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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML19323C9712019-11-15015 November 2019 Interim 10 CFR 21 Report for Masoneilan Model 8005N Transducer ML19304B6072019-10-31031 October 2019 Written Defect Notification for GE-Hitachi Stationary Primary Contact Finger Q0114C5382P002 ML19261A1942019-09-0606 September 2019 Final Report (Log # 2019-22-00) (Event# EN 54215) - Non-Destructive Examination (Liquid Penetrant) Performance of Components by an Un-Qualified Employee ML18302A2282018-10-19019 October 2018 Itt Enidine - USNRC 10CFR Part 21 Notification ML18270A3352018-09-26026 September 2018 Interim 10 CFR 21 Report for General Electric Hitachi (GEH) Relay Contact Cartridge DJ148C6159P001 ML17188A4222017-06-26026 June 2017 Itt Enidine, Inc - Part 21 - Potential Transducer Component Defect ML17124A7342017-05-0404 May 2017 Final Part 21 Report for General Electric Hitachi Model AKR-2BE- 50 Breaker ML17101A3642017-04-0707 April 2017 Part 21 - Circuit Breaker Defect Discovered During Current Injection Testing ML16344A1182016-12-0909 December 2016 Interim 10 CFR 21 Report for General Electric Hitachi Model AKR-2BE-50 Breaker ML15243A1742015-08-25025 August 2015 Part 21 Furmanite Nuclear Grade Leak Seal Material FSC-N-1B ML13213A2832013-07-26026 July 2013 Closure of Part 21 Interim Report for Flowserve Four Inch Regulating Valve ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13094A1772013-03-18018 March 2013 Notice to the U.S. Nuclear Regulatory Commission of a Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters Manufactured by Aaf ML12319A4732012-11-0909 November 2012 Interim Part 21 Report for Flowserve Four Inch Regulating Value ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12097A3162012-03-0202 March 2012 Part 21 Report - Rosemont Pressure Tranmitters Out of Tolerance Condition ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML0934301402009-12-0202 December 2009 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 1OCFR21-0098, Rev. 0, Amot Thermostatic Valve Element, P/N: 9760X ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0414104452004-04-27027 April 2004 During Unpacking of Boxes for Palo Verde I SG I at Ansaldo Plant It Was Revealed That Some Tubes Had Been Damaged by Screws During Packing in Sandviken. During Sandvik Reinspection of Boxes at the Ansaldo Plant, Further Damaged Tubes Were F ML0320500522003-07-11011 July 2003 Response to NRC Letter Regarding Westinghouse Part 21 Reviews 2019-09-06
[Table view] Category:Letter
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 ML24296B2142024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 02: Alternative Request Allowing Normally Closed Valves with a Safety Function to Close to Be Exercise Tested Once Per Refueling Cycle ML24296B2152024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 03: Alternative Request Allowing Removal of the Lower Acceptance Criteria Threshold from Solenoid-Operated Valves ML24296B2172024-10-18018 October 2024 Submittal of Unit 1 Core Operating Limits Report, Revision 34, Unit 2 Core Operating Limits Report, Revision 26, and Unit 3 Core Operating Limits Report, Revision 3 ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 ML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report ML24285A2562024-10-11011 October 2024 License Renewal - Alloy 600 Management Program Plan Response to Request for Additional Information IR 07200044/20244012024-10-0808 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200044/2024401 ML24269A1542024-09-27027 September 2024 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed Life-of-Plant Alternatives for a Pressurizer Thermowell Nozzle Repair at Palo Verde Nuclear Generating Station, Unit 1 ML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) 05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-08-21021 August 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24208A0612024-08-20020 August 2024 Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5 IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator2024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater2024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24129A1482024-05-0707 May 2024 And Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24032A1542024-04-0303 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) 2024-09-27
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10 CFR 21.21 JOHN J. CADOGAN Vice President Nuclear Engineering Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel 623 393 4921 102-06740-JJC/DCE July 26, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Reference:
Palo Verde Nuclear Generating Station Interim Part 21 Report for Flowserve Four Inch Regulating Valve, Letter 102-06618, dated November 9, 2012, NRC Log Number 2012-51-00
Dear Sir:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket No. STN 50-528, STN 50-529, and STN 50-530 License No. NPF 41, NPF 51, and NPF 74 Closure of Part 21 Interim Report for Flowserve Four Inch Regulating Valve Pursuant to the requirements of 10 CFR Part 21, APS submitted the Interim Report (Reference) regarding an evaluation of an apparent deviation which could not be completed within 60 days from the discovery. The apparent deviation of a basic component involved a four inch regulating valve that would not fully close during post installation calibration. The regulating valve is used to control essential chilled water system chiller refrigerant pressure.
APS completed the required evaluation based on inspections by the supplier, Flowserve US, Inc. The evaluation concluded the regulating valve would not fully close during calibration because the valve stem guide had become dislodged from the normal installed position. This is postulated to have occurred as a result of a fluid pressure surge inside the valve caused by incomplete venting of the valve prior to initiating water flow through the valve during calibration.
Since the inability of the regulating valve to fully close during calibration resulted from maintenance activities during valve installation, no deviation in a A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway.Comanche Peak.Diablo Canyon.Palo Verde-San OnofreSouth Texas-Wolf Creek
102-06740-JJC/DCE July 26, 2013 ATIN: Document Control Desk U. S. Nuclear Regulatory Commission Closure of Interim Part 21 Report for Flowserve Four Inch Regulating Valve Page 2 basic component existed and the condition is no longer subject to an evaluation pursuant to 10 CFR Part 21. Therefore, the referenced interim report may be closed with no additional action required.
The 10 CFR 50, Appendix B, supplier and affected components described in the referenced interim report are provided below:
Supplier Flowserve US, Inc.
1900 S SAUNDERS STREET Raleigh, NC 27603 Basic Components Metrex Corporation Four Inch Refrigerant Pressure Actuated Water Regulating Control Valve, Model MM313OB-11M Flowserve Part Number: 04002262 Metrex Corporation Alternative Bypass Stem Kit for Model MM313OB-11M Metrex Part Numbers 27M-245A, 1K5-14, 45M-744 and 4K1-50 Flowserve Part Number: 04113854XXXXXXX In accordance with 10 CFR 50.4, copies of this report are being forwarded to the Nuclear Regulatory Commission (NRC) Regional Office, NRC Region IV, and the Senior Resident Inspector. If you have questions regarding this submittal, please contact Mark McGhee, Operations Support Manager, Regulatory Affairs, at (623) 393-4972.
Arizona Public Service Company makes no commitments in this letter.
Sincerely, JJC/DCE/hsc cc: E. E. Collins Jr. NRC Region IV Regional Administrator J. K. Rankin NRC NRR Project Manager for PVNGS J. P. Reynoso NRC Senior Resident Inspector for PVNGS