05000387/LER-1917-009, Regarding Secondary Containment Declared Inoperable Due to Trip of Zone II Equipment Exhaust Fan
| ML17319A056 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/15/2017 |
| From: | Berryman B Susquehanna, Talen Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-7656 LER 17-009-00 | |
| Download: ML17319A056 (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) |
| 3871917009R00 - NRC Website | |
text
NOV 1 5 2011 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)/2017-009-00 UNIT 1 LICENSE NO. NPF-14 UNIT 2 LICENSE NO. NPF -22 PLA-7656 TALEN~
ENERGY 10 CFR 50.73 Docket No. 50-387 50-388 Attached is Licensee Event Report (LER) 50-388(387)/2017-009-00. The LER reports an event involving the loss of Secondary Containment due to a trip of a Zone II Equipment 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.
This letter contains no new regulatory commitments.
Attachment: LER 50-3 88(3 87)/20 17-009-00 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: 03/31/2020 (04-2017) htt~;rl/www. nrc.gov/readi ng-nn/doc-collectio ns/n u 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 Equipment 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 09 16 2017 2017
- - 009
- - 00
\\ \\
\\5 2017 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERA TlNG MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 1 D 2o.2201(b)
D 20.2203(a)(3)(i) 0 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.22o1(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) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1 )(ii)(A) 0 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii) 0 50.36(c)(2)
D 50.73(a)(2)(v)(B) 0 73.71(a)(5) 100 D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
[8] 50.73(a)(2)(v)(C)
D 73.77(a)(1)
D 20.2203(a)(2)(v) 0 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) 0 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii) 0 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
~~LEPHONE NUMBER (Include A!ea Code)
I C. E. Manges, Jr., Senior Engineer-Nuclear Regulatory Affairs 1(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 TOEPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR IX] YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
D NO SUBMISSION DATE 12 22 2017 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten fines)
On September 16, 2017 at approximately 13:30, when performing a swap to place the Unit 2 "A" Reactor Building Equipment Compartment Exhaust Fan (2V206A) in service, the fan tripped unexpectedly after being placed in service. Reactor Building differential pressure lowered to < 0.25 inches water gauge (WG) due to the unexpected trip of 2V206A. As a result, Technical Specification 3.6.4.1 Surveillance Requirement 3.6.4.1.1 was not met due to the loss of Secondary Containment differential pressure. The 2V206B fan was placed back in service and Reactor Building differential pressure was restored to above 0.25 inches WG.
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 failure was not able to be replicated during investigation. The cause is still under investigation.
Corrective actions will be determined following completion of the cause analysis.
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
- - 009 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 September, 16, 2017, a plant operator identified belts associated with the Unit 2 "B" Reactor Building Equipment Compartment Exhaust Fan (2V206B) [EllS System/Component Identifier: VA/FAN] slipping and a hot burnt rubber smell in the area. The operator recommended swapping fans to place the "A" fan (2V206A) in service.
On September 16, 2017 at approximately 13:30, when performing the swap to place the 2V206A fan in service, the 2V206A fan tripped unexpectedly after being placed in service. Reactor Building [EllS System Code: NG] differential pressure lowered to < 0.25 inches water gauge (WG) due to the unexpected trip of 2V206A. As a result, Technical Specification 3.6.4.1 Surveillance Requirement 3.6.4.1.1 was not met due to the loss of Secondary Containment differential pressure. The 2V206B fan was placed back in service and Reactor Building differential pressure was restored to above 0.25 inches WG.
On September, 16, 2017, at 15:53, this condition was reported (ENS#52973) 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. Susquehanna Steam Electric Station (SSES) has no redundant Secondary Containment System.
CAUSE OF EVENT
The failure was not able to be replicated during investigation. The cause is still under investigation. Further information associated with the cause will be provided in a supplement to this LER.
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 (10 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://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1 022/r3D
- 1. FACILITY NAME Susquehanna Steam Electric Station Unit 2
CORRECTIVE ACTIONS
, 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
- - 009 REV NO.
- - 00 Corrective actions will be determined following completion of the cause analysis and will be provided in a supplement to this LER.
PREVIOUS SIMILAR EVENTS
Previous similar events will be provided in the supplement to this LER.
NRC FORM 3668 (04-2017)