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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 30-Day Written Event Report
MONTHYEARML19116A2462019-04-26026 April 2019 SR-2019-001-00 for Palo Verde Nuclear Generating Station (PVNGS) Unit 1, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional ML18306A7622018-11-0101 November 2018 Special Report 2-SR-2018-001-00 for Palo Verde Nuclear Generating Station (Pvngs), Unit 2, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional ML1109701512011-04-0101 April 2011 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML1000400662009-12-22022 December 2009 30-Day Report Pursuant to 10 CFR 50.46(a)(3)(ii) and Submittal of Large Break Loss of Coolant Accident Reanalysis Results ML0907005532009-02-24024 February 2009 LER for Palo Verde, Units 1 and 3, Regarding Special Reports 1-SR-2009-001-00, 3-SR-2009-001-00 on Fuel Building Ventilation System High Range, Radioactive Gaseous Effluent Monitor Inoperable ML0524307122005-08-23023 August 2005 Special Report 3-SR-2005-002, Report of Boron Deposit at Control Element Drive Mechanism Vent ML0511601862005-04-14014 April 2005 Special Report 1-SR-2005-001 of Boron Deposit at Control Element Drive Mechanism Vent ML0433402652004-11-19019 November 2004 Special Report 3-SR-2004-003 Re Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable ML0423005132004-08-0606 August 2004 Special Report 3-SR-2004-001 Report of Boron Deposit at Control Element Drive Mechanism Vent ML0423005092004-08-0606 August 2004 Unit I, Special Report 1-SR-2004-003 Report of Boron Deposit at Control Element Drive Mechanism Vent ML0429603932004-07-0505 July 2004 Draft Preliminary Root Cause of Failure Analysis 13.8kV Breaker Failures During Losss of Switchyard Event ML0328804092003-10-0101 October 2003 Special Report 3-SR-2003-04 Regarding Boron Deposit at Control Element Drive Mechanism Vents ML0328703072003-10-0101 October 2003 Special Report 1-SR-2003-002 Re Boron Deposit at Control Element Drive Mechanism Vent ML0204202202002-01-0303 January 2002 Special Report 2-SR-2001-001 Regarding Post Accident Sampling System Being Inoperable 2019-04-26
[Table view] Category:Written Event Report (30 or 60 day)
MONTHYEARML21356B7212021-12-22022 December 2021 Special Report 3-SR-2021-001-00 ML0524307122005-08-23023 August 2005 Special Report 3-SR-2005-002, Report of Boron Deposit at Control Element Drive Mechanism Vent ML0511601862005-04-14014 April 2005 Special Report 1-SR-2005-001 of Boron Deposit at Control Element Drive Mechanism Vent ML0433402652004-11-19019 November 2004 Special Report 3-SR-2004-003 Re Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable ML0423005132004-08-0606 August 2004 Special Report 3-SR-2004-001 Report of Boron Deposit at Control Element Drive Mechanism Vent ML0423005092004-08-0606 August 2004 Unit I, Special Report 1-SR-2004-003 Report of Boron Deposit at Control Element Drive Mechanism Vent ML0429603932004-07-0505 July 2004 Draft Preliminary Root Cause of Failure Analysis 13.8kV Breaker Failures During Losss of Switchyard Event ML0328804092003-10-0101 October 2003 Special Report 3-SR-2003-04 Regarding Boron Deposit at Control Element Drive Mechanism Vents ML0328703072003-10-0101 October 2003 Special Report 1-SR-2003-002 Re Boron Deposit at Control Element Drive Mechanism Vent ML0204202202002-01-0303 January 2002 Special Report 2-SR-2001-001 Regarding Post Accident Sampling System Being Inoperable 2021-12-22
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.w David Mauldin Vice President Mail Station 7605 Palo Verde Nuclear Nuclear Engineering TEL (623) 393-5553 P.O. Box 52034 Generating Station and Support FAX (623) 393-6077 Phoenix, AZ 85072-2034 EA-03-009 102-05135- CDM/DFH/kg August 6, 2004 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. STN 50-530 Special Report 3-SR-2004-001 Report of Boron Deposit at Control Element Drive Mechanism Vent
Dear Sirs:
Attached please find Special Report 3-SR-2004-001 prepared and submitted by Arizona Public Service (APS) pursuant to NRC Revised Order EA-03-009, dated February 20, 2004.Section IV.D of the Order requires licensees to perform certain visual inspections to identify potential boric acid leaks from pressure-retaining components above the Reactor Pressure Vessel head.Section IV.E of the Order requires licensees to submit reports detailing the inspection results within sixty (60) days after returning plants to operation.
This special report details the results of visual inspections performed at PVNGS Unit 3 subsequent to a reactor shutdown on June 7, 2004. The visual inspections were performed in accordance with the Boric Acid Corrosion Prevention Program which APS implements to identify and prevent boric acid corrosion of reactor pressure boundary components.
In accordance with 10 CFR 50.4(b)(1), copies of this report are being provided to the Region IV Administrator and the Palo Verde NRC Senior Resident Inspector.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
fal .i-Special Report 3-SR-2004-001 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Page 2 No commitments are being made to the NRC by this letter. If you have questions regarding this submittal, please contact Dan Marks, Section Leader, Compliance, at (623) 393-6492.
Sincerely, CDM/DFH/kg Attachment cc: B. S. Mallet, Region IV Administrator M. B. Fields, PVNGS Project Manager N. L. Salgado, Sr. Resident Inspector Assistant General Counsel for Materials Litigation and Enforcement Rulemaking and Adjudication Staff
o,* A-Attachment Palo Verde Nuclear Generating Station Unit 3 Special Report No. 3-SR-2004-001 Boron Deposit Found at Control Element Drive Mechanism Vent Docket No. STN 50-530 Reporting Requirement:
The NRC Revised Order EA-03-009, "Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors," dated February 20, 2004,Section IV.D requires that certain visual inspections be performed to identify potential boric acid leaks from pressure-retaining components above the reactor pressure vessel head.
Additionally,Section IV.E of the NRC Order requires that licensees submit reports detailing the inspection results performed per section IV.D within sixty (60) days after returning the plant to operation if a leak or boron deposit was found during the inspection.
Background:
On June 7, 2004, Palo Verde Unit 3 reactor tripped due to a turbine hydraulic control problem. Subsequent to the reactor trip, routine visual inspections were performed in accordance with the Boric Acid Corrosion Prevention Program (APS procedure 70TI-9ZC01). APS implemented the Boric Acid Corrosion Prevention Program to prevent boric acid corrosion of reactor pressure boundary components and to ensure the requirements contained in USNRC Generic Letter No. 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants" are met.
Report Detailina Inspection Results:
During boric acid walk-downs on June 8, 2004, one Unit 3 boric acid residue site was identified above the RPV head. The site was located on the Versa Vent for control element drive mechanism (CEDM) no. 55. The site exhibited no evidence of being an active leak and the boric acid residue did not contact the RPV head or related insulation.
Since no carbon steel was affected and the leak site on Versa Vent for CEDM no. 55 was not an active leak, no non-conforming condition exists. Versa Vent no. 55 was cleaned prior to restarting Unit 3.
Unit 3 was returned to operation (Mode 1) on June 10, 2004.
N