05000387/LER-2022-001, Main Steam Isolation Valve Leakage
| ML22152A249 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/01/2022 |
| From: | Cimorelli K Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 2022-001-00 | |
| Download: ML22152A249 (3) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3872022001R00 - NRC Website | |
text
June 1, 2022 Kevin Cimorelli Site Vice President Attn: Document Control Desk U.S. Nuclear Regulatory Commission 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 50-387/2022-001-00 UNIT 1 LICENSE NO. NPF-14 PLA-8002 TALEN~.
ENERGY 10 CPR 50.73 Docket No. 50-387 Attached is Licensee Event Report (LER) 50-387/2022-001-00. The LER reports an event involving inoperability of a Main Steam Line Isolation Valve (MSIV) that was determined to be rep01iable in accordance with 10 CPR 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 or revised regulatory commitments.
K. Cimorelli Attachment: LER 50-387/2022-001-00 Copy:
NRC Region I Mr. C. Highley, NRC Senior Resident Inspector Ms. A. Klett, NRC Project Manager Mr. M. Shields, PA DEP/BRP
Abstract
On April 02, 2022, during Local Leak Rate Testing (LLRT) conducted during the Unit 1 refueling outage, as-found leakage through the inboard Main Steam Isolation Valve (MSIV) (HV141 F022B) was 107,133 standard cubic centimeters per minute (seem) which exceeded the Technical Specification (TS) 3.6.1.3 limit of 100 standard cubic feet per hour (47,194 seem) for individual valve leakage.
Based on preliminary information, there is evidence that the condition existed during the last operating cycle for longer than allowed by TS 3.6.1.3. The condition is being reported in accordance with 1 O CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
The cause of the event is under investigation and will be provided in a supplement to this report. Repairs to the valve resulted in an acceptable as-left LLRT value. Additional corrective actions, as applicable, will be reported in the supplement. There were no actual consequences to the health and safety of the public as a result of this event.
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3160-0104 EXPIRES: 08/31/2023
- 3. LER NUMBER Susquehanna Steam Electric Station, Unit 1
NARRATIVE
05000-387
CONDITIONS PRIOR TO EVENT
Unit 1 - Mode 5, approximately O percent Rated Thermal Power (RTP)
Unit 2 - Mode 1, approximately 100 percent RTP
EVENT DESCRIPTION
YEAR 2022 SEQUENTIAL NUMBER 001 REV NO.
00 On April 02, 2022, during Local Leak Rate Testing (LLRT) conducted during the Unit 1 refueling outage, as-found leakage through the inboard Main Steam Isolation Valve (MSIV) (HV141F022B) [EIIS System/Component Code: SB/ISV] was 107,133 standard cubic centimeters per minute (seem) which exceeded the Technical Specification (TS) 3.6.1.3 limit of 100 standard cubic feet per hour (47,194 seem) for individual valve leakage.
HV141 F022B was repaired resulting in an as-left individual valve LLRT value of 39,750 seem.
Based on preliminary information, there is evidence that the condition existed during the last operating cycle for longer than allowed by TS 3.6.1.3. The condition is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications.
CAUSE OF EVENT
The cause of the event is under investigation and will be provided in a supplement to this LER.
ANALYSIS/SAFETY SIGNIFICANCE
Analysis/Safety significance will be provided in a supplement to this LER.
CORRECTIVE ACTIONS
HV141 F022B was repaired resulting in a leak rate within TS 3.6.1.3 allowable value. Any additional corrective actions will be provided in a supplement to this LER.
COMPONENT FAILURE INFORMATION
Component Identification - HV141 F022B Component Name - Unit 1 Main Steam Line 'B' Inboard Isolation Valve Valve Manufacturer - Atwood & Morrill Co.
Valve Type - Wye Globe Valve Size - 26" Actuator Manufacturer - S&P Actuator Type - Tandem Cylinder
PREVIOUS OCCURRENCES
Previous occurrences, if any, will be provided in a supplement to this LER. Page.l. of.l.