01-10-2017 | On July 20, 2016, PVNGS received Unit 3 "B" train (3B) control room essential air filtration unit (AFU) carbon sample test results that exceeded the acceptance criteria of the Technical Specification (TS) Ventilation Filter Testing Program. The Unit 3 control room (CR) staff declared the AFU inoperable and entered TS Limiting Condition for Operation (LCO) 3.7.11, control room essential filtration system ( CREFS). The carbon filter replacement and testing was completed, and the Unit 3 CR staff declared the 3B CREFS AFU operable on July 24, 2016.
The investigation determined the 3B CREFS AFU was inoperable since December 17, 2015, which exceeded the Required Action Completion Time for Conditions A and C of LCO 3.7.11 on December 24, 2015 and Condition E during movement of irradiated fuel. The direct cause of this event was exposure of the 3B CREFS AFU carbon filter to a high amount of volatile organic compounds (VOCs) during a CR renovation project. The apparent cause was a lack of knowledge and recognition by PVNGS personnel to identify and properly mitigate the effects of the project on the CREFS AFU resulting in inadequate guidance for controlling all potential sources of VOCs. Applicable change process and work control procedures have been revised to ensure flooring and furniture replacements that could impact the CREFS AFU are evaluated as potential sources of VOCs prior to performing work.
No previous similar events have been reported by PVNGS in the last three years. |
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Category:Letter
MONTHYEARML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program IR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23222A2762023-08-10010 August 2023 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canister Identification Numbers AMZDFX175 and AMZDFX176 and Vertical Concrete Cask Identification Numbers AMZDNE175, and AMZDNE176 ML23199A2942023-08-0909 August 2023 Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 ML23207A2482023-07-26026 July 2023 License Renewal Pressurizer Surge Line Inspection ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owners Activity Report Number 2R24 ML23166B0832023-07-0505 July 2023 Independence Spent Fuel Storage Installation - Issuance of Exemption ML23181A1602023-06-30030 June 2023 2 to Updated Final Safety Analysis Report, and Revision 3 to Operations Quality Assurance Program Description ML23180A2222023-06-29029 June 2023 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) - Operating, TS 3.5.2, Safety Injection Tanks (Sits) - Shutdown, and TS 3.6.5, Containment Air Temperature ML23181A0772023-06-29029 June 2023 Program Review - Simulator Testing Methodology ML23157A1292023-06-0101 June 2023 Annual Report of Guarantee of Payment of Deferred Premium ML23144A3722023-05-24024 May 2023 Response to Regulatory Issue Summary (RIS) 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23143A3912023-05-23023 May 2023 Independent Spent Fuel Storage Installation - Request for Exemption from NAC-MAGNASTOR Certificate of Compliance 72-1031 - Cask Lid Batch 3 Design Requirements ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23132A3392023-05-12012 May 2023 Application to Revise Technical Specifications 3.3.11 to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23128A0692023-05-0808 May 2023 Notification of Biennial Problem Dentification and Resolution Inspection and Request for Information ML23122A1822023-04-29029 April 2023 Transmittal of Technical Specification Bases Revision 76 ML23122A1912023-04-29029 April 2023 Unit 1 Core Operating Limits Report Revision 32, Unit 2 Core Operating Limits Report Revision 25, Unit 3 Core Operating Limits Report Revision 31 ML23116A2772023-04-26026 April 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2022 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 ML23115A4982023-04-25025 April 2023 2022 Annual Environmental Operating Report IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML23103A4642023-04-13013 April 2023 Annual Radiological Environmental Operating Report 2022 ML23103A4312023-04-13013 April 2023 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022 IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 ML23102A3292023-04-12012 April 2023 Application for Authorized Use of Mururoa Single-Use, Supplied Air Suits, Models V4F1 and MTH2 ML23102A3242023-04-12012 April 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-107-A, Separate Control Rods That Are Untrippable Versus Inoperable ML23089A4002023-03-30030 March 2023 Consolidated Decommissioning Funding Status Report - 2022 ML23088A4012023-03-30030 March 2023 Project Manager Assignment IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) ML23080A3002023-03-21021 March 2023 Present Levels of Financial Protection 2024-01-19
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000528/LER-2017-0012017-06-14014 June 2017 Essential Chiller B Inoperable Due to Refrigerant Leak Resulting in Safety System Functional Failure, LER 17-001-00 for Palo Verde Nuclear Generating Station, Unit 1 Regarding Essential Chiller B Inoperable Due to Refrigerant Leak Resulting in Safety System Functional Failure 05000530/LER-2016-0012017-01-10010 January 2017 Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications, LER 16-001-01 for Palo Verde, Unit 3, Regarding Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications 05000528/LER-2016-0022016-11-0404 November 2016 Reactor Trip due to Partially Open Pressurizer Main Spray Valve, LER 16-002-00 for Palo Verde, Unit 1, Regarding Reactor Trip due to Partially Open Pressurizer Main Spray Valve 05000528/LER-2016-0012016-06-0909 June 2016 . Leakage from Reactor Coolant Pump 2B Discharge Pipe Instrument Nozzle, LER 16-001-00 for Palo Verde Nuclear Generating Station Unit 1 RE: Leakage from Reactor Coolant Pump 2B Discharge Pipe Instrument Nozzle 05000530/LER-2015-0042016-02-0505 February 2016 Condition Prohibited by Technical Specifications 3.0.4 and 3.7.2 Due to an Inoperable Main Steam Isolation Valve, LER 15-004-01 for Palo Verde, Unit 3, Regarding Condition Prohibited by Technical Specifications 3.0.4 and 3.7.2 Due to an Inoperable Main Steam Isolation Valve ML1034000852010-11-22022 November 2010 LER Palo Verde, Unit 3 - Submittal of Special Report 3-SR-2010-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable ML0612902562006-04-25025 April 2006 LER 04-02-001 for Palo Verde, Unit 3 Regarding Main Turbine Control System Malfunction Results in Automatic Reactor Trip on Low DNBR ML0602403892005-11-29029 November 2005 Final Precursor Analysis - Palo Verde 1, 2, 3 - Emergency Core Cooling System Piping Voids May Have Prevented Fulfillment of Safety Function ML0530400642005-10-19019 October 2005 Special Report 2-SR-2005-003-00 ML0523802472005-08-13013 August 2005 LER 005-003-00 for Palo Verde, Unit 2 Regarding Two Independent Trains of Auxiliary Feedwater Inoperable ML0413204582004-05-0404 May 2004 Special Report 2-SR-2004-001 for Palo Verde Nuclear Generating Station (PVNGS) Unit 2 Regarding Boron Deposit at Control Element Drive Mechanism Vent ML0303805312003-01-31031 January 2003 LER 03-S01-00 for Palo Verde, Units 1, 2 and 3 Safeguards Material Left Unattended ML0226304872002-09-11011 September 2002 Special Report 1-SR-2002-01 ML0222506692002-08-0707 August 2002 LER 02-S01-00 for Palo Verde Nuclear Station (Pvng), Units 1,2 & 3 Re Reports Discovery of Uncontrolled Safeguards Material in Palo Verde Nuclear Station (PVNGS) Office Complex Outside of Protected Area ML1014705982002-03-0202 March 2002 Event Notification for Palo Verde on Offsite Notification ML0205904412002-02-12012 February 2002 LER 98-003-02, for Palo Verde Units 1, 2 & 3 Re Main Steam Safety Valve As-Found Lift Pressures Outside of Technical Specifications Limits 2017-06-14
[Table view] |
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send 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 intemet e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means 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.
Palo Verde Nuclear Generating Station All times are Mountain Standard Time and approximate unless otherwise indicated.
1. REPORTING REQUIREMENT(S):
This Licensee Event Report (LER) is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) to report a condition prohibited by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.7.11, control room essential filtration system (CREFS)(EllS:V1). Palo Verde Nuclear Generating Station (PVNGS) received Unit 3 "B" train (3B) CREFS air filtration unit (AFU) carbon sample test results that exceeded the TS Ventilation Filter Testing Program (VFTP) acceptance criteria on July 20, 2016 for a sample obtained on June 24, 2016.
The investigation determined the 3B CREFS AFU was inoperable since December 17, 2015, which exceeded the Required Action Completion Time for Conditions A and C of LCO 3.7.11. December 24, 2015 is the event date when the LCO Required Action Completion Time expired. The investigation also determined irradiated fuel was moved in the Unit 3 spent fuel pool on multiple occasions with the operable CREFS train not in the essential filtration mode, which did not meet the requirements of Condition E of LCO 3.7.11.
2. DESCRIPTION OF STRUCTURE(S), SYSTEM(S) AND COMPONENT(S):
The control room (CR) heating, ventilation, and air conditioning (HVAC) system (HJ) consists of normal and essential systems that provide suitable environmental conditions for the CR complex for all normal and abnormal operations. This system is required to maintain temperatures to support a comfortable environment for CR personnel as well as provide adequate cooling to plant equipment, protect the CR staff from intrusion of poisonous gases, smoke, or airborne radioactivity, and ensure the CR area has appropriate conditions for prolonged occupancy through the duration of postulated events. These functions are achieved through the use of one normal ventilation system and two redundant safety systems.
The CR HVAC system includes the CREFS, which consists of two separate, seismically-qualified, redundant essential flow trains. Each flow train consists of an AFU with a series of filters to process intake airflow and recirculate air flow to the CR envelope. Low leakage ductwork and dampers are provided to minimize unfiltered air in-leakage. The CR post-accident habitability requirements are met by either CREFS train.
The B train CREFS shares ductwork with the CR normal (non-essential) ventilation system and both serve the inverter room and communication room during non-emergency conditions. The normal air handling unit ductwork, inverter room, and communication room are automatically isolated from the B train CREFS upon a control room essential filtration actuation signal.
The A train CREFS does not supply the inverter room or the communication equipment room, nor does it share ductwork with the normal ventilation or B train CREFS except for the final CR outlet ducts.
The CREFS AFUs are each designed with a fan, pre-filter, two high-efficiency particulate air (HEPA) filters, and a carbon adsorption filter. The purpose of the carbon filter is to filter out radioiodine during postulated accident situations via a chemical reaction between the iodine and the activated carbon. The carbon is tested every 18 months in accordance with TS Surveillance Requirement (SR) 3.7.11.2 and TS Program 5.5.11, VFTP. This surveillance requirement involves sending a representative carbon sample to a laboratory for testing per ASTM D3803-1989, Standard Test Method for Nuclear-Grade Activated Carbon.
TS LCO 3.7.11 requires two CREFS trains be operable during Modes 1, 2, 3, 4, 5, 6, and during movement of irradiated fuel assemblies. The Required Action for Condition A, for a single inoperable train for reasons other than an inoperable CR envelope boundary, specifies restoration of the inoperable train within 7 days. Condition C requires entry into Mode 3 if the Required Action is not completed.
Additionally, if the Required Action for Condition A is not met, Condition E requires the operable CREFS train be placed in essential filtration mode or immediate suspension of irradiated fuel movement if an operable CREFS train is not immediately placed in the essential filtration mode.
3. INITIAL PLANT CONDITIONS:
On December 24, 2015, PVNGS Unit 3 was in Mode 1 (Power Operation), at 100 percent power, normal operating temperature, and normal operating pressure. There were no other structures, systems, or components out of service that contributed to these events.
4. EVENT DESCRIPTION:
On June 24, 2016, a carbon sample was obtained from the 3B CREFS AFU in accordance with TS SR 3.7.11.2 and the VFTP and sent offsite for testing per ASTM D3803-1989. On July 20, 2016, PVNGS received the carbon sample test results that exceeded the TS VFTP acceptance criteria. Unit 3 CR staff declared the 3B CREFS AFU inoperable and entered TS LCO 3.7.11, CREFS.
PVNGS engineering personnel questioned the departure of the test results from the expected carbon efficiency trend and a second carbon sample was obtained on July 20, 2016 and sent offsite for testing.
The results of this test also exceeded the TS VFTP acceptance criteria. An emergent change-out of the carbon filter began on July 22, 2016. The carbon filter replacement and testing was completed, and the Unit 3 CR staff declared the 3B CREFS AFU operable on July 24, 2016.
An offsite laboratory performed a radioiodine test analysis and determined volatile organic compounds (VOCs) were the direct cause of the CREFS carbon failure. Additional offsite laboratory testing was performed and the results confirmed that a CR renovation project that occurred in December 2015, which included carpet and furniture replacements, was the primary contributor to the failure. The current plant change process addresses impacts from painting, welding, and solvent use in areas that could impact the CREFS AFU carbon filter, but the process does not address flooring or furniture changes as potential VOC sources.
The investigation determined the 3B CREFS AFU became inoperable on December 17, 2015, when the 3B CREFS AFU was operated and exposed to the VOCs created by the CR renovation project.
December 24, 2015, is the event date when the LCO Required Action Completion Time for Conditions A and C of LCO 3.7.11 expired. Irradiated fuel was moved in the Unit 3 spent fuel pool on multiple occasions with the operable CREFS train not in the essential filtration mode, which did not meet the requirements of Condition E of LCO 3.7.11.
The Unit 3 "A" train CREFS AFU was not susceptible to VOC contamination because it was not operated during the CR renovation.
The CR renovation project has been performed in each of the three PVNGS units. The carbon filters for the Unit 1 and Unit 2 "A" and "B" trains of CREFS AFUs have been tested since the discovery of this condition with satisfactory results.
5. ASSESSMENT OF SAFETY CONSEQUENCES:
This event did not result in a potential transient more severe than those analyzed in the Updated Final Safety Analysis Report (UFSAR) or result in an abnormal release of radioactive materials to the environment. There were no actual safety consequences as a result of this event and the event did not adversely affect the health and safety of the public. The redundant train 3A CREFS AFU was not removed from service while the 3B CREFS AFU was inoperable.
The nuclear safety risk significance associated with the subject condition was minimal. The degraded CREFS AFU filtration capability impacts design basis requirements regarding CR staff dose in design basis accidents. However, the condition has minimal impact on actual risk due to: (1) the remaining margin in the filters capable of limiting doses from design basis events to those which will not create acute health effects and (2) the availability of portable air breathing devices to minimize the dose impacts from elevated CR airborne radionuclides in design basis and beyond design basis events. In addition, the likelihood of events creating radioactive releases capable of causing acute health effects to the CR staff assuming no CREFS AFU capability is very small ( probabilistic risk assessment model results.
The event would not have prevented the fulfillment of a safety function and the condition did not result in a safety system functional failure as defined by 10 CFR 50.73 (a)(2)(v).
6. CAUSE OF THE EVENT:
The direct cause of the 3B CREFS AFU carbon filter failure was exposure to a high amount of VOCs from a CR renovation project.
The apparent cause of this event was a lack of knowledge and recognition by PVNGS personnel to identify and properly mitigate the effects of a CR renovation project on the CREFS AFU resulting in inadequate guidance for controlling all potential sources of VOCs.
7. CORRECTIVE ACTIONS:
As an immediate corrective action, the CREFS AFU carbon filter bed was replaced and testing was completed. The CREFS AFU was declared operable on July 24, 2016.
Palo Verde Nuclear Generating Station To address the apparent cause, applicable change process and work control procedures have been revised to ensure flooring and furniture replacements that could impact the CREFS AFU are evaluated as potential sources of VOCs prior to performing work.
8. PREVIOUS SIMILAR EVENTS:
No similar conditions have been reported by PVNGS in the last three years.
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05000530/LER-2016-001 | Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications LER 16-001-01 for Palo Verde, Unit 3, Regarding Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000529/LER-2016-001 | Main Steam Isolation Valve Actuator Train Inoperable due to Low Nitrogen Pre-Charge Pressure | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000528/LER-2016-001 | . Leakage from Reactor Coolant Pump 2B Discharge Pipe Instrument Nozzle LER 16-001-00 for Palo Verde Nuclear Generating Station Unit 1 RE: Leakage from Reactor Coolant Pump 2B Discharge Pipe Instrument Nozzle | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000530/LER-2016-002 | Emergency Diesel Generator Failure Resulting in a Condition Prohibited by Technical Specifications | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000528/LER-2016-002 | Reactor Trip due to Partially Open Pressurizer Main Spray Valve LER 16-002-00 for Palo Verde, Unit 1, Regarding Reactor Trip due to Partially Open Pressurizer Main Spray Valve | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000528/LER-2016-003 | Inoperable Containment Isolation Valve SGA-UV-1134 Due to Failure to Close During Testing | |
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