05000333/LER-2022-002, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation
| ML22327A241 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/22/2022 |
| From: | Timothy Peter Constellation Energy Group |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| JAFP-22-0048 LER 2022-002-00 | |
| Download: ML22327A241 (1) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 3332022002R00 - NRC Website | |
text
Constellation JAFP-22-0048 November 22, 2022 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 James A. FitzPatrick NPP P.O 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:
Dear Sir or Madam:
LER: 2022-002-00, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation This report is being submitted pursuant to 10 CFR 50. 73(a)(2)(iv)(A).
There are no new regulatory commitments contained in this report.
Questions concerning this report may be addressed to Mr. Mark Hawes, Regulatory Assurance Manager (Acting), at (315) 349-6659.
Sincerely,~~;,__----
~Peter Site Vice President TCP/MH/pa
Enclosure:
LER: 2022-002-00, Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation 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 Mode Switch Failed to Bypass Low Main Steam Line in Mode 2 Resulting in MSIV and RPS System Actuation
- 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 09 26 2022 2022 - 002 - 00 11 22 2022 Facility Name N/A Docket Number N/A
- 9. Operating Mode 2
- 10. Power Level 000 Month Day Year No Yes (If yes, complete 15. Expected Submission date) 01 31 2023 Abstract (Limit to 1560 spaces, i.e., approximately 15 single-spaced typewritten lines)
On September 26, 2022, at 0306 EDT, while the reactor was sub-critical and inserting control rods for a planned refueling outage, James A. FitzPatrick Nuclear Power Plant (JAF) experienced a reactor scram and Group 1 isolation on low steam line pressure logic. As a result of Group 1 isolation signal seven out of eight Main Steam Isolation Valves (MSIV) isolated. A outboard MSIV (29AOV-86A) failed to isolate on the initial signal. The Reactor Protection System (RPS) actuated, resulting in all control rods being fully inserted, and manual actuation of RCIC. This event is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A).
The cause of RPS actuation was determined to be a failure of the reactor mode switch (05A-S1) to enact the logic required to bypass MSIV isolation on low main steam line pressure and RPS actuation on MSIV closed position. A supplement report will be submitted when all corrective actions have been finalized.
(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)
Event Description
On September 26, 2022, James A. FitzPatrick Nuclear Power Plant (JAF) was reducing power for a planned plant shutdown for a refuel outage. At the time of the Scram, no structures, components, or systems were inoperable at the start of the event and contributed to the event. Control rods [EIIS identifier: AA] were being inserted and reactor power and pressure was decreasing.
At 0230, operators placed the mode switch (05A-S1) [JE] in Startup/Hot Standby (Mode 2).
At 0306, an unplanned Scram signal was received due to a Group 1 isolation on low main steam line [SB]
pressure.
All control rods were fully inserted. Main Steam Isolation Valves (MSIV) [SB] isolated except A outboard MSIV (29AOV-86A) failed to close. primary containment isolation system (PCIS) [JM] isolated valves in multiple systems according to group 1 isolation. When the PCIS was reset, 29AOV-86A was then manually isolated.
At 0530, Operators made the decision to place Reactor Core Isolation Cooling (RCIC) system [BN] in service to augment pressure and level to assist in transition to feedwater [SJ] and condensate [SD] systems. At 0751, RCIC was shut down and in a standby lineup.
The NRC was notified of this event at 0541 by ENS 56119 in accordance with 10 CFR 50.72(b)(2)(iv)(B)
Reactor Protection System (RPS) actuation while critical and 10 CFR 50.72(b)(3)(iv)(A) for systems actuation.
A reactor engineering analysis of reactor criticality was performed for the period of time prior to the event, and it was determined that the reactor was sub-critical. On October 4, 2022, ENS 56119 was updated to retract 10 CFR 50.72(b)(2)(iv)(B).
The A outboard MSIV (29AOV-86A) failed to close, but the safety function for A main steam line isolation was successful because the inboard MSIV isolated successfully.
Event Analysis
The Scram was initiated by an RPS actuation, which was initiated by MSIV closure, and MSIV isolation actuation was initiated by low main steam line pressure. The RPS actuation on MSIV closed position, and MSIV isolation on low main steam line pressure are not required to actuate in Mode 2 and should have been bypassed by mode switch position contacts. Mode 2 supports conditions at low reactor power, such as startup and shutdown, where the analyzed plant transient events for these required system actuations are not applicable.
The investigation confirmed the Mode Switch (05A-S1) was changed to Mode 2 by the Operator; however, some trip bypasses were not engaged. As the plant reduced power for the planned refuel outage, the un-bypassed trip setpoints actuated Group 1 isolation valves in multiple systems, including RPS, and MSIV system actuation. The automatic actuation of these systems and manual actuation of RCIC is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A). The Failure Modes Causal Team (FMCT) identified the most likely cause of failure of proper switch contacts make-up as performance of first-time preventative maintenance activity to inspect mode switch on operation. During this activity the mode switch was deliberately operated slowly to perform detailed inspection of switch components and gearing. This style of operation resulted in all contacts not making up properly when switch was operated. 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.
2022
- - 002
- - 00 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
No similar events were identified at JAF.
Corrective Actions
Completed Actions A Failure Mode Causal Team (FMCT) was formed to identify most likely causes and assist in completion of troubleshooting actions prior to plant start-up. During troubleshooting, no abnormal component degradation was identified when 05A-S1 was inspected. Prior to startup, 05A-S1 was tested satisfactorily.
Operating procedure OP-65 revision was completed prior to reactor start-up adding requirements to ensure when the mode switch position is changed the proper switch contact logic is validated by redundant indications.
29AOV-86A was repaired prior to startup with a new air pack and solenoid valve cluster assembly. The replaced items were sent to PowerLabs for failure analysis.
Planned Actions An investigation into the cause of 05A-S1 contacts not bypassing trip setpoints is ongoing and will be submitted as a supplement to this event report by January 31, 2023.
Safety Significance
There were no actual or potential nuclear or radiological consequences during this event.
Plant systems operated in response to this event as expected with the exception that a single component (29AOV-86A) of the MSIV system did not isolate. The redundant in inboard component fulfilled the safety function of the MSIV system. In addition, Safety/relief valves were not required to control pressure.
References Issue Report, IR 04524574, Reactor Scram from Mode 2 During Plant Shutdown, dated September 26, 2022 Issue Report, IR 04524581, A Outboard MSIV Failed to Close on GP 1 Isolation, dated September 26, 2022