05000333/LER-2020-003-01, High Pressure Coolant Injection Inoperable Due to Oil Leak
| ML21251A585 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/08/2021 |
| From: | Timothy Peter Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-21-0082 LER 2020-003-01 | |
| Download: ML21251A585 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3332020003R01 - NRC Website | |
text
Exelon Generation JAFP-21-0082 September 8, 2021 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 James A. FitzPatrick NPP P 0 Box 110 Lycoming. NY 13093 Timothy C. Peter Site Vice President-JAF James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-059 NRC Docket No. 50-333
Subject:
Reference:
Dear Sir or Madam:
LER: 2020-003-01, High Pressure Coolant Injection Inoperable due to Oil Leak FitzPatrick letter, LER: 2020-003, High Pressure Coolant Injection Inoperable due to Oil Leak, JAFP-20-0042, dated June 9, 2020 This report is supplement 1 to Licensee Event Report (LER) submitted by the Reference. This report is being submitted pursuant to 50.73(a)(2)(v)(D) and 50.73(a)(2)(i)(B). This LER revision is being submitted to include reference to reporting criterion 50.73(a)(2)(i)(B) for Operation or Condition Prohibited by Technical Specifications (TS) and include more information in the Event Analysis section. Subsequent analysis of the event determined the High Pressure Coolant Injection (HPCI) system was inoperable for a longer period than allowed by Technical Specifications 3.5.1.
There are no new regulatory commitments contained in this report.
Questions concerning this report may be addressed to Mr. Richard Sullivan, Regulatory Assurance Manager, at (315) 349-6562.
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Enclosure:
LER: 2020-003-01, High Pressure Coolant Injection Inoperable due to Oil Leak cc:
USNRC, Region I Administrator USNRC, Project Manager USNRC, Resident Inspector INPO Records Center (IRIS)
NRC FORM 366 (08-2020)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (08-2020)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023
- 1. Facility Name James A. FitzPatrick Nuclear Power Plant
- 2. Docket Number 05000333
- 3. Page 1 OF 3
- 4. Title High Pressure Coolant Injection Inoperable due to Oil Leak
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved
Month
Day
Year
Year Sequential Number Revision No.
Month Day Year Facility Name N/A Docket Number N/A 04 10 2020 2020 - 003 - 01 09 08 2021 Facility Name N/A Docket Number N/A
- 9. Operating Mode 1
- 10. Power Level 100 Month Day Year No Yes (If yes, complete 15. Expected Submission date)
Abstract (Limit to 1560 spaces, i.e., approximately 15 single-spaced typewritten lines)
On April 10, 2020 at 0300, an oil leak from 23PCV-12, HPCI Trip System Pressure Control Valve (PCV) resulted in the system being declared inoperable. This condition is being reported as a condition that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident per 10 CFR 50.73(a)(2)(v)(D) and for a period longer than allowed by Technical Specification 3.5.1 per 10 CFR 50.73(a)(2)(i)(B).
Corrective action to replace valve 23PCV-12 was completed and system was restored to service at time 2015 on April 10, 2020.
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
(See Page 3 for required number of digits/characters for each block)
LICENSEE EVENT REPORT (LER)
=
Background===
The High Pressure Coolant Injection (HPCI) System [EIIS Identifier: BJ] is part of the Emergency Core Cooling System (ECCS); HPCI provides and maintains an adequate coolant inventory inside the Reactor Pressure Vessel [RPV] to prevent damage to the reactor core under postulated accident scenarios. The system is comprised of various components which include a turbine, pumps, valves, piping, and instrumentation. The HPCI System may be initiated by automatic or manual means.
The HPCI turbine oil system provides for lubrication and cooling of the equipment bearings and other accessories. The oil system also provides control and hydraulic oil to the turbine governor system. Loss of oil pressure to the turbine governor system will cause the steam supply stop valve and turbine control valve to go shut, securing steam to the turbine. The HPCI oil system is not normally pressurized, the system is only pressurized during operational checks of the system and during actual system operation.
Event Description
While conducting a HPCI monthly operability test (ST-4B), a control oil leak was observed from 23PCV-12.
The oil leak is only visible when the oil system is pressurized. Initial leakage rate was estimated at approximately 0.1 gallons per minute. To confirm leak location and validate leak rate, the auxiliary oil pump was restarted. With system oil pressure reestablished, the leak rate was determined to have degraded such that the capability of the HPCI system to meet mission time would be challenged.
Event Analysis
Level in the HPCI Oil Tank provides net positive suction head (NPSH) to the suctions of the oil pumps for the duration of HPCI mission time. Loss of NPSH to the suction of HPCI Main Lube Oil Pump (23P-1MO) and the HPCI Turbine Aux. Lube Oil Pump (23P-150) will result in a loss of oil pressure to the system bearings and system control valves. Oil pressure is required for operation of the HPCI Turbine Steam Supply Stop Valve (23HOV-1) and HPCI Turbine Control Valve (23HOV-2). Loss of bearing cooling and oil pressure for the stop and control valves would have limited HPCI operation and challenged the capability of the HPCI system to meet its mission time. 23PCV-12 was installed on December 16, 2017. It was identified that this PCV had a vulnerability associated with the HPCI system oil PCV actuator diaphragm due to a manufacturing error, as reported by General Electric-Hitachi MFN 10-192. This error resulted in inadequate fabric reinforcement that is critical to ensure durability and reliability of the diaphragm, preventing tearing of the diaphragm. The failure of 23PCV-12 diaphragm would result in a loss of HPCI system turbine lubricating and control oil through the failed diaphragm. This condition is reportable under 10 CFR 50.73(a)(2)(v)(D), Event or Condition that Could Have Prevented Fulfillment of a Safety Function.
Due to the cyclic failure mechanism of the diaphragm, HPCI was inoperable longer than allowed by Technical Specifications (TS) 3.5.1, ECCS Operating. TS 3.5.1 Condition C requires HPCI System be restored to Operable within 14 days or, Condition G, be in Mode 3 and reduce reactor steam dome pressure to 150 psig within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This represents a condition prohibited by Tech Spec and reportable in accordance with 10 CFR 50.73(a)(2)(i)(B).
Cause
The cause was determined to be a tear in the 23PCV-12 control valve diaphragm, allowing a loss of control oil from the system. U.S. NUCLEAR REGULATORY COMMISSION (08-2020)
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023
- 3. LER NUMBER James A. FitzPatrick Nuclear Power Plant 05000 - 333 YEAR SEQUENTIAL NUMBER REV N0.
2020
- - 003
- - 01 Page 3 of 3 (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
Similar Events
Previous LER: None identified.
FAILED COMPONENT IDENTIFICATION:
Manufacturer:
Robertshaw Manufacturer Model Number:
VC-210 NPRDS Manufacturer Code:
R290 NPRDS Component Code:
PCV FitzPatrick Component ID:
Completed Corrective Actions
Valve 23PCV-12 was replaced. Additional corrective actions are documented in the Corrective Action Program.
Safety Significance
Nuclear Safety - The failure of the HPCI turbine over-speed reset control valve diaphragm would result in a loss of HPCI turbine lubricating oil and control oil during HPIC oil system operation. Depending on the amount of oil lost and system demands, the leakage may have prevented the HPCI from meeting system specified mission time.
Industrial safety - No actual or potential industrial safety consequences resulted from this event.
Radiological safety - No actual radiological impact is associated with this event.
References Issue Report - IR 04334315, HPCI Oil Leak, dated April 10, 2020 Issue Report - IR 04397491, NRC NCV 05000333/2020012-01, Defective Part HPIC PCV Failure, dated January 22, 2021 ENS 54657, issued 4/10/2020 Part 21 Reportable Condition Notification: Failure of HPCI Turbine Overspeed Reset Control Valve Diaphragm, MFN 10-192, dated July 1, 2010