05000370/LER-2017-001

From kanterella
Jump to: navigation, search
LER-2017-001, Technical Specification Required Shutdown Due to Reactor Coolant System Leakage
Mcguire Nuclear Station, Unit 2
Event date: 02-23-2017
Report date: 06-26-2017
Reporting criterion: 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
Initial Reporting
LER closed by
IR 05000369/2017003 (1 November 2017)
3702017001R01 - NRC Website
LER 17-001-01 for McGuire, Unit 2, Regarding Technical Specification Required Shutdown Due to Reactor Coolant System Leakaqe
ML17184A147
Person / Time
Site: McGuire Duke energy icon.png
Issue date: 06/26/2017
From: Capps S D
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
MNS-17-027
Download: ML17184A147 (7)


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 used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

McGuire Nuclear Station, Unit 2 05000-0370 2017 -01 -01

BACKGROUND

Applicable Energy Industry Identification [EIIS] system and component codes are enclosed within brackets.

McGuire-specific system and component identifiers are contained within parentheses.

Safety Injection System [BQ](NI):

The NI system is designed to provide Emergency Core Cooling for the Reactor Coolant System [AB](NC) in order to prevent fuel clad melting to assure that the core remains in place and substantially intact in case of an accident. Each unit's NI system contains an "A" and "B" train pump that both actuate automatically upon a safety injection signal following low pressurizer pressure or high containment pressure. A common NI header in containment splits into four 1.5 inch nominal diameter lines each going into 2A, 2B, 2C and 2D NC Cold Legs. Each of these NI lines has two check valves and one normally opened upstream isolation valve in series.

Chemical and Volume Control System [CB](NV):

The NV system is designed to maintain required water inventory in the NC system; maintain seal-water injection flow to the reactor coolant pumps; control water chemistry conditions; and provide emergency core cooling (part of the system shares piping with the NI system).

The event was reported per 10 CFR 50.72(b)(2)(i) for "The initiation of any nuclear plant shutdown required by the plant's Technical Specifications" and 10 CFR 50.72(b)(3)(ii)(A) for "Any event or condition that results in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded." An Emergency Notification System report was made to the Nuclear Regulatory Commission (NRC) on February 23, 2017, at 22:01 hours. A Licensee Event Report (LER) is also required due to the condition of a nuclear plant, including its principle safety barriers, being seriously degraded (10 CFR 50.73(a)(2)(ii)(A)), the completion of a nuclear plant shutdown required by Technical Specifications (10 CFR 50.73(a)(2)(i)(A)), and an operation or condition prohibited by Technical Specifications (10 CFR 50.73(a)(2)(i)(B)). The associated Technical Specification is 3.4.13, "Reactor Coolant System Operational Leakage.

The 2D NI pipe was replaced during the spring 2014 Unit 2 refueling outage following discovery of a rejectable indication at the pipe to NC nozzle weld. LER 370/2014-01 was submitted and details this event. Corrective actions included the removal of a valve deemed susceptible to leak-by, which can introduce cold water to the NI pipe in question. This pipe receives an inspection each refueling outage per Electric Power Research Institute's Materials Reliability Program MRP-146, "Management of Thermal Fatigue in Normally Stagnant Non-Isolable Reactor Coolant System Branch Lines." This same pipe was inspected during the fall 2015 Unit 2 refueling outage and no reportable indications were identified.

2NC-30 is a three-quarter inch manually operated, Flowserve, Y-Globe, bellows seal design Pressurizer Spray Bypass Valve. Boron was identified at 2NC-30 while conducting a Mode 3 walk down at full temperature and pressure during the spring 2014 Unit 2 refueling outage. The valve was cleaned and the boron was determined to be from an inactive leak. The valve was examined again during the fall 2015 Unit 2 refueling outage and no leaks were identified.

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 used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

McGuire Nuclear Station, Unit 2 05000-0370 2017 - 01 - 01 No significant structures, systems, or components were out of service at the time of discovery that contributed to the event.

EVENT DESCRIPTION:

On February 23, 2017, at 19:22 hours, with Unit 1 and Unit 2 at approximately 100 percent power, operators commenced a Unit 2 shutdown upon discovery of pressure boundary leakage on Unit 2 NI pipe upstream of the connection to "D" NC Cold Leg. Subsequent investigation revealed the source of the leak to be a through wall crack on the inside of a bend in the pipe just upstream of the nozzle to the Cold Leg. The leak was approximately 5.75 inches from the nozzle. The indication was open to the surface for a dimension of approximately 0.6 inch of length.

During a containment walk down inspection in Mode 3 on the next day, a pinhole pressure boundary leak was observed in the body of valve 2NC-30.

The relevant sequence of events, with dates and approximate times of occurrence, is as follows:

2/23/17 19:22 Commenced Unit 2 shutdown from 100% upon identification of pressure boundary leakage 2/23/17 22:00 Reported to the NRC (Event Number 52573) 2/24/17 00:41 Unit 2 entered Mode 3 2/24/17 16:11 Identified 2NC-30 leak 2/24/17 17:21 Unit 2 entered Mode 5 3/2/17 15:56 Completed replacement of 2NC-30 3/3/17 10:30 Received NRC's verbal approval for alternative repair of NI pipe (Relief Request 17-MN-001) 3/5/17 11:01 Completed NI pipe repair by weld overlay 3/8/17 16:46 Unit 2 entered Mode 1

CAUSAL FACTORS:

The cause of the NI pipe leak is thermal fatigue damage resulting from NC cross-loop flows. Cross-flow was detected between the 2B NC loop and the 2D NC loop through the shared NI lines. This is an unanticipated mode of thermal cycling that is not addressed by MRP-146 and is different from the cause documented in LER 370/2014-01.

The cause evaluation of the 2NC-30 leak identified the cause as a casting flaw attributed to a combination of defects during the manufacturing process that resulted in a through wall pinhole leak in the valve body. At the leak site, substantial amounts of interdendritic porosity were concentrated near the ID and OD surfaces. In addition, elemental segregation (silicon in particular) was identified, and numerous, short, oxide-filled, intermittent, circumferential cracks were present within, and extending from, the regions of clustered porosity.

All of the cracks exhibited features consistent with casting flaws (i.e., they were not service-related). The interdendritic porosity in addition to the random silicon presence allowed the crack to form, creating this unique and isolated casting flaw. The Metallurgical Laboratory analysis and results showed that the valve did not 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 used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

McGuire Nuclear Station, Unit 2 05000-0370 2017 -01 -01 have any erosion damage present. Due to the random nature of the casting flaw, there is no implication on extent of condition.

CORRECTIVE ACTIONS:

Immediate:

1. Replaced valve 2NC-30.

2. Repaired 2D NI pipe using weld overlay.

Subsequent:

1. Installed strap-on thermocouples/accelerometer on 2D NI piping to monitor temperature and vibration.

2. Replaced 2D NI pipe.

3. Installed a bleed line off of the common NI header to preclude cross-leakage between the NI pipe connections to the NC loops.

4. Installed temperature monitoring devices on susceptible lines.

5. Replaced 2B NI line check valves.

Planned:

1. Install during the next Unit 1 refueling outage thermocouples on key Unit 1 MRP-146 locations to monitor thermal cycling conditions (extent of condition).

2. Install during the next Unit 1 refueling outage a pressure bleed line associated with the Unit 1 common NI header to mitigate the effect of in-leakage to the NI lines (extent of condition).

SAFETY ANALYSIS:

The NI line to 2D NC Cold Leg is dedicated for emergency injection only, and it is generally stagnant during normal plant operation. The leak in this line remained small, and an orderly shutdoWn was performed. The leak was much less than what is considered in the Probabilistic Risk Analysis (PRA) Loss Of Coolant Accident (LOCA) analysis. However, an un-isolable leak in the NC pressure boundary constitutes degradation of a principal safety barrier and is reportable to the NRC.

The finite element analysis results support that if the 1.5 inch NI pipe was subjected to any and all applicable primary design loads — including gravity, LOCA, Safe Shutdown Earthquake inertia and Seismic Anchor Motions — during the time in which it contained the through-wall defect up until the point where it was repaired with weld overlay, the remaining cross-section of the pipe would have remained intact and would not have 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 used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

McGuire Nuclear Station, Unit 2 05000-0370 2017 -01 -01 experienced significant plastic deformation. Additionally, had the leak location failed catastrophically, the pipe break would have constituted a LOCA. Breaks at this location are bounded by analyses in the McGuire Updated Final Safety Analysis Report which concludes that they can be handled without core damage.

The pinhole leak in 2NC-30 was a minor pressure boundary leak, it did not impact unit operation, and was a negligible contribution to the NC leakage calculation during unit operation.

ADDITIONAL INFORMATION:

A review of the McGuire corrective action program was conducted to determine whether this was a recurring event (i.e., similar event with the same cause code). No reactor coolant system pressure boundary through- body valve leaks due to casting flaws have been documented within the past five years. The cause of the 2014 LER was a legacy issue with leakage through valve 2NI-3 (Unit 2 NC Cold Leg Isolation), which created the thermal stratification condition in the 2D NI line. No instances of thermal fatigue caused by cross-loop flows in NI lines have been documented within the past five years. Therefore, this event is not considered a recurring event.