09-20-2016 | On July 22, 2016, the 'A' Essential Services Chilled Water (ESCW) chiller tripped due to low oil pressure and was declared inoperable.
The cause was oil leakage from a recently replaced brass tube fitting connecting the high-pressure side of an oil pressure differential sensing line to the lubrication system. An equivalent stainless steel fitting was installed in place of the brass, and the 'A' ESCW chiller was then declared operable.
This failed brass fitting was a recently installed like-for-like replacement component following a similar 'A' ESCW chiller trip on July 15, 2016, caused by low oil pressure as a result of leakage through the original brass tube fitting.
The cause of the failed tube fitting was fatigue crack growth resulting from vibration, with stress corrosion cracking having a secondary role. The material was replaced with stainless steel, and further analysis to address the vibration is ongoing. |
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Category:Letter
MONTHYEARIR 05000400/20240032024-11-0707 November 2024 Integrated Inspection Report 05000400/2024003 ML24290A1102024-10-24024 October 2024 Notification of Licensed Operator Initial Examination 05000400/2025301 05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-Out2024-10-23023 October 2024 Automatic Reactor Trip Due to Main Generator Lock-Out IR 05000400/20240112024-09-10010 September 2024 NRC Inspection Report 05000400/2024011 IR 05000400/20240052024-08-26026 August 2024 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400-2024005) Rev 1 ML24059A4252024-08-14014 August 2024 Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications ML24213A0522024-08-0202 August 2024 Issuance of Amendment No. 201 to Extend Completion Time of Inoperable Reactor Coolant System Accumulator Using Consolidated Line Item Improvement Process ML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000400/20240022024-07-29029 July 2024 – Integrated Inspection Report 05000400/2024002 ML24170A7312024-07-29029 July 2024 – Exemption from the Requirements of 10 CFR 50.55a(H)(2) Using the Risk-Informed Process for Evaluations Letter 05000400/LER-2024-001, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000400/20243022024-06-27027 June 2024 – NRC Operator Licensing Examination Approval 05000400/2024302 IR 05000400/20244012024-06-25025 June 2024 – Security Baseline Inspection Report05000400/2024401 ML24162A1372024-06-24024 June 2024 – Regulatory Audit Summary Related to the Review of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2)(EPID L-2024-LLE-00040) ML24136A1382024-05-20020 May 2024 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2024011) and Request for Information (RFI) ML24116A2592024-05-14014 May 2024 Staff Evaluation Related to Aging Management Plan and Inspection Plan for Reactor Vessel Internals ML24127A1592024-05-0808 May 2024 – Notification of Licensed Operator Initial Examination 05000400/2024302 IR 05000400/20240012024-05-0505 May 2024 Integrated Inspection Report 05000400/2024001 ML24100A0912024-04-10010 April 2024 Operator License Examination Report ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) IR 05000400/20230062024-02-28028 February 2024 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2023006 ML24032A2632024-02-23023 February 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0044 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter 05000400/LER-2022-006-02, Auxiliary Feedwater Pump Inoperability2023-07-11011 July 2023 Auxiliary Feedwater Pump Inoperability IR 05000400/20243012023-05-15015 May 2023 – Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 – Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 05000400/LER-1922-006-01, Auxiliary Feedwater Pump Inoperability2023-03-10010 March 2023 Auxiliary Feedwater Pump Inoperability ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 05000400/LER-2022-007-01, Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus2023-01-26026 January 2023 Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) 05000400/LER-2022-007, Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus2022-12-20020 December 2022 Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus 2024-09-10
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-Out2024-10-23023 October 2024 Automatic Reactor Trip Due to Main Generator Lock-Out 05000400/LER-2024-001, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out 05000400/LER-2022-006-02, Auxiliary Feedwater Pump Inoperability2023-07-11011 July 2023 Auxiliary Feedwater Pump Inoperability 05000400/LER-1922-006-01, Auxiliary Feedwater Pump Inoperability2023-03-10010 March 2023 Auxiliary Feedwater Pump Inoperability 05000400/LER-2022-007-01, Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus2023-01-26026 January 2023 Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus 05000400/LER-2022-006, Auxiliary Feedwater Pump Inoperability2022-12-20020 December 2022 Auxiliary Feedwater Pump Inoperability 05000400/LER-2022-007, Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus2022-12-20020 December 2022 Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus 05000400/LER-2022-008, Automatic Actuation of Auxiliary Feedwater System2022-12-19019 December 2022 Automatic Actuation of Auxiliary Feedwater System 05000400/LER-2022-005-01, Manual Reactor Trip Due to B Condensate Pump Motor Failure2022-11-28028 November 2022 Manual Reactor Trip Due to B Condensate Pump Motor Failure 05000400/LER-2022-005, Manual Reactor Trip Due to B Condensate Pump Motor Failure2022-10-21021 October 2022 Manual Reactor Trip Due to B Condensate Pump Motor Failure 05000400/LER-2022-004, Both Trains of High Head Safety Injection Inoperable2022-06-30030 June 2022 Both Trains of High Head Safety Injection Inoperable 05000400/LER-2022-003, Manual Reactor Trip Due to Degrading Condenser Vacuum2022-06-28028 June 2022 Manual Reactor Trip Due to Degrading Condenser Vacuum 05000400/LER-2022-001, Essential Services Chilled Water Chiller Inoperable Due to Pre-Rotation Vane Actuator Control Arm Position2022-03-10010 March 2022 Essential Services Chilled Water Chiller Inoperable Due to Pre-Rotation Vane Actuator Control Arm Position 05000400/LER-2021-005, Past Inoperability of Effluent Accident Monitor Exceeded Time Allowed by Technical Specifications2021-08-23023 August 2021 Past Inoperability of Effluent Accident Monitor Exceeded Time Allowed by Technical Specifications 05000400/LER-2021-004, Pressurizer Safety Valve Lift Setpoint Drifted Outside of Technical Specification Tolerance2021-06-21021 June 2021 Pressurizer Safety Valve Lift Setpoint Drifted Outside of Technical Specification Tolerance 05000400/LER-2021-002-01, Re All ECCS Accumulator Isolation Valves Closed in Mode 3 with RCS Pressure Greater than 1000 Psig2021-03-15015 March 2021 Re All ECCS Accumulator Isolation Valves Closed in Mode 3 with RCS Pressure Greater than 1000 Psig 05000400/LER-2021-001, Automatic Reactor Trip Due to Faults on Non-Segregated Bus from Unit Auxiliary Transformer 1B2021-02-16016 February 2021 Automatic Reactor Trip Due to Faults on Non-Segregated Bus from Unit Auxiliary Transformer 1B 05000400/LER-2021-002, All ECCS Accumulator Isolation Valves Closed in Mode 3 with RCS Pressure Greater than 1000 Psig2021-02-15015 February 2021 All ECCS Accumulator Isolation Valves Closed in Mode 3 with RCS Pressure Greater than 1000 Psig 05000400/LER-2020-002, Re Manual Reactor Trip Due to Control Rod Drop During Surveillance Testing2020-10-12012 October 2020 Re Manual Reactor Trip Due to Control Rod Drop During Surveillance Testing 05000400/LER-2020-001-01, Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance2020-06-29029 June 2020 Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance 05000400/LER-2020-001, Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance2020-05-21021 May 2020 Automatic Reactor Trip During Turbine Control System Digital Electro-Hydraulic System Maintenance 05000400/LER-2019-003, Both Source Range Nuclear Instruments Inoperable2019-12-12012 December 2019 Both Source Range Nuclear Instruments Inoperable 05000400/LER-2016-0072017-02-0909 February 2017 Containment Spray System Valve Actuation, LER 16-007-01 for Shearon Harris Unit 1, Regarding Containment Spray System Valve Actuation 05000400/LER-2016-0062016-12-14014 December 2016 Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void, LER 16-006-00 For Shearon Harris Nuclear Plant, Unit 1 Regarding Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void 05000400/LER-2016-0042016-12-0707 December 2016 Reactor Trip and Safety Injection During Turbine Control Testing at Low Power, LER 16-004-00 for Shearon Harris, Unit 1, Regarding Reactor Trip and Safety Injection During Turbine Control Testing at Low Power 05000400/LER-2016-0052016-12-0707 December 2016 Offsite Power Undervoltage Caused Actuation of Several Systems, LER 16-005-00 for Shearon Harris Nuclear Power Plant, Unit 1 Regarding Offsite Power Undervoltage Caused Actuation of Several Systems 05000400/LER-2016-0022016-09-19019 September 2016 'A' Essential Services Chilled Water Chiller Trip due to Oil Leak from Failed Tube Fitting, LER 16-002-00 for Shearon Harris, Unit 1, Regarding 'A' Essential Services Chilled Water Chiller Trip Due to Oil Leak from Failed Tube Fitting 05000400/LER-2016-0012016-09-0101 September 2016 Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions, LER 16-001-00 for Shearon Harris, Unit 1, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions ML1015505742010-01-12012 January 2010 Event Notification for Harris on Offsite Notification Due to Discovery of Tritium in Water Leakage Onsite 2024-07-22
[Table view] |
comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), 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.
05000- Shearon Harris Nuclear Power Plant - Unit 1 400 Note: Energy Industry Identification System (EIIS) codes are identified in the text within brackets [ ].
A. Background
Event Date: July 22, 2016 Mode: 1 Reactor Power: 100 percent No Structures, Systems or Components (SSCs) were inoperable at the start of this event that contributed to the event. No change in plant mode or in reactor power occurred as a result of this event.
On July 15, 2016, the 'A' train Essential Services Chilled Water (ESCW) [KM] chiller [CHU] tripped due to low oil pressure.
An oil leak was identified at a brass tube fitting [PSF] connecting the high-pressure side of an oil pressure differential sensing line to the lubrication system, and the chiller was declared inoperable. The leaking fitting had been in service for over 10 years, and was replaced with a like-for-like component. The chiller was declared operable on July 16, 2016.
The failed component was the 'A' train Essential Services Chilled Water chiller, oil pressure differential sensing line tube fitting, high pressure side, manufactured by Swagelok, Part Number B-600-1-4.
B. Event Description
On July 22, 2016, the 'A' ESCW chiller tripped a second time due to low oil pressure, with the cause being additional oil leakage from the replaced tube fitting. The 'A' ESCW chiller was again declared inoperable. Vibrations were identified on the oil pressure differential sensing line. An equivalent stainless steel fitting was installed in place of the brass. The 'A' ESCW chiller was then declared operable.
Metallurgical analysis of both failed fittings was conducted. Stress corrosion cracking was identified in the first fitting, which contributed significantly to the overall failure and was the initiation site of the fatigue failure. However, the failure of the second fitting was dominated by fatigue, with possible signs of stress corrosion cracking in some locations. Thus, cyclic stress-driven fatigue is considered the primary cause of failure, with stress corrosion cracking having a secondary role. After the second failure, a notable vibration was discovered in the oil pressure differential sensing line, likely driving the fatigue.
This condition is reportable as a condition prohibited by Technical Specification (TS) per 10 CFR 50.73(a)(2)(i)(B). The second fitting failed short of the 30-day mission time of the ESCW system and after the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement time for the applicable ESCW TS Limiting Condition for Operability. The vibrations in the sensing line were likely present when the second fitting was installed after the July 15 failure, as demonstrated by the failure of the first fitting. Thus, the ESCW system was inoperable for longer than permitted by TS, making the July 22, 2016, event reportable.
C. Causal Factor The cause of the failed tube fitting was fatigue crack growth resulting from vibration, with stress corrosion cracking having a secondary role.
comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S.Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource(nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, 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.
05000- Shearon Harris Nuclear Power Plant - Unit 1 400
D. Safety Analysis
No loss of safety function occurred during the event. The `B' ESCW chiller was available throughout the specified period to perform the credited safety function. Thus, the failure of the 'A' ESCW chiller has very low safety significance. At no point during the impacted period was the ESCW system required to mitigate the effects of a Design Basis Accident. Thus, there is no consequence to the health and safety of site personnel or to the public.
E. Corrective Actions
Corrective Actions Completed:
The failed tube fitting was replaced with an equivalent stainless steel fitting. This stainless steel fitting is not as susceptible to stress corrosion cracking in this environment and has higher endurance limits/fatigue strength.
Corrective Actions Planned:
Additional analysis is underway to address the vibrations present on the oil pressure differential sensing line of the 'A' ESCW Chiller.
F. Additional Information:
There have been no previous Licensee Event Reports at Harris due to a tripped ESCW Chiller from oil leakage through a tube fitting due to fatigue failure.
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05000400/LER-2016-001 | Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions LER 16-001-00 for Shearon Harris, Unit 1, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000400/LER-2016-002 | 'A' Essential Services Chilled Water Chiller Trip due to Oil Leak from Failed Tube Fitting LER 16-002-00 for Shearon Harris, Unit 1, Regarding 'A' Essential Services Chilled Water Chiller Trip Due to Oil Leak from Failed Tube Fitting | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000400/LER-2016-003 | Containment High-Range Radiation Monitors Declared Inoperable Due to Potential for Temperature Induced Current | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000400/LER-2016-004 | Reactor Trip and Safety Injection During Turbine Control Testing at Low Power LER 16-004-00 for Shearon Harris, Unit 1, Regarding Reactor Trip and Safety Injection During Turbine Control Testing at Low Power | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000400/LER-2016-005 | Offsite Power Undervoltage Caused Actuation of Several Systems LER 16-005-00 for Shearon Harris Nuclear Power Plant, Unit 1 Regarding Offsite Power Undervoltage Caused Actuation of Several Systems | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000400/LER-2016-006 | Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void LER 16-006-00 For Shearon Harris Nuclear Plant, Unit 1 Regarding Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000400/LER-2016-007 | Containment Spray System Valve Actuation LER 16-007-01 for Shearon Harris Unit 1, Regarding Containment Spray System Valve Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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