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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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v - So 10 CFR 50.55a(g)(4)(Iv)
David Mauldin Vice President Mail Station 7605 Palo Verde Nuclear Nuclear Engineering Tel: 623-393-5553 PO Box 52034 Generating Station and Support Fax: 623-393-6077 Phoenix, Arizona 85072-2034 102-05259-CDM/CKS/TNW April 29, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Docket Nos. STN 50-52815291530 Request to Use a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section Xi for Repair/Replacement Activities at PVNGS in Accordance with 10 CFR 50.55a(g)(4)(iv)
In accordance with the guidance provided in NRC Regulatory Issue Summary (RIS) 2004-16, "Use of Later Editions and Addenda to ASME Code Section Xl For Repair/Replacement Activities" dated October 19, 2004 and in accordance with 10 CFR 50.55a(g)(4)(iv), APS hereby requests NRC approval to use a later Edition of the ASME Boiler and Pressure Vessel Code. Specifically, APS requests approval to use ASME Section Xl, 1998 Edition, no Addenda, paragraph IWA 4422.2.1(a), "Defect Removal without Welding or Brazing" and paragraph IWA 2220, "Surface Examination" as described in the enclosure to this letter. All applicable related requirements to the Edition and Addenda of the ASME Code are also listed in the enclosure.
The need for this request originated from inspections performed on the reactor vessel head vent line nozzle during the current Unit 2 refueling outage as required by the First Revised Order (EA-03-009), Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors. The current ASME Code of record for PVNGS is the 1992 Edition with 1992 Addenda which does not allow the use of eddy current examination as a surface examination to verify that indications have been removed. The use of the later edition and addenda of the ASME code will allow APS to use eddy current examinations as a surface examination to verify the indications have been removed from the reactor vessel vent line nozzle.
APS requests NRC approval to use the later edition and addenda of the ASME code identified in the enclosure to this letter at PVNGS Units 1, 2 and 3 for the remainder of A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
U. S. Nuclear Regulatory Commission - Page 2 ATTN: Document Control Desk Request to Use a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section Xl for Repair/Replacement Activities at PVNGS in Accordance with 10 CFR 50.55a(g)(4)(iv) their respective second 10-year Inservice Inspection Intervals. It is requested that the NRC provide their approval prior to Unit 2 entering Mode 2 (currently scheduled for the week of May 9, 2005) in order to support the restart of PVNGS Unit 2 from the refueling outage.
There are no commitments being made in this letter. If you have any questions, please contact Thomas N.Weber at (623) 393-5764.
Sincerely, CDM/CKS/TNW
Enclosure:
Request to Use a Later Edition and Addenda of the ASME Code per 10 CFR 50.55a(g)(4)(iv) and RIS 2004-16 cc: B. S. Mallett NRC Region IVRegional Administrator M. B. Fields NRC NRR Project Manager G. G. Warnick NRC Senior Resident Inspector for PVNGS
Enclosure Request to Use a Later Edition and Addenda of the ASME Code per 10 CFR 50.55a(g)(4)(v) and RIS 2004-16
Request to Use a Later Edition and Addenda of the ASME Code per 10 CFR 50.55a(g)(4)(iv) and RIS 2004-16 I. Applicable Code Edition and Requirements The current ASME Code of record for PVNGS is the 1992 Edition with 1992 Addenda. The applicable code requirements in the 1992 Edition with 1992 Addenda are as follows:
IWA-4331, "Defect Removal" (a) After final grinding, the affected surfaces, including surfaces of cavities prepared for welding, shall be examined by the magnetic particle or liquid penetrant method to ensure that the indication has been reduced to an acceptable limit in accordance with IWA-3000.
IWA-2220, "Surface Examination" (a) A surface examination indicates the presence of surface discontinuities.
It may be conducted by either a magnetic particle or a liquid penetrant method.
(b) Any linear indication that exceeds the allowable linear surface flaw standards shall be recorded.
IWA-2221, "Magnetic Particle Examination" Magnetic particle examination shall be conducted in accordance with Article 7 of Section V.
IWA-2222, "Liquid Penetrant Examination" Liquid penetrant examination shall be conducted in accordance with Article 6 of Section V.
II. Proposed Alternative Code Edition and Requirements The proposed code is the 1998 Edition, no Addenda. The applicable code Requirements from that code are as follows:
IWA-4422.2.1, "Defect Removal without Welding or Brazing" (a) After removal of defects detected by visual or surface examinations, surface examination of the defect removal area shall be performed.
IWA-2220, "Surface Examination" (a) A surface examination indicates the presence of surface discontinuities.
It may be conducted by a magnetic particle, a liquid penetrant, or an eddy current method.
(b) Any linear indication that exceeds the allowable linear surface flaw standards shall be recorded.
Enclosure Page 1
Itl i,, 4 1 -, ."Ij; ',!, a Request to Use a Later Edition and Addenda of the ASME Code per 10 CFR 50.55a(g)(4)(iv) and RIS 2004-16 IWA-2221, "Magnetic Particle Examination" (a) Magnetic particle examination shall be conducted in accordance with Section V, Article 7.
(b) Magnetic particle examination of coated materials shall be conducted in accordance with Section V, Article 7, Appendix I.
IWA-2222, "Liquid Penetrant Examination" Liquid penetrant examination shall be conducted in accordance with Section V, Article 6.
IWA-2223, "Eddy Current Examination" Eddy current examination for detection of surface flaws shall be conducted in accordance with Appendix IV.
Enclosure Page 2