02-08-2013 | On December. 12, 2012, at approximately 1914 Eastern Standard Time, Sequoyah Nuclear Plant determined that Unit 1 and Unit 2 were at risk of external flooding inundating the Essential Raw Cooling Water ( ERCW) Pumping Station through inadequate electrical conduit penetration seals entering the ERCW Pumping Station. This condition could allow flood waters to enter the ERCW Pumping Station at a rate greater than the installed sump pump capacity creating a condition that could result in the ERCW system being unavailable to perform its design function during a flood event above plant grade. No actual flooding condition occurred or currently exists. This condition has no impact on ERCW system, operability during any non-flooding event.
The root cause evaluation determined that existing documentation including licensing documents and configuration controlled drawings for the ERCW Pumping Station do not contain sufficient information to identify the design basis flood barriers.
Compensatory measures are currently in place and permanent modification of inadequate conduit seals are scheduled for repair per design requirements. |
---|
LER-2012-001, Unanalyzed Condition Affecting Essential Raw Cooling Water System due to External FloodingDocket Number |
Event date: |
12-12-2012 |
---|
Report date: |
02-08-2013 |
---|
Reporting criterion: |
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition |
---|
3272012001R00 - NRC Website |
|
L PLANT CONDITION(S) At the time of the discovery of the condition, Tennessee Valley Authority (TVA), Sequoyah Nuclear Plant (SQN) Unit 1 was operating at approximately 100 percent rated thermal power (RTP) and SQN Unit 2 was shutdown (defueled).
IL DESCRIPTION OF EVENT
A. Event:
On December 12, 2012, SQN performed an inspection of electrical manway (MNWY) - 33 and confirmed that inadequate electrical conduit penetration seals (approximately elevation 686 feet) provided an in-leakage path into the Essential Raw Cooling Water (ERCW) [EMS Code Kl] Pumping Station. The condition was previously evaluated as a degraded non-conforming condition, as determined by a Functional Evaluation (FE). It was previously considered based on review of the drawings for the MNWY 33 electrical conduit runs that the conduit penetrations were sealed. Since this was not the case, SQN concluded that the as-found condition was reportable because SQN was operating outside of the current licensing basis as a result of the ERCW Pumping Station not being able to remain dry during a flood event above plant grade (elevation 705.0 feet). The December 12, 2012 discovery date for 10 CFR 50.72 and 50.73 reporting is based on this recognition of the safety significance of the issue.
The condition did not result in any immediate structure, system, or component (SSC) inoperability. The Fukushima Dai-ichi Near-Term-Task-Force (NTTF) flooding walkdown efforts encompassed the extent of condition for identifying configurations that could bypass external flood protection features. The inadequate electrical conduit penetration seals have been identified and are scheduled for permanent repair.
On December 12, 2012, at 1914 Eastern Standard Time, NRC was notified, in accordance with 10 CFR Part 50.72(b)(3)(ii)(B), for a condition that places both units in an unanalyzed condition that significantly degrades plant safety and 50.72(b)(3)(v)(A), for a condition that could prevent the fulfillment of the safety related function of the ERCW system needed to shutdown the reactor.
B. Inoperable Structures, Components, or Systems that Contributed to the Event None C. Dates of Major Occurrences:
1971 The initial design criteria for electrical cables in the MNVVYs penetrating into the ERCW Pumping Station included a testing requirement to fill the MNWYs with water and be pressurized. To perform the test, each of the MNWY covers needed to be watertight.
April 26, 1974 The 1971 design criterion for electrical cables leading to the ERCW Pumping Station was revised to remove the initial testing requirement. The revised design change stated the ERCW Pumping Station will remain dry during a flood but, did not identify flood barriers or provide details to maintain the ERCW Pumping Station dry.
January 24, 1978 As-Constructed drawings of ERCW Pumping Station were issued. However, the documentation neither provided clear information about ERCW Pumping Station design basis flood (DBF) boundaries nor provided reference that validated potential flood boundaries were adequate for a DBF. The documentation did show the original plant design had CHICO A, a leak sealing compound, in electrical conduits in MNWY-33 but, no analysis supports CHICO A as a suitable flood barrier.
October 10, 1980 A revision to the conduit and grounding drawings included a reference to generic fire penetration drawings for sealing instructions because of a similar detail for EYS sealing fittings with CHICO A compounds. As a result, a loss of configuration control occurred because the fire protection drawings contained sealing details that did not pertain to flood barriers.
January 15, 1985 A revision to fire protection drawings allowed for use of Dow Corning room temperature vulcanizing (RTV) compound as a substitute for CHICO A in fire stop penetrations. Limited testing of the Dow Corning RTV was performed in 1980 for a different application. There is no documentation supporting adherence to the vendor recommended application of Dow Corning RTV for MNWY-33.
July 11, 1986 A revision to the fire protection drawings included a note to discuss watertight conduit and penetration seals. Testing performed using the Dow Corning RTV in blank electrical conduits was performed but, does not provide satisfactory results for use as a watertight seal (it leaked).
June 17, 1991 SQN implemented a design modification to remove the MNWY watertight cover and install dipstick holes to determine if the MNWY had flooded. Since no requirements for periodic leak testing were identified, and it was presumed that the watertight cover seals no longer performed a function, the MNWY cover seals were removed. This left the electrical conduit seals as the only barrier against a flood above plant grade.
July 7, 1995 A design modification for electrical conduits allowed the use of 'C' condulet with RTV in place of the EYS sealing fittings with RTV. The design modification did not contain sufficient detail for DBF considerations.
August 13, 2002 An administrative change to the conduit and grounding drawing denoted that EYS sealing fitting were not required and 'C' condulet could be substituted for electrical conduits.
September 16, 2012 The NTTF walkdown identified a potential leak path into the ERCW Pumping Station via electrical conduits.
November 15, 2012 An FE was conducted for the potential leak path into the ERCW Pumping Station via electrical conduits.
November 19, 2012 A temporary modification to install sump pumps into the ERCW Pumping Station is performed.
December 3, 2012 A design modification to insert conduit seals in MNWY-33 electrical conduits is developed for implementation.
December 12, 2012 The steel MNWY cover and concrete missile shield at MNWY-33 is removed for inspection and documentation of as found conditions. Upon inspection of MNWY-33, TVA determined that SQN Units 1 and 2 were at risk of flooding into the ERCW Pumping Station during a flood above plant grade as a result of electrical conduit penetration seals not being filled with material required to make the ERCW Pumping Station watertight. Subsequently, an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification was made to the NRC.
December 15, 2012 The temporary modification for the ERCW Pumping Station is revised to add larger capacity sump pumps based on a revision to the in-leakage calculation. The installation of the sump pumps was completed.
January 4, 2013 The FE for potential leak path into the ERCW Pumping Station via electrical conduits is revised as a result of the as found inspection results.
D. Other Systems or Secondary Functions Affected:
No other systems or secondary functions were affected by this event.
Method of Discovery: E.
The condition of potential water in-leakage into the ERCW was identified by TVA during the NTTF walkdown.
F. Operator Actions:
Operations issued a Standing Order that provides guidance for operation of the ERCW temporary sump pumps upon meeting entry conditions for Abnormal Operating Procedure (AOP)-N.03, External Flooding.
G. Safety System Responses:
No safety systems activation occurred.
CAUSE OF THE EVENT
A. Root Cause:
- The root cause analysis determined that existing documentation including licensing documents and configuration controlled drawings for the ERCW Pumping Station do not contain sufficient information to identify flood barriers. SQN design criteria for Flood Protection, states that the ERCW Pumping Station shall remain dry, but does not clearly identify what is credited as flood barriers. Further, configuration controlled drawings do not indicate that the conduit and penetration seals are performing the function of a flood barrier, only that these are watertight.
B. Contributing Factor:
Inadequate configuration control for DBF protection existed as noted by several revisions to configuration controlled drawings which led to an inadequate seal applied to conduits in MNWY-33.
Maintenance practices related to flooding issues were not sensitive to the requirements for maintaining adequate flood barriers during a flooding event.
IV. ANALYSIS OF THE EVENT
The ERCW system is safety related and is designed to supply cooling water to various essential heat loads in both the primary and secondary portions of each unit. Provisions are made to ensure a continuous flow of cooling water to those systems and components necessary for plant safety during either normal operation or under accident conditions; including external flooding events. The ERCW system is designed to continue operation during the
- post-flood condition. The availability of water for the most demanding condition on the ERCW system is based on the following events occurring simultaneously: loss of offsite power, loss of downstream dam, loss of two diesel generator units serving the same power train, and a design basis earthquake.
The ERCW Pumping Station is designed to remain fully functional for floods up to the Probable Maximum Flood (PMF) including wind-wave run-up. The deck elevation (elevation 720 feet) is below the PMF plus wind wave run-up, but is protected from flooding by outside walls. The lower elevations of the ERCW Pumping Station are intended to be watertight. The lower floors of the ERCW Pumping Station are separated into three bays. One bay is for all of the B-train ERCW components. There are two bays for the A-train ERCW components, each has essentially one-half of the required ERCW components.
Based on a review of the supporting documents, it was determined that the electrical conduit penetration seals were meant to be the flood barrier. However, there was no clear identification of the flood barriers and their requirements. The associated maintenance activities on the flood barriers were performed using the fire penetration drawing, which is what the conduit and grounding drawing referenced.
The EYS sealing fittings with CHICO A sealing compound were originally installed in MNWY-33 and they acted as the barrier against flooding, but the lack of documented design basis for flooding barriers since initial construction eventually led to the replacement of some of the EYS sealing fittings with a less than adequate seal. A plant modification will install electrical conduit seals that have been tested to withstand the head pressure that could be exerted during a flood.
V. ASSESSMENT OF SAFETY CONSEQUENCES
Based on the above information, a potential for a reduction in the defense-in- depth to nuclear safety existed. As a result, this event could potentially have adversely affected the health and safety of plant personnel or the general public had an actual flooding event occurred. No flooding event occurred or is pending.
The ERCW Pumping Station is designed to remain fully functional for floods up to the DBF. AOP-N.03, External Flooding, provides the necessary actions to mitigate the effects on plant operations during probable maximum external flood conditions.
Interim measures installed temporary sump pumps in the ERCW Pumping Station to remove excess water in order to keep equipment operable during flooding conditions. The FE calculates both the leak rate into the ERCW Pumping Station and pumping capacity of the temporary sump pumps. The FE determined that one bay of ERCW systems would be inundated based on the existing seals. One of A-train bays (two bays exist) is required for safe shutdown during a DBF. For the time prior to the installation of the temporary pumps, there is no supporting evidence to conclude that the ERCW system could have performed its design function during a flood above plant grade.
In addition to level considerations, plant flood preparations will cope with the "fastest rising" flood which is the calculated flood that can exceed plant grade with the shortest prediction notice. Reservoir levels for large floods in the Tennessee Valley can be predicted well in advance.
A minimum of 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br />, divided into two stages, is provided for safe plant shutdown by use of this prediction capability. Stage I, a minimum of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> long, will commence upon a prediction that flood-producing conditions might develop. Stage II, a minimum of 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> long, will commence on a confirmed estimate that conditions will provide a flood. This two-stage scheme is designed to prevent excessive economic loss in case a potential flood does not fully develop.
The estimated probability is less than 2.6E-3 that a Stage I flood warning will be issued during the 40-year life of the plant. The estimated probability is less than 1.0E-3 that shutdown will need to continue into Stage II during plant life.
Deterministically, the risk of a maximum flooding event is low because of the low probability of a PMF, the ample warning time, the development of the event over an extended period of time, and the additional resources that would be available to perform mitigating actions.
VI. CORRECTIVE ACTIONS
A. Immediate Corrective Actions:
The steel MNWY cover was opened to assess conditions affecting the ERCW Pumping Station was performed. Temporary modification installed sump pumps in ERCW Pumping Station. Installation of qualified conduit seals is in progress.
B. Corrective Actions to Prevent Recurrence:
The following corrective actions to prevent recurrence were identified in the root cause analysis and are being tracked in accordance with the SQN Corrective Action Program.
1. SQN will issue a design basis document that will include, but not limited to, the following: identify SSC's which provide external flooding protection for the Emergency Diesel Generator Building and ERCW Pumping Station, ensure adequacy of identified barriers, design requirements / regulatory and licensing requirements, reference AOP-N.03, reference drawing series and test data, and develop an inspection program for flood barriers.
2. An exterior flood barrier drawing series will be issued to identify the exterior flood boundaries and contain seal details. Associated drawings will be revised as applicable.
VII. ADDITIONAL INFORMATION
A. Failed Components:
None B. Previous LERs on Similar Events:
A review of previous reportable events for the past three years did not identify any similar events.
C. Additional Information:
The corrective action document for this report is Problem Evaluation Report (PER) 655763 (Root Cause Evaluation).
D. Safety System Functional Failure:
The ERCW system would not have been available to perform its function.
E. Unplanned Scram with Complications:
VIII.
This event did not result in an unplanned scram with complications.
COMMITMENTS
None
|
---|
|
|
| | Reporting criterion |
---|
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 |
|