Letter Sequence Other |
---|
|
|
MONTHYEARML1025101862010-08-30030 August 2010 Relief Request Serial #10-MN-001 Project stage: Request ML1105507702011-03-0303 March 2011 Relief 10-MN-001 for a Proposed Alternative to to Delay the Update to the Code of Record During the Fourth 10-Year Inservice Inspection (ISI) Interval Project stage: Other 2010-08-30
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000369/20240032024-11-0404 November 2024 Integrated Inspection Report 05000369/2024003 and 05000370/2024003 ML24303A4212024-10-30030 October 2024 Mcguire Nuclear Station, Units 1 & 2, Notification of an NRC Fire Protection Team Inspection FPTI NRC 05000369/2025010, 05000370/2025010 and Request for Information RFI IR 05000369/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000369/2024402 05000370/2024402 IR 05000369/20240052024-08-26026 August 2024 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2, (Report 05000369-2024005 and 05000370-2024005) IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20244032024-07-25025 July 2024 – Cyber Security Inspection Report 05000369/2024403 and 05000370/2024403 Rev IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf ML24100A8742024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 – Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 05000369/LER-1923-001, Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error2023-12-13013 December 2023 Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection – U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20234012023-08-0404 August 2023 – Security Baseline Inspection Report 05000369/2023401 and 05000370/2023401 (OUO-SRI) Cover IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station – Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 IR 05000369/20234202023-07-24024 July 2023 – Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23124A0862023-05-0303 May 2023 Cycle 29, Revision 1, Core Operating Limits Report (COLR) IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 2024-08-26
[Table view] Category:Safety Evaluation
MONTHYEARML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML21306A1592021-11-16016 November 2021 Request to Use Provisions of Later Edition and Addenda of the ASME Code, Section XI (EPID; L-2021-LLR-0048) ML21155A2132021-08-26026 August 2021 Plant ML21131A0262021-06-23023 June 2021 Issuance of Amendments to Change Technical Specification 3.8.1, to Reduce Emergency Diesel Generator Maximum Voltage ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20230A2052020-08-21021 August 2020 Relief Request RA-20-0031, Delay to Update the Code of Record for Inservice Inspection ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19217A3242019-08-14014 August 2019 Relief Request MC-SRV-NC-03, Alternate Testing for Pressurizer Power Operated Relief Valve Block Valve 2NC-35B ML19184A5852019-08-0808 August 2019 Issuance of Amendment Nos. 316 and 295 to Correct Editorial Error in Technical Specification 3.0 and Remove Expired Footnotes from TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1, and 3.8.4 ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19126A0302019-06-28028 June 2019 Issuance of Amendments to Technical Specification 3.8.1, AC Sources-Operating ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML19091A1942019-04-17017 April 2019 Safety Evaluation Input for License Amendment Request to Revise the Technical Specifications 3.8.1, AC Sources - Operating. ML18355A6102019-01-25025 January 2019 Issuance of Amendments to Revise the Licensing Basis for Protection from Tornado Generated Missiles ML18318A3582019-01-16016 January 2019 Issuance of Amendment Nos. 311 and 290 to Correct Non-Conservative Technical Specification 3.4.11, Pressurizer Power Operated Relief Valves Porvs) ML18277A3222018-11-19019 November 2018 Issuance of Amendments 310 and 289 to Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18009A8422018-01-31031 January 2018 Issuance of Amendments to Extend the Containment Type a Leak Rate Test Frequency to 15 Years and Type C Leak Rate Test Frequency to 75 Months (CAC Nos. MF9020 and MF9021; EPID L-2016-LLA-0032) ML17297A9172018-01-0505 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF9110 and MF9111; EPID L-2017-LLA-0161) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17271A0342017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 (CAC Nos. MF9101 - MF9107) ML17269A1982017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 ML17277A3132017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-340-A, Revision 3 (CAC Nos. MF9117 and MF9118; EPID L-2017-LLA-0169) ML17261B2182017-10-25025 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-315-A Revision 0 (CAC Nos. MF9112 and MF9113; EPID L-2017-LLA-0171) ML17269A0552017-10-25025 October 2017 McGuire, Units 1 and 2 - Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-283-A, Revision 3 (CAC NOS. MF9098 and MF9099) ML17244A1022017-09-25025 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF 285-A, Revision 1 ML17240A3542017-09-18018 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-269-A, Revision 2 ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) 2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 3, 2011 Mr. Regis T. Repko Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNIT 1 - RELIEF 10-MN-001 FOR A PROPOSED ALTERNATIVE TO DELAY THE UPDATE TO THE CODE OF RECORD DURING THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. ME4676)
Dear Mr. Repko:
By letter dated August 30, 2010, Duke Energy Carolinas, LLC (the licensee), submitted relief request 10-MN-001 for McGuire Nuclear Station, Unit 1 (McGuire 1), related to delaying the update to the Code of Record for the fourth 1O-year inservice inspection (lSI) interval. The third 10-year lSI interval for McGuire 1 ends on December 1, 2011. The licensee requested approval of a proposed alternative to the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (the Code) requirements for lSI. The proposed alternative would delay the required update of the McGuire 1 Code of Record for the fourth lSI interval until the time of the required update to the McGuire 2 Code of Record, scheduled for July 15, 2014.
The Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and, based on the information provided in the licensee's request for relief, the NRC staff has determined that the proposed alternative provides an acceptable level of quality and safety.
Therefore, pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(a)(3)(i), the NRC staff authorizes the use of the proposed alternative to delay the required update of the McGuire 1 Code of Record for the fourth lSI interval until the time of the required update to the McGuire 2 Code of Record.
R. Repko - 2 All other requirements of ASME Code.Section XI for which relief has not been specifically requested remain applicable. including third-party review by the Authorized Nuclear Inservice Inspector.
Sincerely.
0r (C--.____
Gloria Kulesa. Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear ReactorRegulation Docket No. 50-369
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF FOURTH 10-YEAR INTERVAL INSERVICE INSPECTION RELIEF NO. 10-MN-001 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNIT 1 DOCKET NO. 50-369
1.0 INTRODUCTION
By letter dated August 30. 2010 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML102510186), Duke Energy Carolinas, LLC (the licensee),
submitted Request for Relief 10-MN-001 for the McGuire Nuclear Station. Unit 1, (McGuire 1) requesting approval of a proposed alternative to delay updating the Code of Record for the fourth Inservice Inspection (lSI) interval until the time of the required update to the Code of Record for the fourth lSI interval for McGuire 2.
2.0 REGULATORY EVALUATION
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR). Part 50. Section 50.55a, paragraph 50.55a(g)(4), American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (the 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 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. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year inspection interval and subsequent 10-year inspection 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 inspection interval, subject to the limitations and modifications listed therein.
Paragraph 50.55a(a)(3) of 10 CFR Part 50 states that alternatives to the requirements of 10 CFR 50.55a(g) may be used, when authorized by the Nuclear Regulatory Commission (NRC), if (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff reviewed and evaluated the licensee's request pursuant to 10 CFR 50.55a(a)(3)(i).
Enclosure
-2
3.0 TECHNICAL EVALUATION
3.1 ASME Code Components Affected
ASME Class 1, 2, and 3 components and component supports.
Note: This relief request specifically excludes ASME Class MC components at McGuire 1.
3.2 Code Requirement Pursuant to 10 CFR 50.55a(g)(4)(ii), McGuire 1 is required to update its lSI program to the requirements of the latest Code edition and addenda incorporated by reference in 10 CFR 50.55a(b)(2) twelve months prior to the start of its subsequent 120-month lSI interval.
In the case of McGuire 1, the fourth 10-year lSI program Code of Record should reflect the ASME Code,Section XI, 2004 Edition, no Addenda. The third 10-year lSI program Code of Record is the 1998 Edition through the 2000 Addenda.
3.3 Licensee's Proposed Alternative and Basis The licensee requests authorization to delay the update of the McGuire 1 Code of Record for the fourth lSI interval until the time of the required update for McGuire 2. The McGuire 1 fourth lSI interval starts on December 1, 2011. McGuire 2 is scheduled to adopt the latest ASME Code edition and addenda incorporated by reference in 10 CFR 50.55a(b) twelve months prior to the start of its fourth lSI interval, which is scheduled to begin on July 15, 2014.
The McGuire 'I lSI program will continue with a revised 10-year program plan for the fourth interval that references the same Code of Record used for the third lSI interval, that is, the 1998 Edition through the 2000 Addenda of ASME Code,Section XI. This edition and addenda of the Code is the same as that currently being used for the third lSI interval program at McGuire 2. The licensee states that having two separate ASME Code editions implemented on a two-unit site can create procedural and programmatic differences that could potentially result in implementation errors, and that having both units on the same Code of Record provides many implementation benefits which will maintain the existing level of quality and safety and provide cohesive programs for lSI, repairs, replacements and pressure testing.
At the time of the required McGuire 2 Code update, the McGuire 1 lSI interval program will be revised to implement the updated Code of Record for the remainder of the McGuire 1 fourth lSI interval, which is expected to include the second and third inspection periods in their entirety (approximately 7 years).
3.4 Staff Evaluation The licensee requests authorization to have the lSI programs for McGuire 1 and McGuire 2 based on the same Code of Record. The licensee proposes that McGuire 1 will continue lSI inspections for the first inspection period of the fourth lSI interval in accordance with the 1998 Code Edition through the 2000 Addenda, with provisions and restrictions, until the time of the required McGuire 2 update. At the time of the McGuire 2 update, both units will be updated to the applicable Code Edition required by 10 CFR 50.55a(g)(4)(ii) for McGuire 2. The NRC staff
- 3 concurs with the licensee that having two different lSI programs based on separate editions and addenda of the ASME Code implemented for the two McGuire units can possibly create procedural and programmatic differences that could potentially result in implementation errors, and that having the lSI programs for both units based on the same Code edition and addenda can eliminate such differences and should provide for more cohesive programs for lSI, repairs, replacements, and pressure testing. Therefore, the NRC staff finds that delaying the Code of Record update will maintain the existing level of quality and safety and, thus, is acceptable.
The licensee states that the following limitations and modifications of 10 CFR SO.SSa(b)(2) shall apply when using the 1998 Edition through the 2000 Addenda:
Code Cases, if used, shall comply with the requirements specified in Regulatory Guide 1.147.
Use of the provisions of IWA-4340, "Mitigation of Defects by Modification," of Section XI of the ASME Code is prohibited except when specifically authorized by the NRC staff in accordance with 10 CFR SO.SSa(a)(3).
Repair and replacement activity provisions in IWA-4S40(c) of the 1998 Edition of ASME Code,Section XI, for pressure testing Class 1, 2, and 3 mechanical joints must be applied.
The NRC staff finds that the licensee's provisions, limitations and modifications for the use of the 1998 Edition through the 2000 Addenda of ASME Code,Section XI, meet the provisions, limitations and modifications specified in 10 CFR SO.SSa(b)(2) and, thus, are acceptable.
The licensee proposes to transition to the implementation of the McGuire 1 fourth lSI interval Code of Record by including the second and third inspection periods in their entirety. The NRC staff finds that this plan clearly defines an acceptable transition between the two Code editions, and finds that the licensee's proposed alternative will provide an acceptable level of quality and safety. The NRC staff also notes that it has previously authorized delay of the Code of Record for Comanche Peak Nuclear Power Plant, Unit 1, for the third 1O-year lSI interval by letter dated April 28. 2010 (ADAMS Accession No. ML100850122).
The NRC staff notes that for Class 1 and Class 2 piping, Examination Category B-F, B-J, C-F-1 and C-F-2 piping welds are inspected under a risk-informed lSI (RI-ISI) program through the end of the third interval by letter dated June 12,2002 (ADAMS Accession No. ML021480421).
and that 100% of the required RI-ISI inspections will be completed in the third lSI interval. At the end of the third interval, the RI-ISI program will need to be authorized if it is to be used in the fourth lSI interval.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the proposed alternative, to delay updating the fourth lSI interval Code of Record for McGuire 1 until the time of the fourth lSI interval McGuire 2 Code of Record update provides an acceptable level of quality and safety.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the
- 4 regulatory requirements set forth in 10 CFR SO.SSa(3)(i). Therefore, the NRC staff authorizes the proposed alternative at McGuire 1, until the time of the McGuire 2, Code of Record update, currently scheduled for July 1S, 2014.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Jay Wallace, NRR/DCI Date: March 3, 2011
R. Repko -2 All other requirements of ASME Code,Section XI for which relief has not been specifically requested remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Sincerely, IRA!
Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-369
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDciCpnb Resource LPL2-1 R/F RidsNrrLAMOBrien Resource (hard copy)
RidsAcrsAcnw_MailCTR Resource RidsNrrPMMcGuire Resource (hard copy)
RidsNrrDirsltsb Resource RidsOgcRp Resource RidsNrrDorlLpl2-1 Resource RidsRgn2MailCenter Resource RidsNrrDorlDpr Resource TLupold. NRR JWaliace, NRR ADAMS Accession No. ML110550770 *concurrence via email dated 2/9/11 ML110410172 OFFICE NRR/LPL2-1/PM INRR/LPL2-1/LA NRR/CPNB/BC NRR/LPL2-1/BC NRR/LPL2*1/PM NAME JThompson IMO'Brien TLupold* GKulesa JThompson DATE 2/28/11 02/09/11 313/11 3/3/11 OFFICIAL RECORD COpy