1-4-2007 | Unit Status: (Refueling) at 0% At the time of the event, Unit 1 was in Mode 6 power, and Unit.2 in Mode 1 (Power Operation) at 100% power.
Event Description: On April 15, 2007, while Unit 1 was in Mode 6, core alterations occurred with only one of the two required source range neutron flux monitors operable. Operators were unaware that only one of the source range neutron flux monitors was able to generate an audible high flux at shutdown alarm. The requirement for two source range neutron flux monitors to provide visual count rate indication was met during this period. This event, which constitutes an operation prohibited by Technical Specifications, was determined to be of no significance to the health and safety of the public.
Event Cause: The cause of this event was the failure to ensure that the operability requirements of the Gamma-Metrics shutdown monitors were adequately captured in the applicable surveillances and operating procedures when these monitors were credited in Technical Specifications as redundant monitors.
Corrective Actions: Revise applicable procedures with the appropriate operability requirements including the function of the Gamma-Metrics shutdown monitor alarm switch, and place a warning label near each Gamma-Metrics shutdown monitor alarm switch on both Units. . |
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LER-2007-003, Inoperable Source Range Neutron Flux Monitors during Mode 6 and Core Alterations.Docket Number |
Event date: |
04-15-2007 |
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Report date: |
1-4-2007 |
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3692007003R00 - NRC Website |
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BACKGROUND
Applicable Energy Industry Identification (EIIS) system and component codes are enclosed within brackets. McGuire unique system and component identifiers are contained within parentheses.
Nuclear Instrumentation System [IG] (ENB):
The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS)[IG](ENB) and the Wide Range Neutron Flux Monitoring System (Gamma-Metrics). These detectors monitor neutrons leaking from the core. The NIS source range channels are boron tri- fluoride (BF3) detectors while the Gamma-Metrics shutdown monitors are fission chambers. These instruments provide continuous visible count rate indication in the control room and an audible high flux alarm in the control room to alert operators to a possible dilution event.
Although not required for operability, the NIS source range channels, N31 and N32, also provide audible indication of count rate in the control room and upper containment near the refueling bridge.
The Gamma-Metrics shutdown monitors were installed by modification in 1994 for additional indication and alarm capability. The Technical.
Specification Bases was also revised in 1994 to allow crediting the Gamma-Metrics as redundant monitors for Operability purposes.
McGuire Technical Specification (TS) 3.9.3 Nuclear Instrumentation:
TS 3.9.3 requires that two source range neutron flux monitors shall be Operable in Mode 6 to ensure redundancy. The two required source range neutron flux monitors may consist of a combination of NIS source range channels and Gamma-Metrics shutdown monitors. For an instrument to be Operable, it must provide a continuous visible count rate indication in the control room and an audible high flux control room alarm.
Per TS 3.9.3 Condition A, with only one required source range neutron flux monitor operable, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, core alterations and introduction of coolant into the reactor coolant system with boron concentration less than required to meet the minimum boron concentration must be suspended immediately.
BACKGROUND (continued) On September 21, 2005, while Unit 1 was in Mode 6, all source range neutron monitors became inoperable when annunciator alarm circuitry failed.
Subsequently, on September 22, 2005 core alteration activities commenced with these monitors inoperable. The inability of the required source range monitors to generate an audible high flux at shutdown alarm was not discovered until September 23, 2005. All other control room source range neutron flux indications were functioning properly during this period.
This activity represented an operation prohibited by McGuire's Technical Specifications.
The causes of this event were attributed to an inadequate Operator Aid Computer (OAC) alarm response procedure, and the common alarm circuitry of the high flux at shutdown alarm.
EVENT DESCRIPTION
At the time of this event, Unit 1 was in Mode 6, refueling operations, and Unit 2 was in Mode 1 at 100% power.
On March 23, 2007, Unit 1 core unload commenced.
During core unload, as directed by the Internal Transfer Development procedure, PT/0/A/4150/048, both Gamma-Metrics shutdown monitor's alarm switches were placed in "BYPASS" when the respective neutron flux count rate decreased to below 0.2 counts per second (cps) after the fuel assembly had been removed from in front of the monitor. This is necessary to preclude nuisance alarms in the control room from low count rate or background noise.
At this time, both NIS source range channels were Operable.
On March 25, 2007, Unit 1 core unload was completed.
On April 15, 2007, Unit 1 core reload commenced with both Gamma-Metrics shutdown monitor's alarm switches still in "BYPASS." At this time, both NIS source range channels were Operable.
During core reload, as directed by PT/0/A/4150/048 and OP/1/A/6100/SU-2, both Gamma-Metrics shutdown monitor's alarm switches are placed in "NORMAL" when the respective neutron flux count rate increases to above 0.2 cps after a fuel assembly has been placed in front of the monitor.
When the initial fuel assemblies were loaded in the core, the neutron flux count rate was lower than needed to restore the Gamma-Metrics shutdown monitor's alarm switch to "NORMAL," therefore, the switches remained in "BYPASS.
Also following placement of the initial fuel assemblies, it is necessary to adjust the high flux at shutdown alarm setpoint for each NIS source range channel. During this setpoint adjustment, the channel becomes Inoperable.
At 1226 on April 15, 2007, NIS source range channel N32 was logged Inoperable to adjust the high flux at shutdown alarm setpoint. With both Gamma-Metrics shutdown monitor's alarm switches in "BYPASS," this left only NIS source range channel N31 as fully'Operable.
Core reload continued.
At 1252, NIS source range channel N32 high flux at shutdown alarm setpoint adjustment was complete and restored to Operable status.
At 1312, NIS source range channel N31 was logged Inoperable to adjust the high flux at shutdown alarm setpoint. With both Gamma-Metrics shutdown monitor's alarm switches in "BYPASS," this left only NIS source range channel N32 as fully Operable.
Core reload continued.
At .1315, core reload was suspended when a tornado watch was issued for the area around McGuire.
At 1358, NIS source range channel N31 high flux at shutdown alarm setpoint adjustment was complete and restored to Operable status.
Around this time, Engineering noticed that both Gamma-Metrics shutdown monitor's alarm switches were in "BYPASS." Engineering informed Operations that this had rendered the Gamma-Metrics shutdown monitors Inoperable.
Given that the Required Actions and Completion Times of Condition A of TS 3.9.3 were not satisfied during the NIS source range channel alarm setpoint adjustments, this event represented a condition prohibited by plant Technical Specifications reportable per the requirements of 10 CFR 50.73 (a)(2)(i)(B).
CAUSAL FACTORS
The cause of this event was the failure to ensure that the operability requirements of the Gamma-Metrics shutdown monitors were adequately captured in the applicable surveillances and operating procedures when these monitors were credited in Technical Specifications as redundant source range neutron flux monitors in 1994.
CORRECTIVE ACTIONS
Immediate:
1. The requirement to log a Gamma-Metrics shutdown monitor as Inoperable if its alarm switch is in "BYPASS" in Mode 6 was added to the control room Operator's turnover log.
Subsequent:
1. Lessons learned communication was sent to all control room Operators.
2. Information stickers were placed on the Gamma-Metrics shutdown monitor alarm switches for both Units informing the Operators that placing this switch in "BYPASS" renders the associated monitor Inoperable per TS 3.9.3.
Planned:
1.Revise the Semi-Daily Surveillance Items Checklist, PT/1&2/A/4600/003 A, clarifying the TS 3.9.3 Operability requirements including the function of the Gamma-Mettics shutdown monitor alarm switch.
2.Revise the Total Core Reloading procedure, PT/0/A/4150/033, and the Internal Transfer Development procedure, PT/0/A/4150/048, to ensure the Gamma-Metrics shutdown monitor alarm switch is placed in "NORMAL" prior to Core Alterations when crediting Gamma-Metrics shutdown monitor Operability.
3.Revise the Refueling and Replacing Reactor Vessel Head procedure, OP/1&2/A/6100/SU-2, to ensure the Gamma-Metrics shutdown monitor alarm switch is placed in "NORMAL" prior to Core Alterations when crediting 'Gamma-Metrics shutdown monitor Operability.
4.Revise the computer based Technical Specification Action Item Log (TSAIL) by adding a comment that if a Gamma-Metrics shutdown monitor is being credited for Operability, its alarm switch must be placed in "NORMAL.
5.Place a permanent label on the Gamma-Metrics shutdown monitor alarm switches for both Units informing the Operators that placing this switch in "BYPASS" renders the associated monitor Inoperable per TS 3.9.3.
SAFETY ANALYSIS
The source range neutron flux monitors provide a signal to alert the Operators to unexpected changes in core reactivity such as a boron dilution accident or an improperly loaded fuel assembly.
At the time of this event, one NIS source range channel was fully operable with visible count rate indication, an audible high flux at shutdown alarm in the control room, and audible indication of count rate in the control room and upper containment. In addition, both Gamma-Metrics shutdown monitors were providing visible count rate indication. Also, Reactor Engineering was regularly monitoring and recording the neutron count rate during the entire core reloading process.
During this event, the boron concentration in the Reactor Coolant System was verified to be within the Core Operating Limit Report (COLR) limits. Also during this event, all sources of unborated water that are connected to the Reactor Coolant System were secured closed to ensure the required boron concentration stated in the COLR would not be violated. Together these controls prevent a dilution event and are required by Technical Specifications.
In conclusion, the overall safety significance of this event was determined to be minimal and there was no impact on the health and safety of the public.
ADDITIONAL INFORMATION
A six year search of the McGuire corrective action database (PIP) and LER database revealed one (1) similar event. Therefore, this event is considered to be recurring. Since the position of the Gamma-Metrics shutdown monitor alarm switches were not relevant to the 2005 LER (see below), they were not addressed at that time.
1. LER 369/2005-05 (PIP M-05-04437) On September 21, 2005, while Unit 1 was in Mode 6, all source range neutron monitors became inoperable when annunciator alarm circuitry failed.
Subsequently, on September 22, 2005 core alteration activities commenced with these monitors inoperable. The inability of the required source range monitors to generate an audible high flux at shutdown alarm was not discovered until September 23, 2005. All other Control room source range neutron flux indications were functioning properly during this period.
This activity represented an operation prohibited by McGuire's Technical Specifications.
The causes of this event were attributed to an inadequate Operator Aid Computer (OAC) alarm response procedure, and the common alarm circuitry of the high flux at shutdown alarm.
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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 |
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