05-22-2009 | Beaver Valley Power Station ( BVPS) Unit 1 commenced the performance of a Recirculation Spray System ( RSS) flow test surveillance on one of the two outside RSS pumps. To perform this test while in Mode 1, the suction and discharge containment isolation valves ( CIVs) on this RSS train of piping were closed (but not de-energized) and the RSS pump piping and casing was filled with water through the pump's casing manual drain valve since the RSS train is normally maintained dry. After successfully running the pump on recirculation flow, it was recognized during the pump draining operation that the CIVs on this RSS train's piping needed to be de-energized in order to maintain containment operability. These CIVs receive an 'open' signal following a containment isolation-Phase B signal, and not the typical 'close' signal. Thus, if a design basis accident was postulated to have occurred when the pump casing's manual valves were open, containment operability would be compromised with the CIVs going open and pressurizing the pump casing. This is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by plant Technical Specifications (TS).
The cause of this event was determined to be less than adequate change management in revising the performance mode of the test without adequate evaluation of the impact on Technical Specification requirements. Narrow focus by procedure preparers, review organizations and end users on the most obvious TS requirement (Recirculation Spray System) resulted in a failure to identify that a more limiting TS requirement (Containment operability) was impacted by the test. This event is considered to have very low safety significance. |
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There were no structures, components, or systems that were inoperable at the start of the event that contributed to the event. Energy Industry Identification System (El IS) codes are identified in the text as [XX].
DESCRIPTION OF EVENT
commenced the performance of a Recirculation Spray System (RSS) flow test, pursuant to Technical Specification Surveillance 3.6.7.2 for one of the two outside RSS pumps [BE].
See the simplified drawing included at the end of this report. This containment spray system is normally maintained in a dry condition during power operation with its suction containment isolation valve (MOV-1RS-155B) and its discharge containment isolation valve (MOV-1RS 156B) open. This surveillance procedure, which previously was normally performed in Modes 5 and 6, was recently revised to allow performance in all modes.
Technical Specification (TS) 3.6.7 requires four RSS subsystems be operable while in Modes 1 through 4. The TS Required Action (restore an inoperable subsystem within 7 days) was entered at the start of the surveillance procedure since the one applicable RSS subsystem was being made inoperable during the surveillance procedure. To perform this test while in Mode 1, the suction and discharge containment isolation valves (CIVs) on this RSS train of piping were closed (but not de-energized) and the RSS 2B pump , piping and casing were filled with water through the pump casing manual drain valve and manual valves connected at the top of the pump casing were opened to provide a vent path. Filling operation was performed for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 11 minutes. Filling operation was suspended until the next day when an additional 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and 27 minutes of filling was performed on 03/27/2009.
After the filling operation was complete, the pump was successfully run on recirculation flow to complete the flow test portion of the surveillance procedure. Water was then drained from the pump and piping by connecting pressurized air to one vent and draining the water out the casing drain line to a local sump. Draining was performed for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 5 minutes through the night.
At 04:18 on 03/28/2009 during the draining operation, the Shift Manager recognized that the CIVs on this RSS train's piping needed to be de-energized while closed since the RSS pump's vent and drain valves were open. These CIVs receive an 'open' signal following a containment isolation-Phase B (CIB) signal during a design basis Loss-of-Coolant-Accident (LOCA), and not the typical 'close' signal. In the configuration with open manual valves on the pump's casing, containment operability would have been compromised if a LOCA were to occur pressurizing containment. Since this RSS train's CIVs (the containment pressure boundary during the surveillance) remained energized, they would have automatically DESCRIPTION OF EVENT (Continued) opened following a CIB signal, and resulted in a path to pressurize the pump's casing. The two CIVs on this RSS piping train were immediately de-energized, removing this portion of the RSS piping from potentially becoming an extension of the containment boundary.
Although the Required Action for TS 3.6.7 for one inoperable RSS subsystem was entered at the start of the surveillance procedure, it was not recognized that TS 3.6.1 for Containment operability was also being entered whenever a normally-closed manual drain/vent valve on the pump's casing was opened by the surveillance procedure while this train's CIVs were energized.
ANALYSIS OF EVENT
The Recirculation Spray System is designed to operate following a design basis LOCA.
The RSS pumps do not immediately start following a LOCA, but start only when sufficient water has been injected into containment to allow an appropriate level of water to accumulate in the containment sump for proper RSS pump operation. The RSS normally-open CIVs receive a signal to automatically open following a containment isolation-Phase B signal. The RSS piping will thus initially experience direct containment pressure following a LOCA, which makes this piping an extension of containment pressure boundary.
TS 3.6.1 requires that Containment shall be operable in Modes 1 through 4. The Bases for TS 3.6.1 states that "All penetrations required to be closed during accident conditions are either 1) capable of being closed by an operable automatic containment isolation system or 2) closed by manual valves, blind flanges, or de-activated automatic valves secured in their closed positions." The RSS pump casing drain/vent penetrations are required to be closed during accident conditions, but were not adequately isolated from containment pressure during this surveillance procedure by appropriate automatic or passive isolation function when the RSS pump drain/vent manual valves were open with the RSS CIV's remaining energized while in Mode 1. TS 3.6.1 Required Action A requires that an inoperable containment be restored with one hour and Required Action B requires the Unit be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> when Completion Time for Required Action A is not met. Thus, non-compliance with TS 3.6.1 occurs when the containment (i.e., penetrations in this case) is inoperable longer than 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. A RSS pump casing drain/vent valve was open for more than 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> during both the filling operation and the draining operation.
Thus, when this RSS pump flow surveillance procedure was being performed, BVPS Unit 1 inadvertently did not comply with TS 3.6.1, which was a condition prohibited by the plant's Technical Specifications and is reportable pursuant to 10CFR50.73(a)(2)(i)(B).
ANALYSIS OF EVENT (Continued) An engineering evaluation was performed to assess the impact of the containment bypass path that existed during the surveillance procedure on the potential radiological doses following a postulated design basis accident (i.e., LOCA). This assessment determined that neither the licensing bases dose values nor the regulatory dose limits would have been exceeded. Additionally, based on the small unisolated valve openings and the maximum calculated flow rates through the flow path, this event is not expected to impact the Large Early Release Frequency (LERF). Therefore, this event is considered to have very low safety significance.
There was no loss of safety function for the Containment pursuant to 10 CFR 50.73(a)(2)(v) since the evaluation described above concluded that neither the licensing bases radiological dose values nor the regulatory radiological dose limits would have been exceeded if a LOCA were postulated to have occurred during the time that the drain/vent valves were open (providing potential leak paths from the containment) when this surveillance procedure was being performed.
CAUSE OF EVENT
The root cause of this event was determined to be less than adequate change management in revising the performance mode of the test without adequate evaluation of the impact on Technical Specification requirements. Narrow focus by procedure preparers, review organizations and end users on the most obvious TS requirement (Recirculation Spray System) resulted in a failure to identify, that a more limiting TS requirement (Containment operability) was impacted by the test.
A contributing cause was that components associated with the Recirculation Spray System pump (vents, drains, pump seal, etc) were not consistently identified in site procedures as potential impacts on containment operability.
CORRECTIVE ACTIONS
1. The subject Recirculation Spray System surveillance procedures will be revised to include reference to Containment Technical Specification 3.6.1 and the necessary steps to ensure compliance, such as maintaining the suction and discharge CIVs in the de-energized and closed position.
CORRECTIVE ACTIONS (Continued) 2. Various other routine Recirculation Spray System pump procedures will be reviewed and revised as appropriate at both BVPS units to include a reference to Technical Specification 3.6.1 for Containment, and to verify that sequence of steps are appropriate to ensure compliance while in Modes 1 through 4.
3. A training needs analysis will be performed for the licensed operator initial and continuing training programs based on this event. This analysis will consider if current training material adequately emphasizes that the Outside. Recirculation Spray System components (vents, drains, pump seal, etc) at both units are an extension of the Containment boundary, and the need to take a broad view of affected Technical Specifications when procedure changes are made such as changing the mode of performance.
4. A training needs analysis will be performed for Engineering training programs based on this event. This analysis will consider if current training material adequately emphasizes that the Outside Recirculation Spray System components (vents, drains, pump seal, etc) at both units are an extension of the Containment boundary, and the need to take a broad view of affected Technical Specifications when procedure changes are made such as changing the mode of performance.
5. The training program for the independent procedure reviewers (IQR) will be updated to include lessons learned from this event with emphasis on the responsibility of the IQR to ensure compliance with applicable Technical Specifications.
Completion of the above and other corrective actions are being tracked through the BVPS corrective action program.
PREVIOUS SIMILAR EVENTS
A review found two prior BVPS Unit No. 1 and one prior BVPS Unit No. 2 Licensee Event Report within the last three years for an event involving an actual or potential breach of containment integrity or events involving recent procedure changes for tests being conducted during power operation.
- BVPS Unit 1 LER 2006-003, "Inadvertent Technical Specification Noncompliance Due to Inoperable Containment Isolation Valve". This LER involved not closing a containment isolation valve on a clearance boundary as expected, due to a combination of human error and inadequate supervision oversight.
PREVIOUS SIMILAR EVENTS (Continued)
- BVPS Unit 2 LER 2008-002, "Containment Air Lock Equalization Valve Inadvertently Left Open Following Routine Containment Entry". This LER involved not closing a containment isolation valve following a routine, containment entry as required by the procedure, due to inappropriate procedure format.
- BVPS Unit 1 LER 2007-001, "Valve Testing Program Change Inadvertently Leads to Condition Beyond Design Basis During Test". This LER involved a weakness of the procedure change process.
Both of the first two LERs were not similar to this LER because appropriate procedural steps and practices were not followed. In this 2009 Unit 1 LER, adequate containment isolation procedural guidance was not provided.
The third LER involved not recognizing the procedure change's effect on the design basis safety analysis which would not have been reasonably evident to the procedure performers. This 2009 Unit 1 LER involved not recognizing the procedure change's effect on a second Technical Specification requirement, which could have been understood by the procedure performers.
CR 09-56250 Simplified Drawing BVPS Unit 1 Recirculation Spray System Outside Pump Subsystem Test Configuration Vent Vent Flow Element
Heat Exchanger RSS Pump MOV-1RS-156B Casing Drain 1RS-P-2B Valve Pump Casing MOV-1RS-155B Inside Outside Containment Containment
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05000410/LER-2009-001 | Momentary Loss of Control Power to High Pressure Core Spray, Pump Due to Degraded Fuse Block Connection | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000266/LER-2009-001 | Component Coolina Water PumD Inoperable In Excess of Technical Specification Allowed Completion Time | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000263/LER-2009-001 | Containment Overpressure Not Ensured in the Appendix R Analysis | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000250/LER-2009-001 | Procedure Inadequacy Causes Control Room Ventilation Isolation Technical Specification Noncompliance | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000237/LER-2009-001 | Common Mode Failure of Reactor Building Isolation Dampers | 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000530/LER-2009-001 | Manual Reactor Trip Due to a Loss of Instrument Air to the Containment Building | | 05000457/LER-2009-001 | Reactor Trip on Over Temperature Delta Temperature due to a Signal Spike on One Channel With Another Channel Placed in the Tripped Condition for Surveillance Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000413/LER-2009-001 | Both Trains of Chemical and Volume Control, Auxiliary Feedwater and Containment Spray Systems were Inoperable due to a Component Failure | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000412/LER-2009-001 | Equipment Operability for Steam Generator Tube Rupture Safety Analysis Not Met | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vi) | 05000461/LER-2009-001 | Safety Function Lost Due to Capacitor Failure on Circuit Card | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000382/LER-2009-001 | Waterford 3 Steam Electric Station 05000382 1 OF 3 | | 05000370/LER-2009-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000346/LER-2009-001 | Containment Air Cooler Fans Inoperable Due to Misapplication of Potter and Brumfield Rotary Relays | 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 | 05000336/LER-2009-001 | Reactor Trip Due to High Pressurizer Pressure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000305/LER-2009-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000281/LER-2009-001 | Manual Reactor Trip Initiated to Replace a Rod Control Data Logging Card | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000261/LER-2009-001 | Emergency Diesel Generator Inoperable in Excess of Technical Specifications Allowed Completion Time | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000220/LER-2009-001 | Failure to Implement Required Technical Specification Actions Associated with Failed Surveillance Test | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000389/LER-2009-001 | Unit 2 Main Feedwater Isolation Valves Stroke Time Potentially Affected by Temperature | 10 CFR 50.73(a)(2)(I)(B) | 05000321/LER-2009-001 | Pump Suction Swap for HPCI and RCIC Non-Conservative With Respect To Technical Specification Requirements | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000334/LER-2009-001 | Surveillance Test Inadvertently Violates Technical Specification 3.6.1 for Containment Operability | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000369/LER-2009-001 | III Duke Energy® BRUCE H HAMILTON Vice President McGuire Nuclear Station Duke Energy Corporation MGO1VP / 12700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.com June 24, 2009
U.S. Nuclear Regulatory Commission
ATTENTION: Document Control Desk
Washington, D.C. 20555
Subject: Duke Energy Carolinas, LLC
McGuire Nuclear Station, Units 1 and 2
Docket Nos. 50-369, 50-370
Licensee Event Report 369/2009-01, Revision 0
Problem Investigation Process (PIP) M-09-02216
Pursuant to 10 CFR 50.73 Sections (a) (1) and (d), attached
is Licensee Event Report 369/2009-01, Revision 0, regarding
the past inoperability of the Nuclear Service Water System
"A" Trains due to potential for strainer fouling.
This report is being submitted in accordance. with 10 CFR
50.73 (a) (2) (i)- (B), an Operation Prohibited by Technical
Specifications, and 10 CFR 50.73 (a) (2) (v) (B), any Event.
or Condition That Could Have Prevented Fulfillment of the
Safety Function.
This event is considered to be of no significance with
respect to the health and safety of the public. There are
no regulatory commitments contained in this LER.
If questions arise regarding this LER, contact Rick Abbott
at 980-875-4685.
Very truly yours,
Bruce H. Hamilton
Attachment
www.duke-energy.corn m U.S. Nuclear Regulatory Commission
Date
Page 2
CC: L. A. Reyes, Regional Administrator •U.S. Nuclear Regulatory Commission, Region.II
Sam Nunn Atlanta Federal Center
•61 Forsyth Street, SW, Suite 23T85
Atlanta, GA 30303
J. H. Thompson, Jr. (Addressee Only)
Senior Project Manager (McGuire)
U.S. Nuclear Regulatory Commission
Mail Stop 0-8G9A
Washington, DC 20555
J. B. Brady
Senior Resident Inspector
U.S. Nucle'ar Regulatory Commission-
McGuire Nuclear Station
B. 0. Hall, Section Chief
Radiation Protection Section
1645 Mall Service Center.
Raleigh, NC 27699
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104t EXPIRES: 08/31/2010
(9-2007) Estimated burden per response to comply with this mandatory collection request: 50 hours. Repoded
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 internet 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 (See reverse for required number of collection does not display a currently valid OMB control number, the NRC may not conduct or digits/characters for each block) sponsor, and a person is not required to respond to, the information collection. LICENSEE EVENT REPORT (LER) 1. FACILITY NAME 2. DOCKET NUMBER I 3. PAGE _McGuire Nuclear Station, . 0369 8 Unit 1 05000- OF 4. TITLE Nuclear Service Water System (NSWS)d
"A" Trains Past Inoperable when aligned
to the Standby Nuclear Service Water Pond due to'corrosion.
(SNSWP) | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | 05000456/LER-2009-001 | Steam Generator Tube Exceeding Plugging Criteria Remained In Service During Previous Cycle | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000395/LER-2009-001 | Inadequate Procedure Results In EDG Not Obtaining Maximum Load Required By Technical Specification | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000336/LER-2009-002 | Reactor Coolant System Pressure Boundary Leakage | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000373/LER-2009-002 | Loss of Shutdown Cooling Due to Spurious Closure of the Shutdown Cooling Suction Isolation Valve | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | 05000382/LER-2009-002 | Waterford 3 Steam Electric Station 05000382 10OF 4 | | 05000278/LER-2009-002 | Inoperable 'A' Wide Range Neutron Monitor Results in Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000287/LER-2009-002 | Unit 3 Trip Due to Generator Phase Differential Lockout | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000263/LER-2009-002 | | | 05000412/LER-2009-002 | Unacceptable Indications Identified During Reactor Vessel Head Inspection | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000354/LER-2009-002 | As Found Values for Safety Relief Valve Lift Setpoints Exceed Technical Specification Allowable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000346/LER-2009-002 | Vibration Induced Failure of Temperature Instrument Results in Operation above Licensed Power Limit | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000261/LER-2009-002 | Failure to Complete Technical Specifications Required Action Within the Allowed Completion Time | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000334/LER-2009-002 | Feedwater Isolation Initiates Auxiliary Feedwater System During Refueling Shutdown | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000254/LER-2009-002 | Quad Cities Nuclear Power Station Unit 1 05000254 1 OF 5 | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000305/LER-2009-002 | Steam Exclusion Door Blocked Open During Maintenance Activities | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000250/LER-2009-002 | Turkey Point Unit 3 05000250 1 of 10 | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 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 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000220/LER-2009-002 | High Pressure Coolant Injection System Initiation Following a Manual Turbine Trip Due to High Turbine Bearing Vibrations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000298/LER-2009-002 | Manual Scram On Low Water Level Caused By Turbine Trip From Hydraulic Fluid Leak | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000305/LER-2009-003 | Containment Spray Pump A Inoperable At Degraded Voltage Protection Setpoint | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000395/LER-2009-003 | ..Potential Loss of Residual Heat Removal System Safety Function In Mode 4 Due To An Unanalyzed Condition0 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | 05000389/LER-2009-003 | RCP 2B2 Lower Seal Cavity Line Leak | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000323/LER-2009-003 | Containment Sump Recirculation Valve Position Interlock Failure Due to Inadequate Testing | | 05000263/LER-2009-003 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000261/LER-2009-003 | Manual Reactor Trip Due to Failure of 'A' Steam Generator Level Module | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2009-003 | Reactor Recirculation Pump Failure Results in Manual Reactor Protection System Actuation | 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 | 05000361/LER-2009-003 | Pressurizer Auxiliary Spray Failed Inservice Test | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | 05000457/LER-2009-003 | Drain Procedure for ECCS Suction Line Creates an Unanalyzed Condition Due to Inadequate Configuration Requirements | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000237/LER-2009-003 | Emergency Diesel Generator Oil Leak | 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 |
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