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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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AA 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 102-06060-DCM/DAF September 10, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529 and 50-530 Response to August 11, 2009, Request for Additional Information for the Review of the PVNGS License Renewal Application By letter no. 102-05937, dated December 11, 2008, Arizona Public Service Company (APS) submitted a license renewal application (LRA) for PVNGS Units 1, 2, and 3. By letter dated August 11, 2009, the NRC issued a request for additional Information (RAI) related to the PVNGS LRA. Enclosed is APS's response to the August 11, 2009, RAI.
APS makes no commitments in this letter. Should you need further information regarding this request, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on (Date)
Sincerely, DCM/RAS/DAF
Enclosure:
Response to August 11, 2009, Request for Additional Information for the Review of the Palo Verde Nuclear Generating Station License Renewal Application A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway -Comanche Peak - Diablo Canyon - Palo Verde - San Onofre - South Texas - Wolf Creek
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Response to August 11, 2009, Request for Additional Information for the Review of the Palo Verde Nuclear Generating Station License Renewal Application Page 2 cc: E. E. Collins Jr. NRC Region IV Regional Administrator J. R. Hall NRC NRR Project Manager R. I. Treadway NRC Senior Resident Inspector for PVNGS B. E. Holian NRC License Renewal Director L. M. Regner NRC License Renewal Project Manager
ENCLOSURE Response to August 11, 2009, Request for Additional Information for the Review of the Palo Verde Nuclear Generating Station License Renewal Application
Enclosure Response to August 11, 2009, Request for Additional Information for the Review of the Palo Verde Nuclear Generating Station License Renewal Application NRC RAI B2.1.32-1 Under Aging Management Programs of Appendix B, the applicant states that the Protective Coating Monitoring and Maintenance Program,Section XI.S8 of NUREG-1801, "Generic Aging Lessons Learned (GALL) Report," is not credited for aging management. Also, the Structures Monitoring Program in Appendix B, section B2.1.32, states that "Though coatings may have been applied to the external surfaces of structural members, no credit was taken for these coatings in the determination of aging effects for the underlying materials. The Structures Monitoring Program evaluates the condition of the coatings as an indication of the condition of the underlying materials." However, in addition to using the Protective Coating Monitoring and Maintenance Program to ensure the function of coated structures and components, the GALL Report states that "Proper maintenance of protective coatings inside containment is essential to ensure operability of post-accident safety systems that rely on water recycled through the containment sump/drain system." Although the licensee does not credit the program for aging management, there needs to be adequate assurance that there is proper maintenance of the protective coatings in containment, such that they will not degrade and become a debris source that may challenge the Emergency Core Cooling Systems performance. Therefore the staff requires the following additional information:
- 1. Please describe in detail, the coatings assessment program referenced in the supplemental response to GL 2004-02, dated February 28, 2008. How will the program ensure that there will be proper maintenance of the protective coatings inside containment and ensure operability of post-accident safety systems that rely on water recycled through the containment sump/drain system in the extended period of operation? Also, describe the frequency and scope of the inspections, acceptance criteria, and the qualification of personnel who perform containment coatings inspections.
APS Response to RAI B2.1.32-1 As noted in the RAI, the coatings program is not credited for Palo Verde Nuclear Generating Station (PVNGS) license renewal aging management and, as such, this program has not been included within the scope of license renewal. However, Arizona Public Service Company (APS) agrees that the coatings program is important for the Emergency Core Cooling System (ECCS) performance.
The Palo Verde Containment Coatings Condition Assessment procedure defines the in-service monitoring program for containment coatings to include service level I coatings and unqualified coatings. Inspection results are used to maintain coating system integrity and as an input into the mechanical design of the ECCS sump and input into the Mechanical Design/Nuclear Fuel Management Design Basis Accident (DBA) Loss-of-Coolant Accident (LOCA) Analysis. The procedure directs visual inspections of accessible coated surfaces of each area or room of containment to look for defects such as:
- Flaking/Peeling delamination
Enclosure Response to August 11, 2009, Request for Additional Information for the Review of the Palo Verde Nuclear Generating Station License Renewal Application
- Mechanical or physical damage Inspections are performed every operating cycle. Coatings identified as being degraded are documented in the corrective action process. The coating specialist reviews newly identified defects or damage to determine if further testing is required to identify the extent of the defect or damage and to answer any operability questions. Possible corrective actions include:
- Repair at a future date (bare substrate addressed)
Coatings inspectors are qualified to a certified coatings inspection program or are ANSI N45.2.6 certified.
Please note that by letter no. 102-05973, dated March 13, 2009, (Agencywide Document Access and Management System [ADAMS] Accession No. ML090830334) APS submitted Revision 1 to Supplemental Response to NRC Generic Letter 2004-02. This submittal provided a more detailed description of the PVNGS coatings program than that provided in the February 2008 GL 2004-02 supplemental response submittal.
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