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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
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ODCM 2.1 A P--- A subsidiaryof Pinnacle West CapitalCorporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Vice President Tel. 623-393-5403 P.O. Box 52034 Generating Station Regulatory Affairs and Plant Improvement Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06283-DCM/KAC November 22, 2010 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. STN 50-530 License No. NPF-51 Special Report 3-SR-2010-001-00 Attached please find Special Report 3-SR-2010-001 -00, which is prepared and submitted pursuant to PVNGS Offsite Dose Calculation Manual (ODCM) requirements. This report discusses the inoperability of a fuel building ventilation system high range radioactive gaseous effluent monitor for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
By copy of this letter and the attachment, this report is being provided to the NRC Region IV Administrator and the PVNGS Resident Inspector.
No commitments are being made to the NRC by this letter.
Should you need further information regarding this submittal, please contact Marianne Webb, Compliance Section Leader, at (623) 393-5730.
Sincerely, DCM/MNW/KC/gat Enclosure Special Report 3-SR-2010-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable cc: (with enclosure)
E. E. Collins Jr. NRC Region IV Regional Administrator J. R. Hall NRC NRR Senior Project Manager L. K. Gibson NRC NRR Project Manager J. H. Bashore NRC Senior Resident Inspector (acting) for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway - Comanche Peak
11-;
Enclosure Special Report 3-SR-2010-001-00 Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable
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Palo Verde Nuclear Generating Station Special Report 3-SR-2010-001 -00 Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable Docket No. STN 50-530, Unit 3 Reporting Requirement:
The PVNGS Offsite Dose Calculation Manual (ODCM) contains operability requirements for radioactive gaseous effluent monitoring instrumentation in Section 2.1, "Requirements: Gaseous Monitors." Action 42 for Table 2-1, Item 5, "Fuel Building Ventilation System," specifies that when the number of OPERABLE High Range Monitors is less than required by the Minimum Channels OPERABLE requirement, and the required monitor is not restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, then the associated actions are to:
a) Initiate the Preplanned Alternate Sampling Program to monitor the appropriate parameter(s) when it is needed.
b) Prepare and submit a Special Report to the Commission within 30 days following the event outlining the action(s) taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.
Initial Conditions:
At 1405 Mountain Standard Time (MST) on October 21, 2010, Unit 3 was in a refueling outage, with the core off-loaded to the spent fuel pool. The fuel building ventilation system high range radioactive gaseous effluent monitor (RU-146) was declared inoperable due to its 120 VAC Class 1E power supply (PNB-D26) being removed from service.
RU-146 was not restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Actions Taken:
The Preplanned Alternate Sampling Program was initiated pursuant to the ODCM Requirement 2.1, ACTION 42(a) on October 24, 2010, at 1405 MST. On October 28, 2010, at 0845 MST, RU-146 was declared OPERABLE after restoration of power and completion of the channel check surveillance test. There were no radiation level anomalies recorded during the compensatory period that alternate sampling was in place.
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Palo Verde Nuclear Generating Station Special Report 3-SR-2010-001-00 Cause of the Inoperability:
There was no monitor malfunction associated with the inoperability of RU-146. The cause for exceeding the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> allowed by ODCM 2.1, Action 42(b), was primarily due to the voluntary implementation of a modification to improve the reliability of inverter (PNB-N12) during a time that imposed minimum risk impact to the station.
The inverter, the associated Class IE 125vdc bus, and therefore monitor RU-146, were specifically removed from service at a time when the reactor was defueled. This modification was scheduled to work 24/7 during a refueling outage because the scope of this work cannot be performed when the unit is operating. The cumulative effect of the work resulted in RU-1 46 being out of service for 162 hours0.00188 days <br />0.045 hours <br />2.678571e-4 weeks <br />6.1641e-5 months <br /> and 40 minutes.
Plans and Schedule for Restoring the Channels to OPERABLE Status:
On October 28, 2010, at 0845 MST, RU-1 46 was declared OPERABLE after completion of the channel check surveillance test.
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