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MONTHYEARML0513003622005-05-0909 May 2005 Request to Use a Subsequent Edition and Addenda to ASME Boiler and Pressure Vessel Code Section XI for Repair/Replacement Activities (TAC Nos. MC6851/6852/6853) Project stage: Other 2005-05-09
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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
[Table view] Category:Safety Evaluation
MONTHYEARML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program 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 ML22334A0702022-12-15015 December 2022 Issuance of Amendment Nos. 220, 220, and 220, to Revise Technical Specifications to Adopt TSTF-487, Relocate DNB Parameters to the COLR ML22178A0042022-08-11011 August 2022 Issuance of Amendment Nos. 219, 219, and 219, to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump Ts to Address GSI-191 Issues ML22049A0572022-02-23023 February 2022 Relief Request 69 to Extend Inservice Inspection of Containment Tendon by Four Months Due to the Covid 19 Pandemic (EPID L 2022 Llr 0011 (Covid 19)) ML21347A0032021-12-22022 December 2021 Issuance of Amendment Nos. 217, 217, and 217 Regarding Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML21307A1312021-11-17017 November 2021 the Independent Spent Fuel Storage Installation - Order Approving Transfers of Control of Licenses for Minority Interests Subject to Expiring Leases (EPID L-2021-LLM-0003) (Letter) ML21225A0932021-08-17017 August 2021 Ng Station, Units 1, 2,& 3 - Issuance of Amendment Nos. 216, 216, and 216 Regarding Revision to Technical Specifications to Adopt TSTF-501, Rev.1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21118B0282021-05-25025 May 2021 Letter/Se Approving Indirect Transfer of Licenses for Units 1, 2, and 3, and the Independent Spent Fuel Storage Installation ML21105A3402021-04-21021 April 2021 Issuance of Amendment Nos. 215, 215, and 215 Revision to Technical Specifications to Adopt TSTF-563, Revision 0 ML21089A0102021-04-0202 April 2021 Relief Request 66 to Defer Inservice Inspection of Containment Tendon by One Year Due to Covid-19 Pandemic ML20350B8032021-02-0808 February 2021 Issuance of Amendment Nos. 214, 214, and 214 to Make Administrative Changes to the Technical Specifications ML20216A5392020-08-0606 August 2020 Relief Request 65 for Inspection of Reactor Pressure Vessel Bottom Mounted Instrument Nozzles and Pressurizer Surge Line Weld Overlay ML20163A0372020-07-31031 July 2020 the Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 213, 213, and 213 to Revise Emergency Plan Staff Augmentation Times ML20114E3252020-04-30030 April 2020 Relief Request 64 for Impractical Examinations for the Third 10-Year Inservice Inspection Interval ML20031C9472020-03-0404 March 2020 Nonproprietary, Issuance of Amendment Nos. 212, 212, and 212 to Revise Technical Specifications to Support the Implementation of Framatome High Thermal Performance Fuel ML20016A4582020-02-10010 February 2020 Issuance of Amendment Nos. 211, 211, 211, to Extend Implementation Date for Amendment Nos. 209, 209, and 209 Associated W/Initiative 4b That Permit the Use of Risk-Informed Completion Times on the TS ML19309F3042019-12-18018 December 2019 Issuance of Amendment Nos. 210, 210, and 210, to Revise Technical Specifications to Adopt Traveler TSTF-529, Revision 4,Clarify Use and Application ML19304C5622019-11-0505 November 2019 Safety Evaluation - Arizona Public Service Company - Palo Verde Nuclear Generating Station - License Amendment Request to Adopt TSTF-529 ML19085A5252019-05-29029 May 2019 Issuance of Amendments Nos. 209, 209, and 209 - Regarding Adoption of Risk Informed Completion Times in Technical Specifications (CAC Nos. MF6576, MF6577, and MF6578; EPID L-2015-LLA-0001) ML19107A3722019-04-19019 April 2019 Relief Request 62 Regarding Proposed Alternative Pressurizer Heater Sleeve Repairs ML19070A2182019-04-0303 April 2019 Issuance of Amendment Nos. 208, 208, and 208 - Regarding Response Time Testing of Pressure Transmitters ML19044A6412019-02-19019 February 2019 Relief Request No. 58 for the Third 10-Year Inservice Inspection Interval, Request for Relief from the American Society of Mechanical Engineers for Certain Class 1 and Class 2 Welds ML19037A0552019-02-19019 February 2019 Relief Requests 60 & 61 for the Fourth 10-Year Inservice Inspection Interval, Request for Relief from the American Society of Mechanical Engineers Half-Nozzle Repairs (EPID L-2018-LLR-0111 & EPID L-2018-LLR-0112) ML18285A0292018-10-19019 October 2018 Relief Request 59 for the Deferral of Reactor Vessel Beltline Region Interior Attachment Examinations ML18243A2802018-10-10010 October 2018 Issuance of Amendment Nos. 207, 207, and 207 to Adopt 10 CFR 50.69 (CAC Nos. MF9971, MF9972, and MF9973; EPID L-2017-LLA-0276) ML17254A4992017-09-27027 September 2017 Issuance of Amendment Nos. 204, 204, and 204 to Modify the Completion Date for Implementation of Milestone 8 of the Cyber Security Plan ML17188A4122017-07-28028 July 2017 Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendment Nos. 203, 203, and 203 to Revise Technical Specifications to Incorporate Updated Criticality Safety Analysis (CAC Nos. MF7138, MF7139, and MF7140) ML17123A4352017-05-16016 May 2017 Issuance of Amendment Nos. 202, 202, and 202 to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML17090A1642017-04-27027 April 2017 Issuance of Amendment No. 201, 201, and 201 to Revise Technical Specifications Related to Degraded and Loss of Voltage Relay Modifications ML17074A2092017-03-16016 March 2017 Relief Request GRR-01 to ASME Code Case OMN-20 for Third 10-Year Interval Pump and Valve Inservice Testing Program ML17004A0202017-01-0404 January 2017 Issuance of Amendment No. 200, Revise Technical Specification 3.8.1, AC Sources - Operating, for One-Time Extension of the Diesel Generator Completion Time, Risk-Informed (Emergency Circumstances) ML17003A0832017-01-0303 January 2017 Safety Evaluation Input Regarding Changes to Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML17004A2092017-01-0303 January 2017 Safety Evaluation Input for Palo Verde Nuclear Generating Station, Unit 3, Llcense Amendment Request for a One-Time Extension of the 3B Emergency Diesel Generator Completion Time ML17003A3892017-01-0303 January 2017 Safety Evaluation Input Regarding the Palo Verde Nuclear Generating Station Unit 3 Emergency Request to Extend Diesel Generator 3B Completion Time ML16358A4152016-12-23023 December 2016 Technical Specifications for One-Time Extension of Completion Time for Emergency Diesel Generator ML16358A6762016-12-23023 December 2016 Issuance of Amendment No. 199, Request for One-Time Extension of the Diesel Generator Completion Time (Emergency Circumstances) ML16180A1092016-09-0808 September 2016 Issuance of Amendment Nos. 198, 198, and 198, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. ML16194A3232016-07-22022 July 2016 Review and Approval of Request for Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 11-04A, Nuclear Generation Quality Assurance Program Description ML16088A2612016-07-20020 July 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16172A0382016-06-23023 June 2016 Relief Request 54 to Approve an Alternative to Flaw Removal for Reactor Coolant Pump 2A Suction Pressure Instrument Nozzle, for the Third 10-Year Inservice Inspection Interval ML16004A0132016-02-19019 February 2016 Issuance of Amendment No. 197, 197, and 197, Adopt Technical Specification Task Force Traveler TSTF-439-A, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML15266A0052015-09-25025 September 2015 Issuance of Amendment No. 196, Revise Technical Specification Surveillance Requirement 3.1.5.3 for Control Element Assembly 88 for the Remainder of Cycle 19 (Exigent Circumstances) ML15238B6612015-09-15015 September 2015 Relief Request 53, Alternative to ASME Code Section XI Requirements Related to Flaw Removal ML15070A1242015-03-30030 March 2015 Issuance of Amendment Nos. 195, 195, and 195, Adopt TSTF-486, Revision 2, Revise Mtc Surveillance for Startup Test Activity Reduction (STAR) Program (WCAP-16011) and TSTF-406, Revision 2 ML15079A0062015-03-30030 March 2015 Relief Request 52 - Request for Approval of Alternate to Flaw Removal, Flaw Characterization and Successive Examinations, for the Remainder of Its Useful Life ML15058A0292015-03-27027 March 2015 Staff Assessment Regarding Review of Pressurized-Water Reactor Vessel Internals Aging Management Program Plan ML14202A3782014-09-0909 September 2014 Issuance of Amendment Nos. 194, 194, and 194, Request to Revise TS 3.3.3, Control Element Assembly Calculators and TS 3.3.6, Engineered Safety Features Actuation System (ESFAS) Logic and Manual Trip (TAC Nos. MF2879-81) ML14115A0452014-06-25025 June 2014 Issuance of Amendment Nos. 193, 193, and 193, Adopt Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 ML14093A4072014-04-10010 April 2014 Relief Request 51, Alternative to ASME Code for Flaw Removal, Reactor Vessel Bottom-mounted Instrumentation Nozzle, Third 10-Year ISI Interval 2023-09-13
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May 9, 2005 Mr. Gregg R. Overbeck Senior Vice President, Nuclear Arizona Public Service Company P. O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION (PALO VERDE),
UNITS 1, 2, AND 3 - REQUEST TO USE A SUBSEQUENT EDITION AND ADDENDA TO AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
BOILER AND PRESSURE VESSEL CODE (CODE) SECTION XI FOR REPAIR/REPLACEMENT ACTIVITIES (TAC NOS. MC6851, MC6852, AND MC6853)
Dear Mr. Overbeck:
By letter dated April 29, 2005, Arizona Public Service Company submitted a request to use the 1998 Edition, no Addenda to ASME Code Section XI, for repair/replacement activities. The current inservice inspection (ISI) Code of record for Palo Verde, Units 1, 2, and 3, is the 1992 Edition with the 1992 Addenda. The authorization of the subsequent edition and addenda of the ASME Code will allow the use of eddy current examinations as an acceptable surface examination technique.
Paragraph 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations (10 CFR) states that inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided that they are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed in 10 CFR 50.55a(b) and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met.
Based on the enclosed Safety Evaluation, the NRC staff concludes that the proposed request is acceptable and authorizes the use of the 1998 Edition, no Addenda to ASME Code Section XI
for repair/replacement activities for the remainder of the current 10-year ISI intervals for Palo Verde, Units 1, 2, and 3. All other requirements of the ASME Code,Section III and XI for which relief has not been specifically requested and approved remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Sincerely,
/RA/
Robert A. Gramm, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN-50-529, and STN 50-530
Enclosure:
Safety Evaluation cc w/encl: See next page
for repair/replacement activities for the remainder of the current 10-year ISI intervals for Palo Verde, Units 1, 2, and 3. All other requirements of the ASME Code,Section III and XI for which relief has not been specifically requested and approved remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Sincerely,
/RA/
Robert A. Gramm, Chief, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN-50-529, and STN 50-530
Enclosure:
Safety Evaluation cc w/encl: See next page DISTRIBUTION:
PUBLIC RidsNrrDlpmLpdiv (HBerkow) RidsNrrPMMFields PDIV-2 r/f RidsAcrsAcnwMailCenter RidsRgn4MailCenter (TPruett)
RidsNrrLADBaxley RidsOgcRp TChan JDixon-Herrity ACCESSION NO: ML051300362 NRR-106 OFFICE PDIV-2/PM PDIV-1/LA EMCB OGC Nlo PDIV-2/SC NAME MFields LFeizollahi TChan DReddick RGramm for DBaxley DATE 5-9-05 5-9-05 05/04/05 5/9/05 5/9/05 Changes Only OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE A SUBSEQUENT EDITION AND ADDENDA TO AMERICAN SOCIETY FOR MECHANICAL ENGINEERS (ASME)
BOILER AND PRESSURE VESSEL CODE (CODE) SECTION XI FOR REPAIR/REPLACEMENT ACTIVITIES ARIZONA PUBLIC SERVICE COMPANY, ET AL.
PALO VERDE NUCLEAR GENERATING STATION (PALO VERDE), UNITS 1, 2, AND 3 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530
1.0 INTRODUCTION
By letter dated April 29, 2005, Arizona Public Service Company (the licensee) submitted a request to use the 1998 Edition, no Addenda to ASME Code Section XI for repair/replacement activities. The current inservice inspection (ISI) Code of record is the 1992 Edition with the 1992 Addenda for the Palo Verde Nuclear Generating Station (Palo Verde), Units 1, 2, and 3.
The authorization of the subsequent edition and addenda of the ASME Code will allow the use of eddy current examinations as an acceptable surface examination technique.
The licensee submitted this request in accordance with the guidance provided in NRC Regulatory Issue Summary (RIS) 2004-16, dated October 19, 2004. In this RIS, the NRC staff stated that licensees who wish to use provisions of subsequent editions and addenda of the ASME Code Section XI for activities, including repair/replacement activities, must receive prior NRC review and approval as required by section 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations (10 CFR).
2.0 REGULATORY REQUIREMENTS Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. Section 50.55a(g)(4)(ii) of 10 CFR requires that ISI examination of components and system pressure tests conducted during the first 10-year ISI interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
The repair, replacement, and modification of plant components are not explicitly mentioned in 10 CFR 50.55a(g)(4) and associated subparagraphs. However, these activities are specifically mentioned in ASME Code Section XI. The NRC staff considers that these activities are not separate and distinct from, but are included under, inservice examinations. Therefore, the requirements of 10 CFR 50.55a(g)(4)(iv) are applicable to repair/replacement activities.
Section 50.55a(g)(4)(iv) states that inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided that they are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed in 10 CFR 50.55a(b), and subject to Commission approval.
Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met. Currently, Section 50.55a(b)(2) incorporates by reference the ASME Code Section XI from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2003 Addenda (Division 1).
3.0 REQUEST TO USE A SUBSEQUENT EDITION AND ADDENDA TO ASME CODE SECTION XI FOR REPAIR/REPLACEMENT ACTIVITIES 3.1 Current Code Requirements The current ASME Section XI Code of record for Palo Verde, Units 1, 2, and 3, 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.
3.2 Proposed Alternative Code Edition and Requirements The licensee proposes to use the 1998 Edition, no Addenda of the ASME Section XI Code for repair/replacement activities. 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.
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.
4.0 TECHNICAL EVALUATION
The NRC staff evaluated the licensee's request using the criteria contained in 10 CFR 50.55a(g)(4)(iv), which states that inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda of the ASME Code provided certain conditions are satisfied.
The first condition is that the proposed edition and addenda is incorporated by reference in 10 CFR 50.55a(b). Currently, Section 50.55a(b)(2) incorporates by reference the ASME Code Section XI from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2003 Addenda (Division 1), which includes the 1998 Edition, no Addenda of the ASME Section XI Code proposed by the licensee.
The second condition is that the limitations and modifications listed in 10 CFR 50.55a(b) are satisfied for the specific use of the proposed subsequent Code edition and addenda. There are no restrictions specified in 10 CFR 50.55a(b) for the portion of the 1998 Edition, no Addenda of the ASME Section XI Code that the licensee proposes to use.
The third condition is that if portions of subsequent Code editions or addenda are used, all related requirements of the respective editions or addenda must be met. The NRC staff is satisfied that the licensee has listed all related requirements in the 1998 Edition, no Addenda of the ASME Section XI Code that are relevant to the stated repair/replacement activities.
Based on the above, the NRC staff finds that the conditions of 10 CFR 50.55a(g)(4)(iv) are satisfied and that the licensee<s request to use the 1998 Edition, no Addenda of the ASME Code Section XI for repair/replacement activities is acceptable.
5.0 CONCLUSION
The NRC staff concludes that the proposed request is acceptable and authorizes the use of the ASME Code Section XI, 1998 Edition, no Addenda, for the specified repair/replacement activities for the remainder of the current 10-year ISI intervals for Palo Verde, Units 1, 2, and 3.
All other requirements of the ASME Code,Section III and XI for which relief has not been specifically requested and approved remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: M. Fields Date: May 9, 2005
Palo Verde Generating Station, Units 1, 2, and 3 cc:
Mr. Steve Olea Mr. John Taylor Arizona Corporation Commission Public Service Company of New Mexico 1200 W. Washington Street 2401 Aztec NE, MS Z110 Phoenix, AZ 85007 Albuquerque, NM 87107-4224 Douglas Kent Porter Ms. Cheryl Adams Senior Counsel Southern California Edison Company Southern California Edison Company 5000 Pacific Coast Hwy Bldg DIN Law Department, Generation Resources San Clemente, CA 92672 P.O. Box 800 Rosemead, CA 91770 Mr. Robert Henry Salt River Project Senior Resident Inspector 6504 East Thomas Road U.S. Nuclear Regulatory Commission Scottsdale, AZ 85251 P. O. Box 40 Buckeye, AZ 85326 Mr. Jeffrey T. Weikert Assistant General Counsel Regional Administrator, Region IV El Paso Electric Company U.S. Nuclear Regulatory Commission Mail Location 167 Harris Tower & Pavillion 123 W. Mills 611 Ryan Plaza Drive, Suite 400 El Paso, TX 79901 Arlington, TX 76011-8064 Mr. John Schumann Chairman Los Angeles Department of Water & Power Maricopa County Board of Supervisors Southern California Public Power Authority 301 W. Jefferson, 10th Floor P.O. Box 51111, Room 1255-C Phoenix, AZ 85003 Los Angeles, CA 90051-0100 Mr. Aubrey V. Godwin, Director Brian Almon Arizona Radiation Regulatory Agency Public Utility Commission 4814 South 40 Street William B. Travis Building Phoenix, AZ 85040 P. O. Box 13326 1701 North Congress Avenue Mr. Craig K. Seaman, Director Austin, TX 78701-3326 Regulatory Affairs/Nuclear Assurance Palo Verde Nuclear Generating Station Mail Station 7636 Phoenix, AZ 85072-2034 Mr. Hector R. Puente Vice President, Power Generation El Paso Electric Company 310 E. Palm Lane, Suite 310 Phoenix, AZ 85004