05000388/LER-1917-010, Regarding Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
| ML18033A039 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/02/2018 |
| From: | Berryman B Susquehanna, Talen Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-7681 LER 17-010-00 | |
| Download: ML18033A039 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 3881917010R00 - NRC Website | |
text
FEB 0 2 2018 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 50-388/2017-010-00 UNIT 2 LICENSE NO. NPF -22 PLA-7681 TALEN~
ENERGY 10 CFR 50.73 Docket No. 50-388 Attached is Licensee Event Report (LER) 50-388/2017-010-00. This LER is reporting an event involving drifting of Reactor Pressure Steam Dome-Low switches. This event was determined to be reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
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 50-388/2017-010-00 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) htl[1://www. nrc. gov/read i ng-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
,3. PAGE Susquehanna Steam Electric Station Unit 2 05000388 1 OF3
- 4. TITLE Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Switches
- 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 NUMBER NO.
05000 12 5
2017 2017
- - 010
- - 00 02 02 2018 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERAllNG 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)
D 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)
D 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)
D 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)
D 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)
IXI50.73(a)(2)(i)(B)
D 50.73 (a)(2)(vii)
D 73.77(a)(2)(ii)
D 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 t~LEPHONE NUMBER (Include Area Code) lc. E. Manges, Jr., Senior Engineer-Nuclear Regulatory Affairs j(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 TOEPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR [8) YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
D NO SUBMISSION 3
30 2018 DATE
~BSTRACT (Limit to 1400 spaces, i. e., approximately 15 single-spaced typewritten lines)
On December 5, 2017, the Unit 2 "C" and Unit 2 "D" Reactor Steam Dome Pressure-Low permissive switches were found outside of the Technical Specification (TS) allowable value. Both drifted outside of the upper allowable value which is intended to ensure that the reactor dome pressure has fallen to a value below the Core Spray and Residual Heat Removal (RHR)/Low Pressure Coolant Injection (LPCI) maximum design pressures to preclude over-pressurization of the low pressure systems prior to low pressure injection initiation.
Based on the information currently available, Susquehanna believes that the condition existed for longer than allowed by TS 3.3.5.1 and TS 3.5.1. As such, this is a condition prohibited by Technical Specifications and is being reported in accordance with 10 CFR 50. 73(a)(2)(i)(B).
The cause is still under investigation. Corrective actions will be determined following completion of the cause analysis. Causal and corrective action information will be provided in a supplement to this Licensee Event Report (LER).
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
Unit 1 - Mode 1, approximately 100 percent Rated Thermal Power Unit 2 - Mode 1, approximately 100 percent Rated Thermal Power 2017
- - 010 There were no structures, systems, or components that were inoperable at the start of the event that contributed to the event.
EVENT DESCRIPTION
- - 00 Susquehanna Steam Electric Station (SSES) had been utilizing Barton 288A switches in the Reactor Steam Dome Pressure-Low channels that provide the injection permissive for the Core Spray system [EllS System Identifier: BM] (Technical Specification (TS) Function 1 d) and the Low Pressure Coolant Injection system (LPCI) [EllS System Identifier: BO] (TS Function 2d). In order to address drift issues with the Barton pressure switches, all eight were replaced with GE recommended Cameron 288A pressure switches between September 6, 2017 and November 15, 2017. The switches were bench tested prior to installation and calibration checked at the time of installation. Subsequent calibration checks were performed at intervals less than the quarterly Technical Specification (TS) required calibrations. During these subsequent calibration checks, the Unit 2 "C" (PIS-B21-2N021 C) and Unit 2 "D" (PIS-B21-2N021 D) pressure switches, were found outside of the Technical Specification (TS) allowable value. A timeline of events is as follows:
On September 20, 2017, the obsolete Barton 288A pressure switch for PIS-B21-2N021C was replaced with a GE recommended Cameron 288A pressure switch.
On October 9 2017 the obsolete Barton 288A pressure switch for PIS-B21-2N021 D was replaced with aGE recommended Cameron 288A pressure switch.
On October 20, 2017, PIS-B21-2N021C and PIS-B21-2N021 D were calibration checked. PIS-B21-2N021C had drifted to 454 pounds per square inch (psi), which was within the TS allowable value (upper allowable value of 454.4 psi). PIS-B21-2N021 C was adjusted to a value of 441.4 psi. PIS-B21 -2N021 D had drifted to 447.8 psi, which was within the TS allowable value (upper allowable value of 455 psi). PIS-B21-2N021 D was adjusted to a value of 444.1 psi.
On December 5, 2017, PIS-B21-2N021C and PIS-B21-2N021 D were found outside of the TS allowable value during the calibration check. Both drifted outside of the upper allowable value which is intended to ensure that the reactor dome pressure has fallen to a value below the Core Spray and RHR/LPCI maximum design pressures to preclude over-pressurization of the low pressure systems prior to low pressure injection initiation. PIS-B21-2N021C exceeded the TS allowable value by 1.4 psi (455.8 psi versus an upper allowable value of 454.4 psi). PIS-B21-2N021 D exceeded the TS allowable value by 2.8 psi (457.8 psi versus an upper allowable value of 455 psi). Both switches were adjusted to within the TS allowable value.
Although drift in the same manner was seen in the other six switches, none of the others were observed to have drifted outside of the TS allowable value during any of the subsequent calibration checks.
Based on the information currently available, Susquehanna believes that the condition existed for longer than allowed by TS 3.3.5.1 and TS 3.5.1. As such, this is a condition prohibited by Technical Specifications and is being reported in accordance with 10 CFR 50. 73(a)(2)(i)(B). 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/r3{)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. LER NUMBER YEAR Susquehanna Steam Electric Station Unit 2 05000-0388 SEQUENTIAL NUMBER REV NO.
2017
- - 010
- - 00
CAUSE OF EVENT
The cause is still under investigation. Further information associated with the cause will be provided in a supplement to this LER.
ANALYSIS/SAFETY SIGNIFICANCE
Information concerning safety significance will be provided in a supplement to this LER.
CORRECTIVE ACTIONS
Corrective actions will be determined following completion of the cause analysis and will be provided in a supplement to this LER.
COMPON~NT FAILURE INFORMATION The switches that drifted are Cameron Model 288A pressure switches.
PREVIOUS SIMILAR EVENTS
LER 50-388(387)/2015-001-01, "Condition Prohibited by Technical Specifications Due to Drift of Reactor Pressure Steam Dome-Low Switches", dated February 10, 2016.
NRC FORM 3668 (04-2017)