LER-2013-008, Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(iii)
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B)
10 CFR 50.73(a)(2)(ix)(A)
10 CFR 50.73(a)(2)(x) |
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L-2013-250 10 CFR § 50.73 August 19, 2013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re:
Turkey Point Unit 3 Docket No. 50-250 Reportable Event: 2013-008-00 Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to be Inoperable Longer than AOT The attached Licensee Event Report 05000250/2013-008-00 is submitted in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the Technical Specifications.
If there are any questions, please call Mr. Robert J. Tomonto at 305-246-7327.
Very truly yours, Michael Kiley Vice President Turkey Point Nuclear Plant Attachment cc:
Regional Administrator, USNRC, Region 1I Senior Resident Inspector, USNRC, Turkey Point Nuclear Plant Florida Power & Light Company 9760 SW 344t' St., Florida City, FL 33035 1-
,IZL
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Turkey Point Unit 3 05000250J 1 of 4
- 4. TITLE Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to be Inoperable Longer than AOT Y SEQUENTIAL REVM NUMBER MONTH I
- 10. POWER LEVEL 100 El El El El El El El El El 20.2201(b) 20.2201(d) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi)
El 20.2203(a)(3)(i)
El 20.2203(a)(3)(ii)
El 20.2203(a)(4)
El 50.36(c)(1)(i)(A)
El 50.36(c)(I)(ii)(A)
El 50.36(c)(2)
El 50.46(a)(3)(ii)0 [E 50.73(a)(2)(i)(A)
Z 50.73(a)(2)(i)(B)
El El El El El El El El El 50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D)
El 50.73(a)(2)(vii)
El 50.73(a)(2)(viii)(A)
El 50.73(a)(2)(viii)(B)
El 50.73(a)(2)(ix)(A)
El 50.73(a)(2)(x)
El 73.71(a)(4)
El 73.71(a)(5)
El OTHER Specify in Abstract below or in
ANALYSIS OF THE EVENT
Background
CCW circulates through engineered safety features (ESF) heat loads during accident conditions to support ESF equipment cooling, reactor heat removal and containment heat removal. CCW is required to maintain safe shutdown (hot standby) at any time, including loss of offsite power and plant fires. CCW is also required to achieve and maintain safe (cold) shutdown during fires requiring control room evacuation, remove spent fuel pool heat, and remove plant heat loads required to support all normal operating modes.
Analysis The leak at the 3A CCW pump vent line was documented on June 7, 2013 in condition reports 1880602 and 1880576. The immediate operability screening concluded that the low leakage rate did not affect system operation. The leak was observed and assumed to be thread leakage where the pipe nipple is installed in the pump casing. Because leakage at threaded connections is occasionally experienced and mostly attributable to thread leakage and not through-wall leakage, station staff including Operations, Engineering and condition report reviewers did not consider the possibility of a through-wall leak.
The vent line fitting was removed and examined to determine the cause of the leakage. Initial examination of the pipe nipple revealed a through-wall flaw approximately V/ inch long at the valley of the sixth thread.
Subsequent examination detemined the flaw to be in excess of the length required to assure structural integrity. The failure mode was determined to be high cycle fatigue.
The 3A CCW pump vent line fitting with the service-induced flaw was installed in 2012. New vent lines were installed on all Unit 3 and 4 CCW pump casings to improve venting effectiveness. The design will be modified to increase margin for vibration effects.
Reportability
TS Limiting Condition for Operation (LCO) 3.7.2 requires three CCW pumps to be operable in Modes 1-4. If one CCW pump is inoperable, then the AOT is 30 days if both remaining pumps are powered by independent sources. If the remaining two CCW pumps are not powered from independent sources, then the AOT is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. During the 12 day period June 7, 2013 to June 19, 2013, with the 3A CCW pump inoperable, both the 3B and 3C CCW pumps were powered from the same safety bus and were not independently powered, and so the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AOT applied. Therefore, the TS LCO, AOT and shutdown Actions were not met and a condition prohibited by the TS existed reportable in accordance with 10 CFR 50.73(a)(2)(i)(B).
ANALYSIS OF SAFETY SIGNIFICANCE The through-wall flaw in the 3A CCW pump vent fitting was determined to impact structural integrity and would not allow the pump to perform its safety function for its mission time of 30 days. Therefore, the 3A
CCW pump was inoperable during the 12-day period that leakage was evident and monitored prior to removal of the pump from service and repair.
During the 12-day period, the 3B and 3C CCW pumps were available to perform the safety function of the CCW system. While the 3B and 3C CCW pumps were aligned to the 3B 4160V safety bus, the capability existed to power the 3C CCW pump from the 3A 4160V safety bus should the need have arisen restoring the provision for independent power supplies. Only one CCW pump in operation is needed to remove design basis heat loads. Therefore, the CCW system remained functional with redundant capability to perform the required safety function and so the safety significance is considered to be low.
CORRECTIVE ACTIONS
Corrective actions include the following:
- 1. The leaking fitting on the 3A CCW pump was replaced.
- 2. Replace similar Schedule 40 CCW pump vent line fittings with Schedule 80 fittings.
- 3. Perform formal evaluations of existing leaks in threaded connections in Class 1, 2 and 3 systems.
- 4. Modify the design to increase margin for vibration effects.
ADDITIONAL INFORMATION
EIIS Codes are shown in the format [IEEE system identifier, component function identifier, second component function identifier (if appropriate)].
FAILED COMPONENTS IDENTIFIED: None
PREVIOUS SIMILAR EVENTS
None
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| 05000251/LER-2013-001, Regarding Power Operated Relief Valve Inoperable for Greater than Allowed Outage Time Due to Lifted Leads | Regarding Power Operated Relief Valve Inoperable for Greater than Allowed Outage Time Due to Lifted Leads | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000250/LER-2013-001, Regarding Procedure Noncompliance Causes Incorrect Instrument Setting and Condition Prohibited by Technical Specifications | Regarding Procedure Noncompliance Causes Incorrect Instrument Setting and Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000251/LER-2013-002, Reactor Trip Due to Loss of Offsite Power Resulting from Generator Testing | Reactor Trip Due to Loss of Offsite Power Resulting from Generator Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000250/LER-2013-002, Regarding Automatic Reactor Trip Due to Low Condenser Vacuum | Regarding Automatic Reactor Trip Due to Low Condenser Vacuum | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000250/LER-2013-003, Regarding Manual Reactor Trip Due to Increasing Reactor Coolant Pump Seal Leakage | Regarding Manual Reactor Trip Due to Increasing Reactor Coolant Pump Seal Leakage | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000250/LER-2013-004, Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position | Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000250/LER-2013-005, Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves | Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000250/LER-2013-006, Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps | Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
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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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000250/LER-2013-008, Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT | Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000250/LER-2013-009, Regarding Loose Breaker Control Power Fuse Holder Caused 3B Jcw Pump to Be Inoperable Longer than AOT | Regarding Loose Breaker Control Power Fuse Holder Caused 3B Jcw Pump to Be Inoperable Longer than AOT | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(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)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) |
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