | Improper Overloads Installed on Control Room Ventilation Filter Train | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000265/LER-2004-004 | Quad Cities Nuclear Power Station Unit 2 05000265 1 of 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000251/LER-2004-004 | Turkey Point Unit 4 05000251 1 OF 4 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000247/LER-2004-004 | 450 Broadway, GSB P.O. Box 249Entergy Buchanan, NY 10511-0249 Tel 914 734 6700 Fred Dacimo Site Vice President Administration January 6, 2005 Indian Point Unit No. 2 Docket Nos. 50-247 N L-05-003 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Subject:L Licensee Event Report # 2004-004-00, "Emergency Diesel Generator Actuation from 480 VAC Safety Bus Undervoltage/Blackout Signal Due to Missing Tie Breaker Contact Fingers." Dear Sir: The attached Licensee Event Report (LER) 2004-004-00 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-IP2-2004-05927. There are no commitments made by the Licensee in the attached LER. 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, ....�0-, Fred R. Dacimo Site Vice President Indian Point Energy Center Docket No. 50-247 NL-05-003 Page 2 of 2 Attachment: LER-2004-004-00 CC: Mr. Samuel J. Collins Regional Administrator — Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspector's Office U.S. Nuclear Regulatory Commission Indian Point Unit 2 P.O. Box 59 Buchanan, NY 10511-0059 Mr. Paul Eddy State of New York Public Service Commission 3 Empire Plaza Albany, NY 12223-1350 INPO Record Center 700 Galleria Parkway Atlanta, Georga 30339-5957 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. 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, 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 3. PAGE INDIAN POINT 2 05000-247 16OF66 4. TITLE Emergency Diesel Generator Actuation from 480 VAC Safety Bus Undervoltage/Blackout Signal Due to Missing Tie Breaker Contact Fingers | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 05000237/LER-2004-004 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | |
| 05000219/LER-2004-005 | 1 OF 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000305/LER-2004-005 | 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 | |
| 05000354/LER-2004-005 | Hope Creek Generating Station 05000354 1 OF 3 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000237/LER-2004-005 | • ■■ xen® Exelon Generation Company, LLC:www.exeloncorp.com NuclearDresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 10 CFR 50.73 August 30, 2004 SVPLTR: #04-0058 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DRP-19 and DRP-25 NRC Docket Nos. 50-237 and 50-249 Subject: Licensee Event Report 2004-005-00, "Units 2 and 3 Inoperable Turbine Condenser Vacuum - Low Switches" Enclosed is Licensee Event Report 2004-005-00, "Units 2 and 3 Inoperable Turbine Condenser Vacuum - Low Switches," for Dresden Nuclear Power Station. This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications." Should you have any questions concerning this report, please contact Jeff Hansen, Regulatory Assurance Manager, at (815) 416-2800. Respectfully, r( •11 GI/ Danny G. Bost Site Vice President Dresden Nuclear Power Station Enclosure cc: Regional Administrator — NRC Region III NRC Senior Resident Inspector — Dresden Nuclear Power Station _0" NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OBM NO. 3150-0104 EXP 7-31.2004 (7-2001) 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 Management Branch (T. LICENS EE EVENT REPORT (LER) 6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555.001, or by intemet e mail to bis1@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 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 Dresden Nuclear Power Station Unit 2 05000237 1 of 4 4.Trrt.tUUnits 2 and 3 Inoperable Turbine Condenser Vacuum - Low Switches | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000293/LER-2004-005 | 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 | |
| 05000498/LER-2004-005 | Standby Diesel Generator 12 Not Being Declared Inoperable While the Auxiliary Feedwater Pump 12 Breaker Cell Switch was Being Replaced | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 05000483/LER-2004-006 | AmerenUE PO Box 620 Callaway Plant Fulton, MO 65251 wAmeren UE May 25, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 ULNRC05011 Ladies and Gentlemen: DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO. FACILITY OPERATING LICENSE NPF-30 LICENSEE EVENT REPORT 2004-006-00 "A" Steam Generator tube inspection results classified as C-3 The enclosed licensee event report is submitted in accordance with Technical Specification 5.5.9 and 5.6.10(c) report the Refuel 13 Inservice Inspection Results for the "A" Steam Generator were classified as C-3 due to greater than one percent of the inspected tubes being defective. Included with this License Event Report is the Special Report and Attachment detailing the "A" Steam Generator tube inspection results. This event was initially reported in Event Notification #40705 in which it stated that this report was required by an Administrative Technical Specification and that the "A" Steam Generator tubes do not meet the criteria for serious tube degradation and thus does not represent a degraded or unanalyzed condition. This letter does not contain new commitments. Sincerely, tatA444.4-ailitc Warren A. Witt Manager, Callaway Plant Enclosure subsidiary of Arne= Cogoration ULNRC05011 May 25, 2004 Page 2 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies) Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7E1 Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339 NRC FORM 366� U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104�EXPIRES 7-31-2004 (7-2031)� 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 LICENSEE EVENT REPORT (LER) Management Branch (T-6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to bjwlenrc.gov, and to the Desk Officer, Office of (See reverse for required number of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of Management and digits/characters for each block) Budget, Washington, 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� I3. PAGE CALLAWAY PLANT UNIT 1 05000 483 1�OF�2 4. TITLE "A" Steam Generator tube inspection results classified as C-3. | |
| 05000354/LER-2004-009 | As Found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |