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Category:Letter
MONTHYEARML25029A2572025-01-30030 January 2025 Independent Fuel Storage Installation - Registration of Dry Spent Fuel Transportatable Storage Canisters Identification Numbers AMZDFX184, AMZDFX185 Vertical Concrete Cask Identification Numbers AMZDNE184 ML25017A3802025-01-17017 January 2025 License Amendment Request to Adopt Westinghouse Thermal Design Procedure Topical Report WCAP-18240-P-A ML24362A1302025-01-14014 January 2025 Alloy 600 Management Program Plan ML24351A2032024-12-30030 December 2024 – Regulatory Audit Summary Concerning Relief Request No. 71: Resubmittal of Relief Request-30 ML24348A2252024-12-18018 December 2024 PV 21N 05 Request for Information Letter (Deterministic) 05000530/LER-2024-003, Violation of Technical Specifications 3.9.2 and 3.3.122024-12-12012 December 2024 Violation of Technical Specifications 3.9.2 and 3.3.12 IR 05000529/20240112024-12-11011 December 2024 License Renewal Inspection Report 05000529/2024011 ML24346A1102024-12-10010 December 2024 Relief Request 73 - Proposed Alternative for Pressurizer Lower Shell Temperature Nozzle Life of Repair ML24332A1092024-11-27027 November 2024 Transmittal of Technical Specification Bases Revision 80 ML24326A3612024-11-21021 November 2024 Response to Request for Additional Information – Relief Request 72 IR 05000528/20244032024-11-13013 November 2024 Security Baseline Inspection Report 05000528/2024403 and 05000529/2024403 and 05000530/2024403 ML24312A3152024-11-0505 November 2024 Independent Spent Fuel Storage Installation - Updated Annual Radioactive Effluent Release Report 2023 IR 05000528/20240032024-11-0404 November 2024 Integrated Inspection Report 05000528/2024003 and 05000529/2024003 and 05000530/2024003 ML24295A0362024-10-23023 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 ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 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 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) ML24197A1992024-09-0909 September 2024 Relief Request 70 - Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle 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 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 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 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 IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24177A3222024-06-25025 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 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 IR 05000528/20243012024-06-17017 June 2024 NRC Examination Report 05000528/2024301; 05000529/2024301; 05000530/2024301 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 2025-01-30
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10 CFR 50.90 A member of the STARS Alliance LLC Callaway
- Wolf Creek MARIA L. LACAL Senior Vice President, Nuclear Regulatory & Oversight Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel 623.393.6491 102-07426-MLL/TNW February 17, 2017 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Reference:
Arizona Public Service Company letter 102-07204, Commitment Schedule Change Related to TSTF-493, dated February 25, 2016
[Agencywide Documents Access and Management System (ADAMS)
Accession No. ML16056A594]
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Commitment Change Regarding Adoption of Technical Specifications Task Force Traveler 493, Revision 4, Clarify Application of Setpoint Methodology for LSSS Functions The purpose of this letter is to inform the Nuclear Regulatory Commission (NRC) that Arizona Public Service Company (APS) has revised a regulatory commitment for submitting a license amendment request (LAR) for a technical specification (TS) revision documented in the reference letter. The commitment change was performed in accordance with APS procedure 93DP-0LC08, Regulatory Commitment Tracking, which implements the guidance of NEI 99-04, Guidelines for Managing NRC Commitment Changes, which has been endorsed by the NRC staff in Regulatory Information Summary (RIS) 2000-17, Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff, dated September 21, 2000.
Revision 4 of Technical Specification Task Force (TSTF) Traveler 493, Clarify Application of Setpoint Methodology for Limiting Safety System Settings (LSSS) Functions, was approved by the NRC (75 FR 26294) on May 11, 2010. Option A of TSTF-493 applies notes to functions in the Reactor Protection System (RPS) and Engineered Safety Features Actuation System (ESFAS) specifications. The notes relate to as-found and as-left channel setpoints for the applicable surveillance requirements identified in TSTF-493.
The commitment identified in the reference letter reads as follows:
APS shall submit a license amendment request based on Option A of TSTF-493, Clarify Application of Setpoint Methodology for Limiting Safety System
102-07426-MLL/TNW ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Commitment Change Regarding TSTF-493, Clarify Application of Setpoint Methodology for LSSS Functions Page 2 Settings, by February 28, 2017. No changes to the allowable values or nominal trip setpoints will be requested in the submittal.
After a review of TSTF-493, Revision 4, APS concludes that the current station surveillance testing procedures implement the notes of Option A of TSTF-493. Similar notes already exist for parameters in the PVNGS TS for the RPS and ESFAS instrumentation, which serve to anchor these practices in surveillance procedures. Specifically, steam generator 1 and 2 -
low pressure, in RPS Tables 3.3.1-1 and 3.3.2-1 and ESFAS Table 3.3.5-1, and refueling water storage tank level - low, in ESFAS Table 3.3.5-1 contain similar notes.
APS will continue to implement these current practices to ensure the objectives of TSTF-493 are satisfied, obviating the need for submitting an LAR. The addition of the notes of TSTF-493 to the multitude of instruments in the RPS and ESFAS TS tables would be an administrative effort that complicates the TS tables, from a human factors perspective, with no change in plant operating practice.
The commitment has, therefore, been changed to read as follows:
The practices described in the notes of TSTF-493, Option A, will be retained in PVNGS surveillance procedures.
No new commitments are made by this letter. Should you have any questions concerning the content of this letter, please contact Michael DiLorenzo, Licensing Section Leader, at (623) 393-3495.
Sincerely, MLL/TNW/NTA cc:
K. M. Kennedy NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS M. M. Watford NRC NRR Project Manager C. A. Peabody NRC Senior Resident Inspector for PVNGS T. Morales Arizona Radiation Regulatory Agency (ARRA)
Lacal, Maria L(Z06149)
Digitally signed by Lacal, Maria L(Z06149)
DN: cn=Lacal, Maria L(Z06149)
Date: 2017.02.17 15:22:01
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