05-23-2012 | On March 28, 2012, Callaway Plant personnel discovered a condition in which one train of the containment cooling system operating in 'fast speed' could be tripped by thermal overload protection under certain accident conditions. In this condition, the tripped containment cooling fans could not be automatically restarted by the Load Shedding and Emergency Load Sequencing system.
This condition was previously discovered and reported as Callaway Plant LER 2008-001. After that discovery, Modification MP 08-0013 was implemented to correct this condition. However, on March 16, 2012, MP 08-0013 was inadvertently uninstalled on the 'B' train containment coolers during implementation of a different modification on the same control circuit.
Causes of this event are associated with ineffective communication between the job planner and design engineer, modification implementation work planned beyond the approved scope of the modification, inadequate evaluation of interaction between plant modifications, and inadequate review of the work instructions.
Corrective actions for this event include requiring Field Change Notice initiation when design-related issues are identified, providing training to Callaway Plant staff, and implementing procedure revisions and new checklists to add and strengthen reviews of modifications and work instructions. |
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1. DESCRIPTION OF STRUCTURE(S), SYSTEM(S) AND COMPONENT(S)
At Callaway Plant, the containment cooling system provides a means of cooling the containment atmosphere following a postulated loss-of-coolant accident (LOCA) or main steam line break (MSLB) inside containment. This cooling function reduces containment pressure and temperature following a postulated accident, thereby reducing the potential for leakage of airborne and gaseous radioactivity to the environment and maintaining suitable environmental conditions for the equipment inside the containment building.
The containment cooling system consists of two independent trains of containment coolers. Two containment coolers are provided for each train of containment cooling. One containment cooler consists primarily of a cooling coil and fan. The containment cooling fans can be run in either fast speed or slow speed during normal plant operation to maintain containment pressure and temperature within required operating limits. However, upon receipt of an actuation signal following a LOCA or MSLB in containment, the fans are designed to automatically start or restart in slow speed for their accident mitigation function.
Another relevant feature of the containment coolers is that the fan motors are equipped with thermal overload protection to prevent motor damage. Separate overload devices are provided for slow and fast speed operation.
Subsequent to a thermal overload protective trip, operator action is required to reset the trip before the cooler can be restarted.
2. INITIAL PLANT CONDITIONS
This condition was identified when the plant was in Mode 1, "Power Operation.
3. EVENT DESCRIPTION
On March 28, 2012, Callaway Plant personnel were installing new relays in the 'A' train containment cooler breaker cubicles per Modification MP 01-1010. During the installation process, personnel discovered that the work instructions for MP 01-1010 directed the removal of a previous wiring change that had been made under Modification MP 08-0013. Removal of the MP 08-0013 wiring changes was not authorized under MP 01-1010.
Following the discovery of this condition, the 'A' train containment cooler circuit was restored to the configuration it was in prior to the start of MP 01-1010 implementation. Later that day, however, Callaway Plant staff discovered that the installation of MP 01-1010 had already removed the MP 08-0013 wiring change from the 'B' train containment cooling circuits on March 16, 2012.
When installed, modification MP 08-0013 corrected a condition in which containment cooling fans in 'fast speed' operation could be tripped by thermal overload protection under certain accident conditions prior to being shed.
In this scenario, the tripped cooling fans would not be automatically restarted by the Load Shedding and Emergency Load Sequencing (LSELS) system. Thus, without MP 08-0013 installed and the containment cooling fans in fast speed operation, the containment cooling system may not have been capable of performing its specified safety function under some postulated accident scenarios.
When plant staff discovered that MP 08-0013 had been inadvertently removed from the 'B' containment cooler circuit, the 'B' containment cooling fans were switched from 'fast speed' to 'slow speed' operation to prevent the condition from potentially adversely affecting the 'B' containment coolers until the wiring changes of MP 08 0013 could be reinstalled.
4. ASSESSMENT OF SAFETY CONSEQUENCES
The containment coolers are credited in the safety analysis to remove sufficient energy to maintain peak containment pressure and temperature below design limits. To be considered operable, a single train must be capable of removing 141.4 MBTU per hour under post-accident conditions. During a design basis accident, only one train of coolers is assumed to operate.
Due to the inadvertent removal of the MP 08-0013 wiring changes, the 'B' train containment coolers may not have been able to perform their specified safety function. Without the heat removal capacity of the tripped coolers, post-accident peak containment temperatures and pressures would be impacted.
To evaluate this impact, a sensitivity analysis was performed on the LOCA and MSLB cases that are applicable to this condition. The results of this analysis demonstrated that, even without the availability of the containment coolers, the calculated post-accident temperatures and pressures would not have exceeded the limits in the analysis of record. Therefore, this condition did not significantly degrade plant safety.
This condition is considered to have low safety significance.
5. REPORTING REQUIREMENTS
As a result of the removal of modification MP 08-0013 described in this LER, operability of the 'B' train containment coolers cannot be supported from 0938 on March 16, 2012 through 1511 on March 28, 2012. This corresponds to a period of 12 days, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, 33 minutes.
The Callaway Plant Technical Specification (TS) applicable to this event is TS 3.6.6, Containment Spray and Cooling Systems. TS 3.6.6 Required Action C.1 requires an inoperable containment cooling train to be restored to service within 7 days. If this Completion Time is not met, TS 3.6.6 Required Action D.1 requires Mode 3 entry within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Because the period of 'B' train containment cooling inoperability exceeded the Mode 3 entry requirement of TS 3.6.6, this condition is considered reportable per 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specification 3.6.6.
Additionally, during the time that the 'B' train containment coolers were affected by this condition, the 'A' train containment coolers were twice removed from service. 'A' train maintenance and the 'B' train degraded condition described herein overlapped during the following periods:
0505 on 2012.03.27 - 0256 on 2012.03.28; 0756 on 2012.03.28 - 1511 on 2012.03.28.
This results in a combined period of 1 day, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, and 6 minutes of concurrent inoperability of both trains of containment cooling.
The containment cooling system meets the definition of a system required to mitigate the consequences of an accident as specified by 10 CFR 50.73(a)(2)(v) criterion D. Containment cooling system function was lost during the two periods specified above. Thus, this condition is considered reportable per 10 CFR 50.73(a)(2)(v)(D) as a condition that could have prevented fulfillment of a safety function required to mitigate the consequences of an accident.
6. CAUSE OF THE EVENT
The direct cause for the event was a misunderstanding of the intended scope of MP 01-1010. This misunderstanding of scope occurred because common areas of the same drawings were affected by more than one design modification and also because the designs of MP 08-0013 and MP 01-1010 did not adequately interface with each other.
The causes of this event identified in the root cause evaluation are as follows:
- Ineffective communication between the job planner and design engineer led to misunderstanding of the scope of MP 01-1010 and the associated design modification package drawings.
- The job planner believed he understood the scope of the design modification and planned beyond the scope of the approved modification.
- The design modification process requirements for evaluating the interaction with other plant changes were inadequate.
- The construction supervisor's review of the work instructions was inadequate.
7. CORRECTIVE ACTIONS
As stated in Section 3, following discovery of the wiring discrepancy, immediate corrective action was taken to back out of the implementation of MP 01-1010 on the 'A' train containment coolers, thus restoring the containment coolers to service with MP 08-0013 in place. Additionally, the 'B' train containment coolers were placed in slow speed, thereby preventing this condition from adversely affecting the automatic slow-speed restart function of the containment coolers.
On April 12, 2012, the control circuitry of the 'B' train containment coolers was restored to its correct configuration, incorporating MP 08-0013 and MP 01-1010 as intended.
Corrective actions taken to address the causes listed in Section 6 include, but are not limited to, the following:
- Plant procedures will be revised to require initiation of a Field Change Notice (FCN) when a design related issue is identified during the modification planning process (rather than relying on the less rigorous routing process). As a result, the FCN will facilitate full disposition of any discovered issues and will also provide an independent engineering review as required by the FCN process.
- Plant procedures and planning guidance will be revised to require a signed qualified review of all Level 1 and Level 2 use work instructions. Thus, work instructions for modifications such as MP 01-1010 will receive additional peer review.
- Plant procedures will be revised to lower the threshold that triggers review of work instructions. Thus, review will be required for work instructions of lesser complexity or criticality, such as the work instructions for MP 01-1010.
- A comprehensive checklist will be created for the review of work instructions. This checklist will define review criteria, including the boundaries of the design modification. The use of this checklist will ensure that the critical aspects of the work instructions are reviewed.
- Engineering design guidance will be modified to require a documented review of other plant changes relevant to the modification being designed. This requirement will add accountability for engineers to ensure that their modifications are compatible with other ongoing plant changes.
8. PREVIOUS SIMILAR EVENTS
With respect to the containment cooling system, Callaway Plant submitted LER 2008-001 to report this condition when it was initially discovered in 2008. From LER 2008-001:
Previous occurrences of the containment coolers tripping during fast-speed operation were documented during the Startup Test Program at Callaway in 1983. Actions taken to address the tripping included replacement of the thermal overloads with higher ratings and changes to the control circuitry for the coolers.
A trip of one of the coolers occurred in 1986, and as corrective action for that event, new overloads with trip times in the longer portion of their allowable range were installed. Shortly after that, in 1987, a precaution was added to the operating procedure regarding fast-speed operation of the coolers during conditions of high containment pressure and low cooling water temperature, noting that operation under such conditions may cause the coolers to operate near the thermal overload setpoint(s). No further occurrences were documented until the trip of the "A" cooler on March 26, 2008.
With respect to the modification process, the root cause evaluation for this event did not identify previous internal events that resulted from the same root cause, failure, or sequence of events as the event described herein.
9. OTHER INFORMATION
The Energy Industry Identification System (EllS) identifiers for the components and systems mentioned in this report are as follows:
System: BK, Containment Fan Cooling System Components: FAN, Fan; 49, Thermal Relay
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05000413/LER-2012-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000327/LER-2012-001 | Unanalyzed Condition Affecting Essential Raw Cooling Water System due to External Flooding | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000388/LER-2012-001 | Two Control Room Floor Cooling Systems Inoperable | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000395/LER-2012-001 | Vice President, Nuclear Operations 803.345.4342 August 3, 2012SCE~r .so A SCANA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission
Washington, DC 20555
Dear Sir / Madam: Subject:VVIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSEE EVENT REPORT (LER 2012-001-01) CORE EXIT THERMOCOUPLES & REACTOR WATER LEVEL INDICATION SYSTEM INOPERABLE DUE TO AN INADEQUATE MAINTENANCE PROCEDURE Attached is Licensee Event Report (LER) No. 2012-001-01 for the Virgil C. Summer Nuclear Station Unit 1. This revised report describes a condition where Core Exit Thermocouples and Reactor Water Level Indication System would not be operable for accident monitoring. This report is submitted in accordance with 10 CFR 50.73(a)(2)(i)(B). This letter and attached LER contain no new commitments and no revisions to existing
commitments.
Should you have any questions, please call Bruce Thompson at (803) 931-5042. Very truly yours, Dal Thomas D. Gatlin TS/TDG/jw
Attachment
c: K. B. Marsh P. Ledbetter S. A. Byrne J. C. Mellette J. B. Archie EPIX Coordinator N. S. Carps K. M. Sutton J. H. Hamilton INPO Records Center R. J. White Marsh USA, Inc. W. M. Cherry R. J. Schwartz V. M. McCree NSRC R. E. Martin RTS (CR-11-01807) NRC Resident Inspector FileV(818.07) M. N. Browne PRSF (RC-12-0116) V fALVirgil C. Summer Station • Post Office Box 88 .Jenkinsville, SC • 29065 • F (803) 345-5209 1 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010) Estimated burden per response to comply with this mandatory collection request: 80 hours.0Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA/Privacy Section (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet e-mail to infocollects.resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management andLICENSEE EVENT REPORT (LER) 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 Virgil C. Summer Nuclear Station Unit 1 05000 395 1 OF 5 4. TITLE Core Exit Thermocouples & Reactor Water Level Indication System Inoperable due to Inadequate Maintenance Procedure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000397/LER-2012-001 | DG-3 Inoperable for Longer than Allowed by TS Due to Failed Governor 05000 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000410/LER-2012-001 | Forced Shutdown Due to an Increase in Drywell Leakage in Excess of Technical Specifications Limit | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000289/LER-2012-001 | Single Condition Making Independent Trains Inoperable | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | 05000286/LER-2012-001 | Common Cause Inoperability of Both Trains of Motor Driven Auxiliary Feedwater (AFW) Pumps Due to Inability to Control AFW Regulating Valves After Isolation of Nitrogen Backup | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | 05000265/LER-2012-001 | Main Steam Isolation Valve Local Leak Rate Test Exceeds Technical Specifications Limit | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000456/LER-2012-001 | Two Main Steam Safety Valves Failed Pre-outage Setpoint Testing Due to Abnormal Spring Geometry | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000261/LER-2012-001 | Technical Specification Required Plant Shutdown Due to Missed Surveillance and Operation Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000483/LER-2012-001 | Modification Implementation Error Adversely Impacted the Containment Cooling System | 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000250/LER-2012-001 | Containment Concrete Thickness At Spalled Patch Does Not Meet Technical Specification Design Value | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000414/LER-2012-001 | Carolinas Duke Energy Carolinas, LLC 4800 Concord Rd. York, SC 29745 803-701-4251 December 20, 2012 U.S. Nuclear Regulatory Commission
Attention: Document Control Desk
Washington, D.C. 20555
Subject:�Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Units 1 and 2
Docket Nos. 50-413 and 50-414
Licensee Event Report 414/2012-001
Pursuant to 10 CFR 50.73(a)(1) and (d), attached is Licensee Event Report 414/2012-001,
Revision 0 entitled, "Diesel Generator (DG) 2B Was Unknowingly inoperable from 09/28/12 to
10/23/12 Due to Failed Tachometer Relay Power Supply".
This report is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B), 10 CFR
50.73(a)(2)(ii)(B), and 10 CFR 50.73(a)(2)(v)(A)-(D).
There are no regulatory commitments contained in this letter or its attachment. This event is considered to be of no significance with respect to the health and safety of the
public.
If there are any questions on this report, please contact L.J. Rudy at (803) 701-3084. Kelvin Henderson LJR/s Attachment www. duke-energy. corn Document Control Desk Page 2 December 20, 2012 xc (with attachment): V.M. McCree Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J.H. Thompson (addressee only) NRC Project Manager U.S. Nuclear Regulatory Commission Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto, III NRC Senior Resident Inspector Catawba Nuclear Station INPO Records Center 700 Galleria Place Atlanta, GA 30339-5957 Document Control Desk Page 3 December 20, 2012 bxc (electronic copy)(with attachment): INPO L.E. Harmon C.S. Kamilaris R.D. Hart G.Y. Helton S.F. Hatley (ICES) M.K. Green R.T. Simril, Jr. B.C. Carroll M.C. Nolan W.J. Pritchett, Jr. T.L. Patterson K.R. Alter H.D. Brewer R.E. Abbott, Jr. B.J. Horsley S.L. Western bxc (hard copy)(with attachment): D.B. Alexander L.S. Nichols L.J. Rudy ELL Master File CN-801.01 LER File RGC Date File NCMPA-1 NCEMC PMPA ICES Lee.Harmon@NRC.gov NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013
(10-2010) Estimated burden per response to comply with this mandatory collection request: 80 hours. Reported
lessons learned are incorporated into the licensing process and fed back to industry. Send commentsLICENSEE EVENT REPORT (LER) regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects.resource@nrclov, 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(See reverse for required number of to impose an information collection does not display a currently valid OMB control number, the NRCdigits/characters for each block) may not conduct or sponsor, and a person is not required to respond to, the information collection. r1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE Catawba Nuclear Station, Unit 2 05000414 10OF •4. TITLE Diesel Generator (DG) 2B Was Unknowingly Inoperable from 09/28/12 to 10/23/12 Due to Failed Tachometer
Relay Power Supply | 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000247/LER-2012-001 | Technical Specification (TS) Prohibited Condition Caused by an Inoperable 23 Emergency Diesel Generator Fuel Oil Storage Tank Due to Fuel Oil Below TS Limit | 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-2012-001 | Unanalyzed Conditions Exist for Standby Shutdown Facility Mitizated Events | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000445/LER-2012-002 | COMANCHE PEAK 05000445 10OF06 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000413/LER-2012-002 | Discovery of Inadequacy in Surveillance Testing of Solid State Protection System | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000261/LER-2012-002 | Unplanned LCO 3.5.4 Entry Due to RWST alignment to Purification | 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 | 05000410/LER-2012-002 | Loss of Isolation Function on RHR Shutdown Cooling Suction Line due to Breaker Trip | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000482/LER-2012-002 | . One Train of Automatic Safety Infection Blocked During Entry Into Mode 3 Due To Procedural Weakness | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000361/LER-2012-002 | Emergency Diesel Generator Vibration Trip Not Bypassed For Non-Accident Condition | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000346/LER-2012-002 | Leak from Reactor Coolant Pump Seal Piping Socket Weld due to High Cycle Fatigue | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000333/LER-2012-002 | High Pressure Coolant Injection Pressure Control Valve 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)(i)(B), Prohibited by Technical Specifications | 05000306/LER-2012-002 | Unit 2 Emergency Diesel Generators Inoperable Due To Missing Flood Control Barrier Seal | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000250/LER-2012-002 | Non-compliance with TS 3.4.9.3 due to Manual Isolation Valve Found in Incorrect TS Configuration | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | 05000278/LER-2012-002 | Failure of Primary Containment Isolation Valve due to Foreign Material Results in Condition Prohibited by TS | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000316/LER-2012-002 | Unit 2 Reactor Trip from Generator Trip Due to Incorrect Relay Setting | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2012-002 | Unplanned Actuation of 121 Motor Driven Cooling Water Pump | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000298/LER-2012-002 | Improper Rotor Installation Causes Failure of Diesel Generator to Start | 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-2012-002 | Technical Specification (TS) Prohibited Condition Caused by New Fuel Assemblies Stored in a Configuration Prohibited by the TS | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000237/LER-2012-002 | Inlet Steam Drain Pot Drain Line Leaks Result in HPCI Inoperabilities | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000298/LER-2012-003 | Reactor Building Doors Opened Simultaneously Causes Loss of Safety Function | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000410/LER-2012-003 | Suppression Pool Level Below Technical Specification Limit During Mode Change | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000261/LER-2012-003 | Plant Modification Interfered with the Operation of Containment Wide Range Level Indicator | | 05000298/LER-2012-004 | Cooper Nuclear Station 05000298 1 of 4 | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | 05000410/LER-2012-004 | Manual Reactor Scram due to a Loss of Main Turbine Gland Sealing Steam Resulting in Lowering Condenser Vacuum | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000382/LER-2012-004 | Essential Chiller Oil Leak Creates Unanalyzed Past Operability Condition | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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 | 05000265/LER-2012-004 | Drywell Radiation Monitor Failed Downscale | | 05000261/LER-2012-004 | Reactor Tripped Due to a Turbine Trip Caused by a Feedwater Isolation Signal from Steam Generator 'B' High Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000454/LER-2012-004 | Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Repair Surface Indications | | 05000254/LER-2012-004 | Breech in Secondary Containment | | 05000482/LER-2012-004 | Two Charging Pumps Capable of Injecting into the RCS Due to Inadequate Definition of Centrifugal Charging Pump in LCO 3.4.12 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000410/LER-2012-005 | Automatic Diesel Actuation Due to the Loss of a 115 kV Offsite Power Source | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000298/LER-2012-005 | Cooper Nuclear Station 05000298 1 of 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000298/LER-2012-006 | Missing Vent Plug Results in Technical Specifications Prohibited Condition | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000220/LER-2012-007 | High Pressure Coolant Injection System Logic Actuation Following an Automatic Turbine Trip Signal Due to High Reactor Water Level | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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