On August 22, 2003, a Turbine Trip was caused by a spurious actuation of Moisture Separator Hi-Hi Level switch, LS-4-691. This resulted in a Reactor Scram from 100% power. The reactor shut down as designed. Plant cooldown to cold shutdown was required due to the trip of all five recirculation pumps.
The safety significance of this event is considered minimal. The plant responded as designed for this type of event. Technical Specification limits were maintained. There was no radioactive release. All safety systems were fully operable. Off-site power was available. Operator performance was satisfactory.
All four level switches were replaced and a root cause is in progress. |
DATE OF DISCOVERY
This event occurred on August 22, 2003.
IDENTIFICATION OF OCCURRENCE
Note: System Identification codes from IEEE 805-1984 are indicated with SI. Component Function Identifiers from ANSI/IEEE 803A-1983 are indicated by CFI.
A spurious actuation of a Moisture Separator (SI - SN), HI-HI Level switch (CFI - LS) tripped the main turbine (CFI - TRB) and scrammed the reactor (CFI - RCT). Actuation of the Reactor Protection System is reportable under 10 CFR 50.73(a)(2)(iv)(A).
CONDITIONS PRIOR TO DISCOVERY
The plant was operating at approximately 100% power at normal reactor pressure, level, and temperature. All safety-related equipment was operable. Plant conditions prior to the Turbine Trip / Scram were stable.
DESCRIPTION OF OCCURRENCE
On August 22, 2003, at 0259 hours0.003 days <br />0.0719 hours <br />4.282407e-4 weeks <br />9.85495e-5 months <br />, annunciators (CFI - ANN) in the Main Control Room indicated a Moisture Separator HI-HI Level alarm. About ten seconds later the main turbine tripped as designed. The reactor then scrammed as designed, due to the anticipatory scram on the turbine stop valve closure.
The turbine trip caused a pressure increase which caused two of five Electromatic Relief Valves (CFI - RV) to open momentarily, three of five Reactor Recirculation Pumps (SI - AD, CFI - P) to trip, and both Isolation Condensers (SI - BL) to actuate. The reactor scram shut down the reactor as designed. Operators manually tripped the two operating Reactor Recirculation pumps, as required by procedure, and stabilized plant conditions.
Although no Technical Specification required the plant to be placed in the Cold Shutdown condition, the trip of all reactor recirculation pumps required cooldown to cold shutdown to recover the plant. Plant cooldown was begun at 0349 hours0.00404 days <br />0.0969 hours <br />5.770503e-4 weeks <br />1.327945e-4 months <br />. Shutdown Cooling (SI - BO) was placed in service at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br /> and the cold shutdown condition was reached at 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br />.
NRC FOR/0360A (1-2031) NRC FORM MAUS. NUCLEAR REGULATORY COMMISSION (1-20011 FACILITY NAME (1) DOCKET (2) LER NUMBER (6) PAGE (3)
APPARENT CAUSE
Actuation of the Reactor Protection System was caused by closure of the turbine stop valves when the turbine tripped. The turbine trip was caused by spurious actuation of Moisture Separator Hi-Hi Level switch, LS-4-691.
ANALYSIS OF OCCURRENCE AND SAFETY ASSESSMENT
The safety significance of this event is considered minimal. The plant is designed for this type of transient and responded as designed. Technical specification limits were maintained. There was no radioactive release, nor any effect on the health and safety of the public. Operator performance was satisfactory.
CORRECTIVE ACTIONS
Replaced all four moisture separator Hi-Hi Level Switches.
A root cause of the switch actuation is in progress to determine if additional corrective actions are warranted.
SIMILAR EVENTS
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05000397/LER-2003-010 | | | 05000528/LER-2003-001 | Pressurizer Safety Valve As-Found Lift Pressure Outside of Technical Specification Limits | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000277/LER-2003-001 | | | 05000282/LER-2003-001 | | | 05000301/LER-2003-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000261/LER-2003-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000251/LER-2003-001 | Channel Failure of Qualified Safety Parameter Display System | | 05000316/LER-2003-001 | Unit 2 Shutdown In Accordance With Technical Specification 3.8.1.1, A.C. Sources, Action b | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000324/LER-2003-001 | Main Steam Line Drain Isolation Valve Local Leak Rate Test Failures | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000352/LER-2003-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000353/LER-2003-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000397/LER-2003-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000364/LER-2003-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000529/LER-2003-001 | Reactor Trip with Loss of Forced Circulation Due to Failed Pressurizer Main Spray Valve | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000278/LER-2003-001 | | | 05000305/LER-2003-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000331/LER-2003-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000313/LER-2003-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000352/LER-2003-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000301/LER-2003-002 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000305/LER-2003-002 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000316/LER-2003-002 | Supplemental LER for Unit 2 Reactor Trip due to Instrument Rack 24 Volt Power Supply Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000458/LER-2003-002 | | 10 CFR 50.73(a)(2)(v)(c) | 05000348/LER-2003-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000341/LER-2003-002 | Automatic Reactor Shutdown Due to Electric Grid Disturbance and Loss of Offsite Power | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000261/LER-2003-002 | | | 05000285/LER-2003-002 | 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000397/LER-2003-002 | | | 05000499/LER-2003-002 | Safety Injection Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2003-002 | Reactor Scram as a Result of a Loss of Off-site Power | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) | 05000400/LER-2003-002 | 1 O OF 3 3 | | 05000266/LER-2003-002 | | 10 CFR 50.73(a)(2)(iv), System Actuation | 05000250/LER-2003-003 | Unescorted Access Inappropriately Approved Due to Falsified Pre-Access Information | | 05000261/LER-2003-003 | | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | 05000219/LER-2003-003 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000247/LER-2003-003 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000530/LER-2003-003 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000331/LER-2003-003 | | | 05000529/LER-2003-003 | SOURCE RANGE MONITOR INOPERABLE DURING CORE RELOAD | 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-2003-003 | Unrecognized Diesel Generator Inoperability During Mode Changes | | 05000348/LER-2003-003 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000482/LER-2003-003 | REACTOR PROTECTION SYSTEM ACTUATION AND REACTOR TRIP DUE TO FEEDWATER ISOLATION VALVE CLOSURE | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000301/LER-2003-003 | | | 05000302/LER-2003-003 | Reactor Coolant System Pressure Boundary Leakage Limit Exceeded Due To Pressurizer Instrument Tap Nozzle Cracks | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000382/LER-2003-003 | RCS Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking (PWSCC) | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000397/LER-2003-003 | | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | 05000458/LER-2003-003 | | 10 CFR 50.73(a)(2)(v)(c) | 05000454/LER-2003-003 | Licensed Maximum Power Level Exceeded Due to Inaccuracies in Feedwater Ultrasonic Flow Measurements | | 05000282/LER-2003-003 | | | 05000346/LER-2003-014 | Steam Feedwater Rupture Controls System Re-Energizes in a Blocked Condition | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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