05000373/LER-2016-001, Regarding Secondary Containment Inoperable Due to Reactor Building Ventilation Damper Failure
| ML16102A143 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/11/2016 |
| From: | Vinyard H Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA16-014 LER 16-001-00 | |
| Download: ML16102A143 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 3732016001R00 - NRC Website | |
text
LaSalle County Station Exeon Generation 815-415-2000 Telephone www.exeloncorpcom 10 CFR 50.73 RA16-014 April 11,2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Licensee Event Report 2016-001-00, Secondary Containment Inoperable due to Reactor Building Ventilation Damper Failure In accordance with 10 CFR 50.73(a)(2)(v)(C) and 10 CFR 50.73(a)(2)(v)(D), Exelon Generation Company (EGC), LLC, is submitting Licensee Event Report Number 2016-001-00 for LaSalle County Station, Units 1 and 2.
There are no regulatory commitments in this letter. Should you have any questions concerning this report, please contact Mr. Guy V. Ford, Regulatory Assurance Manager, at (815) 415-2800.
Respectfully, ZLJV Harold T. Vinyard Plant Manager LaSalle County Station
Enclosure:
Licensee Event Report cc:
Regional Administrator NRC Region Ill NRC Senior Resident Inspector LaSalle County Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0704 EXPIRES: 10/31/2018 (11-2015)
Estimated burden pet response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Intormation Collections LICENSEE EVENT REPORT (LER)
Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Otticer, Ottice of Information and (See Page 2 tot required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office ot Management and Budget, Washington,
.4 e
I k
+
I-. ki DC 20503. If a means used to impose an information collection does not risplay a currently valid igi S C arac ers or eac CC
)
0MB control number, the NRC may not conduct or sponsor, and a person is not requited to respond to, the information collection.
- 3. PAGE LaSalle County Station, Unit 1 05000373 1
OF 3
- 4. TITLE Secondary Containment Inoperable due to Reactor Building Ventilation Damper Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE f
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEL REQV MONTH DAY YEAR LaSalle County Station, Unit 2 05000374 FACILITY NAME DOCKET NUMBER 02 10 2016 2016 001 00 04 11 2016
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Checkalithat apply)
El 20.2201(b)
El 20.2203(a)(3)fi)
El 5O.73(a)(2)(ii)(A)
El 50.73(a)(2)fviii)fA)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(iii)
El 50.73(a)(2)tx)(A)
El 20.2203(a)(2)t)
El 50.36(c)(1 )(i)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(ii)
El 50.36(c)(1)ti)(A)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(B)
El 73.71 (a)(5)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
El 73.77(a)(1) 91 El 20.2203(a)(2)(v)
El 50.73(a)(2)O)(A) 50.73(a)(2)(v)(D)
El 73.77(a)(2)(i)
El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(vii)
El 73.77(a)(2)(ii)
El 50.73(a)(2)(i)(C)
El OTHER Specity in Abatract below or in D.
Safety Analysis
Reactor building ventilation fVR) is a non-safety system. The VR system provides filtered outdoor air to control the maximum reactor building temperature in generally accessible areas, and to maintain a minimum negative pressure of 0.25 inches of water column with respect to atmospheric pressure. The system operates during normal plant operating conditions, when secondary containment is required. Each units VA system is capable of maintaining secondary containment at the required negative pressure with the other units VA system shut down. The VA system has no safety design basis except those parts associated with secondary containment isolation dampers, main steam tunnel isolation, and fuel pool exhaust ducts. The loss of secondary containment pressure was reportable as an event or condition that could have prevented the fulfillment of a safety function.
E.
Corrective Actions
Aeplaced both solenoid valves on both halves of the 1 VRO5YA exhaust damper blades.
Declared damper 1 VRO5YA and secondary containment operable. Subsequently restarted the Unit 1 VA system.
Sent the failed solenoid to the vendor for failure analysis. Additional corrective actions will be determined following component failure analysis.
F.
Previous Occurrences
A review of past events identified no reportable occurrences resulting from reactor building ventilation exhaust damper failure in the previous ten years.
G.
Component Failure Data
Part Description: 3-Way Solenoid Valve with Manual Operator, 1/2 IN. NPT, MIN-MAX Operating Pressure Manufacturer: Automatic Switch Company Model No.: HT831 6AO65VMO NRC FORM 3e6A (11-2015)
LaSalle County Station Exeon Generation 815-415-2000 Telephone www.exeloncorpcom 10 CFR 50.73 RA16-014 April 11,2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Licensee Event Report 2016-001-00, Secondary Containment Inoperable due to Reactor Building Ventilation Damper Failure In accordance with 10 CFR 50.73(a)(2)(v)(C) and 10 CFR 50.73(a)(2)(v)(D), Exelon Generation Company (EGC), LLC, is submitting Licensee Event Report Number 2016-001-00 for LaSalle County Station, Units 1 and 2.
There are no regulatory commitments in this letter. Should you have any questions concerning this report, please contact Mr. Guy V. Ford, Regulatory Assurance Manager, at (815) 415-2800.
Respectfully, ZLJV Harold T. Vinyard Plant Manager LaSalle County Station
Enclosure:
Licensee Event Report cc:
Regional Administrator NRC Region Ill NRC Senior Resident Inspector LaSalle County Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0704 EXPIRES: 10/31/2018 (11-2015)
Estimated burden pet response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Intormation Collections LICENSEE EVENT REPORT (LER)
Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Otticer, Ottice of Information and (See Page 2 tot required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office ot Management and Budget, Washington,
.4 e
I k
+
I-. ki DC 20503. If a means used to impose an information collection does not risplay a currently valid igi S C arac ers or eac CC
)
0MB control number, the NRC may not conduct or sponsor, and a person is not requited to respond to, the information collection.
- 3. PAGE LaSalle County Station, Unit 1 05000373 1
OF 3
- 4. TITLE Secondary Containment Inoperable due to Reactor Building Ventilation Damper Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE f
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEL REQV MONTH DAY YEAR LaSalle County Station, Unit 2 05000374 FACILITY NAME DOCKET NUMBER 02 10 2016 2016 001 00 04 11 2016
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Checkalithat apply)
El 20.2201(b)
El 20.2203(a)(3)fi)
El 5O.73(a)(2)(ii)(A)
El 50.73(a)(2)fviii)fA)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(iii)
El 50.73(a)(2)tx)(A)
El 20.2203(a)(2)t)
El 50.36(c)(1 )(i)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(ii)
El 50.36(c)(1)ti)(A)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(B)
El 73.71 (a)(5)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
El 73.77(a)(1) 91 El 20.2203(a)(2)(v)
El 50.73(a)(2)O)(A) 50.73(a)(2)(v)(D)
El 73.77(a)(2)(i)
El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(vii)
El 73.77(a)(2)(ii)
El 50.73(a)(2)(i)(C)
El OTHER Specity in Abatract below or in A.
Condition Prior to Event
Unit(s): 1 / 2 Event Date: February 10, 2016 Event Time: 2207 CST Reactor Mode(s): 1 / 1 Mode(s) Name: Power Operation/Power Operation Power Level: 91%/i 00%
B.
Description of Event
On February 10, 2016, Unit 1 was in Mode 1 at 91 percent power and Unit 2 was in Mode 1 at 100 percent power. At 2207 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.397635e-4 months <br /> CST, it was reported that the Unit 1 reactor building ventilation (VR) exhaust damper 1 VRO5YA failed and began to show dual indication. As a result, the Unit 1 reactor building ventilation exhaust fans tripped oft, causing a positive reactor building differential pressure on both units. The damper and secondary containment were declared inoperable, and Technical Specification 3.6.4.1 Required Action A.i was entered on both units to restore secondary containment to operable within four hours.
In addition, Technical Specification 3.6.4.2 Required Action A.1 was entered to isolate the penetration with one closed or deactivated automatic valve within eight hours.
The loss of secondary containment pressure is reportable in accordance with 10 CFR 50.73(a)(2)(v)f C) and 10 CFR 50.73(a)(2)fv)fD) as an event or condition that could have prevented the fulfillment of the safety function of structures or systems needed to control the release of radioactive material and to mitigate the consequences of an accident. An ENS report was made to the NRC at 0120 EST on February ii, 2016 (EN#51725) pursuant to 10 CFR 50.72(b)(3)(v)(C) and (D).
With the Unit 1 VR system shutdown, the 1 VRO5YA damper was cycled open. The damper went full open; however, a buzzing sound was heard near its associated solenoid. The solenoids were inspected and it was noticed that the buzzing solenoid was also leaking slightly through its exhaust port. Within a short period of time it was observed that the solenoid intermittently energized and de-energized. When the solenoid was de-energized the damper indication was dual with one half of damper blade closed. The solenoids were replaced on both halves of the damper blades on 1 VRO5YA. Damper 1 VRO5YA was declared operable on February 11,2016 at 1027. The Unit 1 VR system was subsequently restarted.
The 1 VRO5YA damper is a safety-related component associated with secondary containment isolation; however, the event was not a Safety System Functional Failure (SSFF). An engineering evaluation concluded that the safety function of the 1 VRO5YA damper is to close during an accident condition to ensure the secondary containment safety function can be satisfied. Since the VR system exhaust isolation damper failed closed during the event, the damper safety function was met; and therefore, this event is not being counted as a Safety System Functional Failure (SSFF) for the NRC performance indicator.
C.
Cause of Event
An apparent cause investigation determined the cause was an intermittent failure of a solenoid on one of the two half damper blades on the 1VRO5YA exhaust isolation damper. This led to the exhaust damper blade half intermittently changing its position, which resulted in the pressure of secondary containment going positive.
There has not been a failure of any solenoid valves on all eight VR dampers in the last 15 years. The solenoids on 1 VRO5YA are replaced on every fourth outage (approximately eight-year frequency). They were last replaced on May 20, 2002 and February 12, 2010. The next scheduled replacement is due in March 2018. This history indicates the solenoid on the 1 VRO5YA exhaust damper failed prematurely. The last failure on April 29, 2009 was on Unit 2 exhaust isolation damper 2VRO5YA (dual indication) due to improper adjustment of the speed controller on the actuator.
D.
Safety Analysis
Reactor building ventilation fVR) is a non-safety system. The VR system provides filtered outdoor air to control the maximum reactor building temperature in generally accessible areas, and to maintain a minimum negative pressure of 0.25 inches of water column with respect to atmospheric pressure. The system operates during normal plant operating conditions, when secondary containment is required. Each units VA system is capable of maintaining secondary containment at the required negative pressure with the other units VA system shut down. The VA system has no safety design basis except those parts associated with secondary containment isolation dampers, main steam tunnel isolation, and fuel pool exhaust ducts. The loss of secondary containment pressure was reportable as an event or condition that could have prevented the fulfillment of a safety function.
E.
Corrective Actions
Aeplaced both solenoid valves on both halves of the 1 VRO5YA exhaust damper blades.
Declared damper 1 VRO5YA and secondary containment operable. Subsequently restarted the Unit 1 VA system.
Sent the failed solenoid to the vendor for failure analysis. Additional corrective actions will be determined following component failure analysis.
F.
Previous Occurrences
A review of past events identified no reportable occurrences resulting from reactor building ventilation exhaust damper failure in the previous ten years.
G.
Component Failure Data
Part Description: 3-Way Solenoid Valve with Manual Operator, 1/2 IN. NPT, MIN-MAX Operating Pressure Manufacturer: Automatic Switch Company Model No.: HT831 6AO65VMO NRC FORM 3e6A (11-2015)