3-16-2007 | Unit Status: At the time this historical condition was identified, Unit 1 and Unit 2 were in Mode 1 (Power Operation) at 100 percent power.
Event Description:1 On January 17, 2007, Engineering identified that a value recorded during performance of Technical Specification (TS)0 3.8.4.5 Surveillance Requirement (SR)0 on May 12, 2005 for vital battery EVCC did not meet the acceptance criteria of the SR.
Corrective actions for the failed TS SR were not performed within the COMPLETION TIME allowed by TS 3.8.4 CONDITION A. This historical event, which constitutes a condition prohibited by Technical Specifications,0 (a)(2)(i)(B). This is reportable per 10 CFR 50.73 event was determined to be of no significance to the health and safety of the public.
Event Cause: The cause for the failure to recognize and report not meeting the TS SR acceptance criteria was human error.0 The in-plant investigation determined that the value was recorded in error and was not truly outside the TS SR acceptance criteria.
Corrective Actions: The importance of reporting any data that does not met an acceptance criteria has been conveyed to Maintenance personnel.0 Affected procedures will be reviewed and enhanced to clearly delineate that the procedure affects TS or Selected Licensee Commitments ( SLC) and require a signature certifying acceptance criteria are met. |
---|
LER-2007-001, 369 5McGuire Nuclear Station Unit 1 05000 1 OF5Docket Number |
Event date: |
1-17-2007 |
---|
Report date: |
3-16-2007 |
---|
3692007001R00 - NRC Website |
|
BACKGROUND
At the time this historical condition was identified, McGuire Unit 1 and Unit 2 were in Mode 1 at 100% power. No systems, structures, or components were out of service at the time of this event which contributed to this event.
Applicable Energy Industry Identification system and component codes are enclosed within brackets. McGuire unique system and component identifiers are contained within parentheses.
The 125 VDC Vital Instrumentation and Control Power System [EJ](EPL) is designed to provide a reliable and continuous source of power to a select group of Class lE instrumentation and control equipment required for start up, normal operation, and orderly shutdown of each unit. Should a loss of offsite power (LOOP) or blackout (no voltage or a degraded voltage condition on the 4KV Essential Buses) occur, this equipment is required to safely shutdown the plant.
The EPL system consists of four independent and physically separate load channels. Each channel is comprised of a battery, a charger connection box, a battery charger, a 125 VDC distribution center, and two 125 VDC power panelboards. Each of the batteries is sized to supply the continuous emergency loads and momentary loads fed from its distribution center plus supply the loads of its cross tied distribution center for one hour.
Technical Specification (TS) Surveillance Requirement (SR) 3.8.4.5, in combination with TS SR 3.8.4.4 provide an indication of physical damage or abnormal deterioration that could indicate degraded battery condition by performing a visual inspection and measuring the resistance of inter-cell, inter-rack, inter-tier, and terminal connections. Associated test acceptance criteria (TAC) in SR 3.8.4.5 include:
Verify battery connection resistance is connections, and McGuire TS 3.8.4 specifies that the four channels of DC sources shall be operable in Modes 1, 2, 3, and 4. Condition A requires that, in the event one channel of DC sources is inoperable, the affected channel must be restored to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> OR verify associated bus tie breakers are closed between DC channels within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and restore the affected channel to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
EVENT DESCRIPTION
12 May 2005 - Maintenance performed procedure IP/0/A/3061/007, "Vital Battery and Terminal Post Inspection," to satisfy TS SR 3.8.4.5 for vital battery EVCC. One (of a total of 59) of the recorded values for inter-cell resistance was 1.7E-4 ohms. This exceeded the acceptance criteria of the SR.
Per step 10.4.2 D of IP/0/A/3061/007, "if inter-cell resistance readings are >1= 1.5E-4 ohms, notify responsible IAE supervisor and Control Room SRO that battery is out of Technical Specification limits and should be declared inoperable." This was not identified at the time and no actions were taken.
This resulted in exceeding the allowed completion time of TS 3.8.4 Condition A.
11 May 2006 - Maintenance performed IP/0/A/3061/007, "Vital Battery and Terminal Post Inspection," to satisfy TS SR 3.8.4.5 for vital battery EVCC, all values recorded met the acceptance criteria of the SR.
21 August 2006 - Maintenance performed PT/0/A/4350/038, "Vital Battery Service Test," to satisfy TS SR 3.8.4.7. The purpose of this SR is to "verify battery capacity is adequate to supply, and maintain in an OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test." All acceptance criteria for the SR were met.
14 December 2006 - Engineering was informed of a potential non-conservative TS value for vital battery inter-cell resistances identified during a Component Design Basis Inspection (CDBI) performed at another licensee's station. Engineering determined the McGuire Technical Specifications did contain a non-conservative value for vital battery inter-cell resistances.
This was entered into the Corrective Action (CA) program (PIP M-06-05905) and an operability evaluation was commenced.
11 January 2007 - Engineering completed the operability evaluation. The vital batteries were declared Operable but Degraded/Non-Conforming (OBDN).
17 January 2007 - During a review of historical data to support the reportability determination associated with the non-conservative TS value discovered above, Engineering discovered the value recorded during the performance of TS SR 3.8.4.5 on 12 May 2005 that did not meet the acceptance criteria.
25 January 2007 - McGuire Regulatory Compliance determined this event was reportable per 10CFR50.73 (a)(2)(i)(B).
05 February 2007 - Maintenance performed IP/0/A/3061/007, "Vital Battery and Terminal Post Inspection," on battery EVCC and all acceptance criteria was met.
CAUSAL FACTORS
The cause of the failure to recognize and report the failed TS SR acceptance criteria was human error. The in-plant investigation determined that the inter-cell resistance value was recorded in error and was not truly outside the TS SR acceptance criteria.
There has not been another case of a vital battery inter-cell resistance value being outside the acceptance criteria. Additionally, resistance values have been taken twice on battery EVCC following this event and all acceptance criteria was met.
CORRECTIVE ACTIONS
IMMEDIATE
1.IP/0/A/3061/007 placed on technical hold pending incorporation of changes deemed necessary in the root cause evaluation.
2.The importance of immediately reporting any data that does not meet Technical Specification acceptance criteria to Supervision and the Control Room Senior Reactor Operator was conveyed to the maintenance technicians involved.
3.McGuire Regulatory Compliance group was immediately informed of the past failure to meet TS SR 3.8.4.5 acceptance criteria.
SUBSEQUENT
1.Maintenance Superintendent issued a communication emphasizing the roles and responsibilities of the Procedure Verifier and Approver.
2.Placed all procedures on Hold that take the same data for the remaining affected batteries.
PLANNED
1. Revise IP/0/A/3061/007 to have Acceptance Criteria Met signoff that verifies Technical Specification data taken is acceptable.
2. Review and revise all Maintenance Procedures which document TS and SLC compliance to require a Acceptance Criteria Met verification by documented signature.
3. Operations, Chemistry, Radiation Protection and Engineering will review procedures that take TS or SLC data to evaluate if applicable signoffs for criteria met are required.
SAFETY ANALYSIS
The battery's ability to perform its safety function is conducted in TS SR 3.8.4.7 - the battery service (duty cycle) test, which is conducted every 18 months. This test was completed successfully on battery EVCC on October 19, 2004 and August, 21, 2006. Both tests demonstrated a battery terminal voltage margin in excess of 4.0 VDC following the most limiting portion of the duty cycle. This voltage margin along with total battery resistance was used to determine the amount of additional battery degradation (increased resistance) required before the battery would be considered inoperable. The Operability analysis revealed that the "TOTAL" EVCC battery inter-cell, inter-tier, and inter-rack connection resistance would have to increase by 2.048E-3 ohms for the available battery terminal voltage margin to decrease to zero. The average battery inter-cell connection resistance measurement during the May 12, 2005 surveillance was 4.37E-5 ohms. The number of battery inter-cell terminal connections required to reach 1.7E-4 ohms and eliminate all available margin (2.048E-3 ohms) would have been 16 connectors. 16 connectors would have had to be at the 1.7E-4ohm value for the battery operability to be in question [(1.7E-4 - 4.37E-5) x 16] = 2.021E-3 ohms.
Even though it was determined that the resistance value was recorded in error and was not truly outside the acceptance criteria, the above evaluation determined that vital battery EVCC would have been operable and completely capable of meeting its design and safety function requirements.
Therefore, it has been determined that there is no impact on either the estimated core damage frequency (CDF) or large early release frequency (LERF) due to this event such that the event described in this LER was not significant with respect to the health and safety of the public.
ADDITIONAL INFORMATION
A review of the McGuire corrective action database did not identify any other events within the past three years having similar circumstances, cause, and corrective actions. Therefore, the event described in this LER is not considered a recurring event.
|
---|
|
|
| | Reporting criterion |
---|
05000498/LER-2007-001 | Turbine-Driven Auxiliary Feedwater Pump Failed to Start During Surveillance Testing (Supplement 1) | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2007-001 | -f Unit 1 Automatic Reactor Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000263/LER-2007-001 | | | 05000266/LER-2007-001 | | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000269/LER-2007-001 | Dual Unit Trip from Jocassee Breaker Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000272/LER-2007-001 | ESF Actuation of Auxiliary Feedwater Pumps in Mode 3. | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000265/LER-2007-001 | Manual Reactor Scram on Increasing Condenser Backpressure Due to a Decrease in 2A Offgas Train Efficiency | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000278/LER-2007-001 | Laboratory Analysis Identifies Safety Relief Valves and Safety Valve Set Point Deficiencies | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000249/LER-2007-001 | Unit 3 High Pressure Coolant Injection System Declared Inoperable | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000282/LER-2007-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000247/LER-2007-001 | 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249Entergy Tel (914) 734-6700 Fred Dacimo Site Vice President Administration February 28, 2007 Indian Point Unit No. 2 Docket No. 50-247 NL-07-013 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Subject:L Licensee Event Report # 2007-001-00, "Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Residual Heat Removal Pump Due to an Electrical Supply Breaker Failure" Dear Sir: Pursuant to 10 CFR 50.73(a)(1), Entergy Nuclear Operations Inc. (ENO) hereby provides Licensee Event Report (LER) 2007-001-00. The enclosed LER identifies an event where the plant was operated in a condition prohibited by Technical Specifications, which is reportable under 10 CFR 50.73(a)(2)(i)(B). This condition has been recorded in the Entergy Corrective Action Program as Condition Report CR-IP2-2007-00013. 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, -Thr red R. Dacimo ite Vice President Indian Point Energy Center E Docket No. 50-247 NL-07-013 Page 2 of 2 Attachment: LER-2007-001-00 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 2 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. 3150-0104DEXPIRES: 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-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. 2. DOCKET NUMBER 1 3. PAGE1. FACILITY NAME: INDIAN POINT 2 05000-247 1 OF 4 4. TITLE: Technical Specification Prohibited Condition Due to Exceeding the Allowed Completion Time for an Inoperable Residual Heat Removal Pump Due to an Electrical Supply Breaker Failure | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ix) | 05000483/LER-2007-001 | . Single Train Inoperability in the Essential Service Water System due to Inadequate Valve Closure Setup | | 05000286/LER-2007-001 | 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249Entergy Tel (914) 734-6700 Fred Dacimo Site Vice President June 4, 2007 Indian Point 3 Docket No. 50-286 N L-07-052 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, D.C. 20555-0001 Subject:LLicensee Event Report # 2007-001-00, "Manual Reactor Trip Due to Decreasing Steam Generator Levels as a Result of the Loss of Feedwater Flow Caused by the Failure of 32 Main Feedwater Pump Train A Control Logic Power Supply" Dear Sir or Madam: Pursuant to 10 CFR 50.73(a)(1), Entergy Nuclear Operations Inc. (ENO) hereby provides Licensee Event Report (LER) 2007-001-00. The attached LER identifies an event where the reactor was manually tripped while critical, which is reportable under 10 CFR 50.73(a)(2)(iv)(A) . This condition has been recorded in the Entergy Corrective Action Program as Condition Report CR-IP3-2007-01775. There are no new commitments identified in this letter. Should you have any questions regarding this submittal, please contact Mr. T. R. Jones, Manager, Licensing at (914) 734-6670. Sincerely, Fred R. Dacimo Site Vice President Indian Point Energy Center cc:LMr. Samuel J Collins, Regional Administrator, NRC Region I NRC Resident Inspector's Office, Indian Point 3 Mr. Paul Eddy, New York State Public Service Commission INPO Record Center pP,c.1)-1
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 6/30/2007 (6-2004) Estimated burden per response to comply with this mandatory collection request:D50 hours.DReportedDlessons learned areDincorporated 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 INDIAN POINT 3 2. DOCKET NUMBER 13. PAGE 05000-286 1 OFTD5 4. TITLE Manual Reactor Trip Due to Decreasing Steam Generator Levels as a Result of the Loss of Feedwater Flow Caused by the Failure of 32 Main Feedwater Pump Train A Control Logic Power Supply | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000293/LER-2007-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000306/LER-2007-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000309/LER-2007-001 | Uncompensated Degradation in a Security System | | 05000414/LER-2007-001 | Failure to Comply with Action Statement in Technical Specification (TS) 3.3.1 for Loss of a Channel of the Solid State Protection System | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-2007-001 | Inoperability of the Chilled Water System - (21 and 22 Chillers Inoperable) | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000331/LER-2007-011 | . Undervoltage ConditiOn Resulted in the Actuation of the Emergency Diesel Generators | | 05000346/LER-2007-001 | Station Vent Radiation Monitor in Bypass due to Faulty Optical Isolation Board | 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 | 05000348/LER-2007-001 | Vire President - Farley Operating Company, Inc. Po51 Office Drawer 470 Ashford, Alabarid 36312-0470 Tel 334 814 4511 Fax 334 814 4728 SOUTHERN June 22, 2007 COMPANY Energy to Serve Your World Docket Nos.: 50-348 NL-07-1231 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant — Units 1 and 2
Licensee Event Report 2007-001-00
Technical Specification 3.8.1 Violation Due to
Failure of Breaker / Mechanism-Operated Cell Switch
Ladies and Gentlemen: Joseph M. Farley Nuclear Plant - Licensee Event Report (LER) No. 2007-001-00 is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(B). This letter contains no NRC commitments. If you have any questions, please advise. Sincerely, 7e. R. Johnson Vice President — Farley Joseph M. Farley Nuclear Plant 7388 North State Highway 95 Columbia AL 36319 JRJ/CHM Enclosure: Licensee Event Report 2007-001-00 - Unit 1 U. S. Nuclear regulatory Commission NL-07-1231 Page 2 cc:� Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, Vice President — Farley Mr. D. H. Jones, Vice President — Engineering RTYPE: CFA04.054; LC # 14596 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Ms. K. R. Cotton, NRR Project Manager — Farley Mr. E. L. Crowe, Senior Resident Inspector— Farley 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. Nudear Regulatory Commission, Washington, DC 2055570001, or by InternetLICENSEE EVENT REPORT (LER) e-mail to infocolledsanrc.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(See reverse for required number of 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, thedigits/characters for each block) information collection. 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Joseph M. Farley Nuclear Plant - Unit 1 05000 348 1 OF 4 4. TITLE Technical Specification 3.8.1 Violation Due to Failure of Breaker / Mechanism-Operated Cell (MOC) Switch | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000316/LER-2007-001 | As-Found Local Leak Rate Tests Not Performed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000456/LER-2007-001 | Unit 1 Reactor Trip Following a 345 Kv Transmission Line Lightning Strike | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000333/LER-2007-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000254/LER-2007-001 | Quad Cities Nuclear Power Station Unit 1 05000254 1 of 3 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000389/LER-2007-001 | S, Reactor Shutdown Due to Unidentified RCS Leakage | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000255/LER-2007-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000369/LER-2007-001 | 369 5McGuire Nuclear Station Unit 1 05000 1 OF5 | | 05000335/LER-2007-001 | Mispositioned Service Air Containment Isolation Valves | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000362/LER-2007-001 | Failure to declare Emergency Diesel Generator Inoperable and enter TS Action | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000353/LER-2007-001 | Scram Discharge Volume Vent and Drain Valves Opened Due To Fuse Removal | 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 | 05000400/LER-2007-001 | Control Rod Shutdown Bank Anomaly Causes Entry into Technical Specification 3.0.3 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000261/LER-2007-001 | Reactor Trip Due to a Loose Wire in the Main Transformer Monitoring Circuitry | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000389/LER-2007-002 | 2B2 Reactor Coolant Pump (RCP) Seal Housing Leakage | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000255/LER-2007-002 | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000395/LER-2007-002 | Failure to Follow Administrative Controls Results in LCO 3.6.4 Violation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000306/LER-2007-002 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000440/LER-2007-002 | Shutdown Cooling Pump Trip Results in Operation Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | 05000414/LER-2007-002 | Technical Specification Violation Associated with Containment Valve Injection Water System | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000416/LER-2007-002 | Reactor SCRAM due to Turbine Trip caused by Loss of Condenser Vacuum | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000423/LER-2007-002 | Loss of Offsite Power Caused by Transmission System Operator While Defueled | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000311/LER-2007-002 | RReactor Trip Due to a Breach in the Condensate System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000369/LER-2007-002 | | | 05000454/LER-2007-002 | Technical Specification Required Shutdown of Unit 1 and Unit 2 Due to an Ultimate Heat Sink Pipe Leak Common to Both Units | | 05000282/LER-2007-002 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000315/LER-2007-002 | Failure to Declare Essential Service Water Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000247/LER-2007-002 | Technical Specification Prohibited Condition Due to Exceeding Containment Air Temperature Limit Allowed Outage Time as a Result of Changes in Instrument Uncertainty | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000250/LER-2007-002 | Completion of Shutdown Required by Technical Specifications due to Inoperable Rod Position Indication for Two Control Rods in the Same Control Bank | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000353/LER-2007-002 | Automatic Actuation of Main Condenser Low Vacuum Isolation Logic During Refueling Outage | 10 CFR 50.73(a)(2)(iv), System Actuation | 05000272/LER-2007-002 | MManual Reactor Trips Due to Degraded Condenser Heat Removal | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
|