05000387/LER-2019-002, Inoperability of C Emergency Service Water Pump
| ML19301C145 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/28/2019 |
| From: | Cimorelli K Susquehanna, Talen Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-7824 LER 2019-002-00 | |
| Download: ML19301C145 (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)(v), Loss of Safety Function |
| 3872019002R00 - NRC Website | |
text
OCT. 2 8 2019 Kevin Cimorelli 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. 570.542.3795 Fax 570.542.1504 Kevin.Cimorelli@TalenEnergy.com SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-387(388)/2019-002-00 UNIT 1 LICENSE NO. NPF-14 UNIT 2 LICENSE NO. NPF -22 PLA-7824 TALEN~
ENERGY 10 CPR 50.73 Docket No. 50-387 and 50-388 Attached is Licensee Event Report (LER) 50-387(388)/2019-002-00. This LER is reporting an event involving the "C" Emergency Service Water pump that was determined to be reportable in accordance with 10 CPR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications and 10 CPR 50.73(a)(2)(v) as an event or condition that could have prevented fulfillment of a safety function.
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.
K. Cimorelli Attachment: LER 50-387(388)/2019-002-00 Copy:
NRC Region I Ms. S. Goetz, NRC Project Manager Ms. L. H. Micewski, NRC Sr. Resident Inspector Mr. M. Shields, P A DEP/BRP
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018) f~~~M~t)~~rf>~
, the NRC may not conduct or sponsor, and a person is not required to resoond to the Information collection.
- 3. Page Susquehanna Steam Electric Station Unit 1 05000387 1 OF3
- 4. Title lnoperability of "C" Emergency Service Water Pump
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Sequential Rev Facility Name Docket Number Month Day Year Year Month Day Year Susquehanna Steam Electric Station Unit 2 Number No.
05000388 08 28 2019 2019 002 00 10 z.g 2019 Facility Name Docket Number N/A 05000
- 9. Operating Mode 12 20 2019 Abstract (Limit to 1400 spaces, i.e., approximately 14 single-spaced typewritten lines)
On August 28, 2019 at approximately 17:40, during lnservice Testing (1ST) of the "A" loop of Emergency Service Water (ESW), the differential pressure for the "C" ESW pump (OP504C) was found to be 88.875 psid, which was below the established 1ST acceptance criteria. Based on the test results, the "C" ESW pump was in the 1ST Required Action Range, which requires the pump to be declared inoperable. At the time of discovery of this condition, Susquehanna was already in Technical Specification (TS) 3.7.2 Condition C for "A" loop maintenance.
On August 29, 2019, the pump lift setting was adjusted and the "C" ESW pump was retested. The retest resulted in an acceptable differential pressure of 91.9 psid, which was in the Alert Range and no longer in the Required Action Range. TS 3.7.2 Condition C was exited on August 29, 2019 at approximately 15:45. On October 04, 2019, Susquehanna completed replacement of the "C" ESW pump. The removed pump had notable degradation.
Based on available information, the condition is considered to have existed for longer than allowed by TS 3.7.2.
The condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications and 10 CFR 50.73(a)(2)(v) as an event or condition that could have prevented fulfillment of a safety function.
Completed corrective actions include replacement of the "C" ESW pump. The cause of the event is under investigation and will be provided under a supplement to this LER with additional corrective actions.
There were no actual safety consequences associated with the condition.
NRC FORM 366 (04-2018)
CONDITIONS PRIOR TO EVENT
Unit 1 - Mode 1, approximately 100 percent Rated Thermal Power Unit 2 - Mode 1, approximately 100 percent Rated Thermal Power YEAR 2019 SEQUENTIAL NUMBER 002 There were no structures, systems, or components that were inoperable at the start of the event that contributed to the event.
EVENT DESCRIPTION
REV NO.
00 On August 28, 2019 at approximately 17:40, during lnservice Testing (IST) of the "A" loop of Emergency Service Water (ESW) [EllS System Code: Bl], the differential pressure for the "C" ESW pump (OP504C)
[EllS Component Code: P] was found to be 88.875 psid, which was below the established 1ST acceptance criteria. Based on the test results, the "C" ESW pump was in the 1ST Required Action Range, which requires the pump to be declared inoperable. At the time of discovery of this condition, Susquehanna was already in Technical Specification (TS) 3.7.2 Condition C for both units in support of maintenance activities on the "A" loop of ESW.
On August 29, 2019, the pump lift setting was adjusted and the "C" ESW pump was retested. The retest resulted in an acceptable differential pressure of 91.9 psid, which was in the Alert Range and no longer in the Required Action Range. TS 3.7.2 Condition C was exited on August 29, 2019 at approximately 15:45.
On October 04, 2019, Susquehanna completed replacement of the "C" ESW pump. The removed pump had notable degradation.
Based on available information, the condition is considered to have existed for longer than allowed by TS 3.7.2. The condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications and 10 CFR 50. 73(a)(2)(v) as an event or condition that could have prevented fulfillment of a safety function.
CAUSE OF EVENT
The cause of the event is still under investigation. A supplement will be issued to provide information on the final conclusions regarding the cause of the condition.
ANALYSIS/SAFETY SIGNIFICANCE
Safety significance information will be provided in the supplement to this LER. Page 2 of 3 (04-2018)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020
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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 Estimated burden per 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 Information Services Branch (T-2 F43), U. S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov,
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the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMS control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. LERNUMBER Susquehanna Steam Electric Station Unit 1 05000-387 YEAR 2019
CORRECTIVE ACTIONS
Key corrective actions include the following:
- 1. Susquehanna completed replacement of the "C" ESW pump on October 04, 2019.
Additional corrective actions will be provided in the supplement to this LER.
COMPONENT FAILURE INFORMATION
Component failure information will be provided in the supplement to this LER.
PREVIOUS OCCURENCES
Previous occurrences will be provided in the supplement to this LER. Page 3 of 3 SEQUENTIAL NUMBER 002 REV NO.
00