02-09-2017 | On October 26, 2016, the Shearon Harris Nuclear Power Plant was in a planned refueling outage. Operations was in the process of restoring the containment spray system following maintenance. During this restoration process, operations started the 'B' containment spray pump with Refueling Water Storage Tank ( RWST) level below 23.4 percent. As a result, the logic to initiate containment spray switchover to the containment sump was satisfied, opening the containment sump suction valve, which established a flowpath that allowed water to be transferred from the RWST to the containment sump. Operations secured the 'B' containment spray pump and re-closed the containment sump suction valve to restore the plant to the desired configuration. During the event, the containment spray system was aligned for recirculation of the spray pump discharge back to the RWST, so no water flowed through the spray header.
The primary cause of the event was a procedural deficiency. The procedure did not establish a physical barrier to prevent the containment sump valves from opening in Modes 5, 6 and defueled. The corrective actions include revising the procedure to remove power to the containment sump valves to prevent them from opening in Modes 5, 6 and defueled. |
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Category:Letter
MONTHYEARIR 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 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 05000400/20243012024-02-21021 February 2024 – NRC Operator Licensing Examination Approval 05000400/2024301 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 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 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 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 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition 2024-09-10
[Table view] Category:Licensee Event Report (LER)
MONTHYEARRA-24-0183, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out 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-2016-0052016-12-0707 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-2016-0042016-12-0707 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-2016-0022016-09-19019 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 Inf000llects.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 Note: Energy Industry Identification System (EllS) codes are identified in the text within brackets [ ].
A. Background
Event Date: October 26, 2016 Mode: 6 Reactor Power: 0 percent Event Time: 1142 EDT No systems, structures, or components 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. The plant was in mode 6, refueling, with the reactor vessel head removed, reactor cavity water level greater than 23 feet, core reload complete, and the residual heat removal system in operation.
This event is reportable per 10 CFR 50.73(a)(2)(iv)(A) as "an event or condition that results in valid actuation of any of the systems listed in paragraph (a)(2)(iv)(B) of [10 CFR 50.73]..." due to actuation of a valve in the containment spray (CT) system [BE].
The purpose of the CT system is to spray borated sodium hydroxide solution into Containment [NH] to cool the atmosphere and to remove the fission products that may be released into the containment atmosphere following a loss of coolant accident (LOCA) or main steam line break (MSLB). It has two principal modes of operation: 1) the initial injection mode, during which time the system sprays borated water taken from the refueling water storage tank (RWST) [TK], and 2) the recirculation mode, which is initiated when low-low level is reached in the RWST. During recirculation mode, the pump suction is transferred from the RWST to the containment sump by opening the containment sump suction valves and closing the valves at the outlet of the RWST. This switchover is accomplished automatically.
B. Event Description
On October 26, 2016, at 1142 EDT, the Shearon Harris Nuclear Power Plant (Harris) was in a planned refueling outage.
Operations was in the process of restoring the CT system following maintenance, with the reactor cavity filled with water and the RWST level less than 23.4 percent. During the CT system restoration, Operations started the 'B' CT pump [P], which was aligned to the RWST. With RWST level less than 23.4 percent, the logic was satisfied to initiate CT switchover to the containment sump. This caused the containment sump suction valve, 1CT-102 [ISV], to open, establishing a flow-path which allowed water to be transferred from the RWST to the containment sump.
Immediate action was taken by Operations to restore the desired plant configuration. This was achieved by securing the CT pump and re-closing 1CT-102. During the event, the CT system was aligned for recirculation of 'B' CT pump discharge back to the RWST, so no water flowed through the spray header.
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 Inf000llects.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 C. Causal Factors The primary cause of this event was a procedural deficiency. The procedure did not establish a physical barrier to prevent the containment sump valves from opening in Modes 5, 6 and defueled.
D. Corrective Actions
Completed Actions:
Immediate corrective action to provide just-in-time training for Operations as a refresher on the operation of the spray system switchover actuation logic.
Planned Actions:
Revise the procedure to remove power to the containment sump valves to prevent them from opening in Modes 5, 6 and defueled.
E. Safety Analysis
The safety significance of this event was minimal, as the condition had no impact on decay heat removal. The event did not affect water inventory in the reactor cavity, and there was no impact on core cooling, which was being performed by the residual heat removal system [BP] at the time of the event. This event did not impact the health and safety of the public.
F. Additional Information
There have been no related events at Harris within the past three years.
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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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