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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
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
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Westinghouse Westinghouse ElectricCompany Nu(1ear Seices P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 UJSA U.S. Nuclear Regulatory Commission Direct tel: (412) 374-5282 Document Control Desk Direct fax: (412) 374-4011 Washington, DC 20555-0001 e-mail: Sepplhaewestinghouse.com Attn: Theodore R. Quay, Chief Your ref NRC Letter dated May 27, 2003 Equipment and Human Performance Branch Our ref LTR-NRC-03-37 Division of Inspection and Program Management July 11, 2003
Subject:
Response to NRC Letter Regarding Westinghouse Part 21 Reviews The purpose of this letter is to formally respond to NRC letter dated May 27, 2003 from Theodore R.
Quay, Chief, Equipment and Human performance Branch, Division of Inspection and Program Management, to the undersigned. We are also in receipt of a second letter wherein you correct an error indicating that the original letter did no represent a Notice of Nonconformance though it was so stated.
The substance of the original NRC letter indicates that based upon information from an individual the NRC, remains concerned regarding Westinghouse's interpretation of Part 21. It appears that Westinghouse does not adequately address the requirements of Part 21 to evaluate deviations and failures to comply that could create a substantial safety hazard if left uncorrected" (emphasis added).
Westinghouse has always performed full and complete evaluations of deviations or failures to comply that are entered into the Westinghouse 10 CFR Part 21 program. These evaluations look at each situation in exacting detail including any systems or other synergistic effects. Our evaluation into the specific issue of the CEA's at Palo Verde Nuclear Generating Station did consider the "left uncorrected" case as we assessed the situation and determined that it is not a credible situation. CEA's are tested and inspected at
-ih-ebeginning and end of every oper-aning cycle-thus providing-a limitation on any issues that may arise.
Notwithstanding that the foregoing was a part of our 10 CFR Part 21 evaluation, Westinghouse acknowledges that this information may not have been explicitly stated in our documentation of this issue.
In addition, regarding the issue of the Control Element Assemblies (CEA) at Palo Verde Nuclear Generating Station, we agree with the NRC statement that there was no deviation or failure to comply on the part of Westinghouse.
Westinghouse remains sensitive to its obligation to continue meeting the requirements specified in 10 CFR Part 21. The following actions have been or will be taken: 1) As a process enhancement, Westinghouse will explicitly state in all future evaluations that the issue in question was assessed assuming that it could create a substantial safety hazard if it were left uncorrected. This wording is already included in Westinghouse Policy/Procedure WEC 21.0 Rev. 3, Page 1, Paragraph I and training on this requirement already is provided to Westinghouse employees.
A BNFL Group company
Page 2 of 2 Our ref: LTR-NRC-03-37
- 2) This information has been provided to our regulatory compliance staff and the aforementioned language will be included in our 10 CFR 21 evaluations. 3) We will confirm that all recently closed and current issues evaluated in the WEC 10 CFR 21 program considered "deviations and failures to comply that could create a Substantial Safety Hazard if left uncorrected," by August 31, 2003.
If there are any additional questions, please do not hesitate to contact the undersigned.
Very truly yours, H. A. Sepp, Mahager Regulatory Compliance and Plant Licensing Official record electronically approved inEDMS 2000 A BNFLGroup company