05000387/LER-1917-006, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Exhaust Fan
| ML17249A538 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/06/2017 |
| From: | Berryman B Susquehanna, Talen Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-7633 LER 17-006-00 | |
| Download: ML17249A538 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 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)(ix)(A) 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)(A), Completion of TS Shutdown 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) |
| 3871917006R00 - NRC Website | |
text
SEP 0 6 2017 Brad Berryman Site Vice President U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 Brad.Berryman@TalenEnergy.com SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388(387)/2017-006-00 UNIT 1 LICENSE NO. NPF-14 UNIT 2 LICENSE NO. NPF-22 PLA-7633 TALEN~
ENERGY 10 CFR 50.73 Docket No. 50-387 50-388 Attached is Licensee Event Report (LER) 50-3 8 8(3 87)/20 17-006-00. The LER reports an event involving the loss of Secondary Containment due to a trip of a Zone II Exhaust Fan. This event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(v)(C) as a condition that could have prevented fulfilment of a safety function.
Should you have any questions regarding this submittal, please contact Mr. Jason Jennings, Manager-Nuclear Regulatory Affairs at (570) 542-3155.
There were no actual consequences to the health and safety of the public as a result of this event.
ins no new regulatory commitments.
B. Benyman Attachment: LER 50-388(387)/2017-006-00 Copy:
NRC Region I Ms. T. E. Hood, NRC Project Manager Ms. L. H. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, PA DEP/BRP
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0313112020 (04-2017) htlr;1://www. nrc. gov/reading-rm/doc-collectio ns/nu regs/staff/sr1 022/r3D the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME
~ - DOCKET NUMBER
- 13. PAGE Susquehanna Steam Electric Station Unit 2 05000388 1 OF3
- 4. TITLE Secondary Containment Declared Inoperable Due to Trip of Zone II Exhaust Fan
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR REV MONTH DAY YEAR Susquehanna Steam Electric Station Unit 1 NUMBER NO.
05000387 07 10 2017 2017
- - 006
- - 00 2017 FACILITY NAME DOCKET NUMBER OCf Q(_p 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 D 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2201(d)
D 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii) 0 50.36(c)(1 )(ii)(A)
D 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5) 100 D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
[8J 50.73(a)(2)(v)(C)
D 73.77(a)(1)
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii) 0 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT r~LEPHONE NUMBER (lndude Area Code)
I C. E. Manges, Jr., Senior Engineer-Nuclear Regulatory Affairs
[(570) 542-3089
- 13. COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX B
VA FSV A499 y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
[8J NO SUBMISSION DATE fl\\BSTRACT (Limit to 1400 spaces, i.e.. approximately 15 single-spaced typewritten lines)
On July 10, 2017, at approximately 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />, Reactor Building Zone II differential pressure was not maintained above the Technical Specification (TS) limit of 0.25 inch of vacuum water gauge (WG) due to Discharge Damper PDD27578B failing closed resulting in loss of the associated Reactor Building Zone II Exhaust Fan 2V205B. As a result, TS 3.6.4.1 Surveillance Requirement (SR) 3.6.4.1.1 was not met due to the loss of differential pressure. Reactor Building Zone II Exhaust Fan 2V205A was manually started and Reactor Building Zone II differential pressure was restored to greater than 0.25 inches WG by approximately 0301 hours0.00348 days <br />0.0836 hours <br />4.976852e-4 weeks <br />1.145305e-4 months <br />.
The condition is being reported in accordance with 10 CFR 50. 73(a)(2)(v)(C) as an event or condition that could have prevented fulfillment of a safety function.
The cause of the event was the failure of the ASCO solenoid valve. Based on further review, the ASCO solenoid valve has been determined to be less than adequate for its application in Reactor Building HVAC.
There were no actual consequences to the health and safety of the public as a result of this event.
NRC FORM 366 (04-2017)
CONDITIONS PRIOR TO EVENT
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 2. DOCKET NUMBER YEAR 05000388 2017
- 3. LER NUMBER SEQUENTIAL NUMBER
- - 006 REV NO.
- - 00 Unit 1 -Mode 1, approximately 100 percent Rated Thermal Power Unit 2 - Mode 1, approximately 100 percent Rated Thermal Power There were no structures, systems, or components that were inoperable at the start of the event that contributed to the event.
EVENT DESCRIPTION
On July 10, 2017, at approximately 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />, Reactor Building [EllS System Code: NG] Zone II differential pressure was not maintained above the Technical Specification (TS) limit of 0.25 inch of vacuum water gauge 0JVG) due to Discharge Damper PDD27578B [EllS System/Component Identifier: VA/DMP]
failing closed resulting in loss of the associated Reactor Building Zone II Exhaust Fan 2V205B [EllS System/Component Identifier: VA/FAN]. Reactor Building Zone II Exhaust Fan 2V205A was manually started and Reactor Building Zone II differential pressure was restored to greater than 0.25 inches WG by approximately 0301 hours0.00348 days <br />0.0836 hours <br />4.976852e-4 weeks <br />1.145305e-4 months <br />.
On July 10, 2017, at 0735 hours0.00851 days <br />0.204 hours <br />0.00122 weeks <br />2.796675e-4 months <br />, this condition was reported (ENS#52844) in accordance with 10 CFR 50.72(b)(3)(v)(C) as an event or condition that, at the time of discovery, could have prevented the fulfillment of the safety function to mitigate the consequences of an accident by controlling the release of radioactive material. SSES has no redundant Secondary Containment System.
CAUSE OF EVENT
The cause of the event was the failure of an ASCO solenoid valve [EllS Component Identifier: FSV]
associated with Discharge Damper PDD27578B. Based on further review, the ASCO solenoid valve has been determined to be less than adequate for its application in Reactor Building Heating Ventilation and Air Conditioning (HVAC) system.
ANALYSIS/SAFETY SIGNIFICANCE
Based on engineering analysis of the event, secondary containment could have performed its safety function of isolating as assumed in the accident analysis and of re-establishing 0.25 inches of vacuum WG (drawdown) within the assumed accident analysis time (1 0 minutes).
This event will not be counted as a safety system functional failure (SSFF) for the NRC performance
- indicator based on the engineering analysis supporting the system's ability to fulfill the safety function.
NRC FORM 3668 (04-2017)
Page 2 of 3 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020 (04*2017)
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1 022, R.3 for instruction and guidance for completing this form http:l/wwvv.nrc.gov/reading-rm/doc-collections/nureqs/staff/sr1 0221r3D
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
Susquehanna Steam Electric Station Unit 2 05000388
CORRECTIVE ACTIONS
YEAR 2017
- 3. LER NUMBER SEQUENTIAL NUMBER
- - 006 Key corrective actions include replacement of the failed solenoid valve with a more robust model.
COMPONENT FAILURE INFORMATION
Manufacturer:
Type:
Process Fluid:
Model:
Voltage:
ASCO Services 3-way electrical solenoid valve Air ASCO 8320 Solenoid Valve, General Use Model 83208003 120 VAC
PREVIOUS SIMILAR EVENTS
The following are recent LERs involving loss of secondary containment due to component failures:
LER 50-388(387)/2017-005-00, " Secondary Containment Declared Inoperable Due to Trip of Zone Ill Filtered Exhaust Fan," dated August 18, 2017.
LER 50-387(388)/2016-012-00, "Unit 2 HVAC Unable to Maintain Differential Pressure," dated May 26, 2016.
LER 50-387(388)/2016-003-00, "Unit 2 Zone 3 HVAC Unable to Maintain Differential Pressure," dated May 6, 2016.
REV NO.
- - 00 LER 50-387(388)/2015-013-00, "Loss of Secondary Containment Due to Failure of Fans," dated February 2, 2016.
LER 50-387(388)/2015-012-00, "Loss of Secondary Containment Differential Pressure Due to Icing of the Intake Supply Plenum Screens," dated February 2, 2016.
LER 50-387(388)/2015-010-00, "Loss of Zone 2 During Unit 1 Reactor SCRAM," dated January 8, 2016.
LER 50-387(388)/2015-005-00, "Loss of Secondary Containment Due to Unit 2 Damper Alignment," dated June 25, 2015.
LER 50-387(388)/2015-002-00," Loss of Secondary Containment due to failure of running fans," dated June 1 0, 2015.
NRC FORM 3668 (04-2017)