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MONTHYEARML1311407912013-04-24024 April 2013 MF1316 & MF1317 - Acceptance E-mail to Licensee-Request to Use Later Edition and Addenda of ASME Code Project stage: Other ML14064A3392014-03-14014 March 2014 Request for Approval to Use a Later ASME Code Section XI Edition and Addenda for Examination Categories B-L-1, B-M-1, and C-G Project stage: Other 2013-04-24
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Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 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 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 ML23156A6832023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-14 ML23156A6822023-06-22022 June 2023 Authorization and Safety Evaluation of Alternative Relief Request I5R-11 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23103A1912023-04-20020 April 2023 Request for Threshold Determination Under 10 CFR 50.80 ML23082A3502023-04-17017 April 2023 Issuance of Amendment No. 192, Revision of Surveillance Requirements Associated with Emergency Diesel Generator Testing ML23094A1422023-04-0505 April 2023 Approval of Alternative Request I5R-13 to Utilize Specific Provisions of Code Case N-716-3 ML23025A4122023-02-28028 February 2023 Issuance of Amendment No. 248 to Revise Alternative Source Term Calculation for Main Steam Isolation Valve Leakage and Non-MSIV Leakage ML22339A0582022-12-21021 December 2022 Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22061A0402022-03-11011 March 2022 Relief Request Associated with Excess Flow Check Valves ML22033A3102022-03-0404 March 2022 Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21295A7342021-11-15015 November 2021 Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21256A1792021-11-0202 November 2021 Issuance of Amendment No. 246 Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21140A1532021-06-0303 June 2021 Correction to April 22, 2021 Safety Evaluation for Requests for Alternative to the Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Program Interval ML21082A2212021-04-29029 April 2021 Issuance of Amendment No. 186, Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML21109A2162021-04-22022 April 2021 Proposed Alternative to Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Interval ML21105A3382021-04-22022 April 2021 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Examination Coverage of Certain Class 1 and 2 Component Welds ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21049A0062021-03-16016 March 2021 Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve ML21049A0242021-02-23023 February 2021 Alternative Request to the Requirements of the ASME OM Code for the Testing Intervals for the Instrument-Line Flow Check Valves ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20332A1152021-01-29029 January 2021 Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20241A1902020-10-20020 October 2020 Issuance of Amendment No. 182 to Change Allowable Main Steam Isolation Valve Leak Rates ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20141L0532020-06-0202 June 2020 Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19301B0052019-11-25025 November 2019 Issuance of Amendment No. 239 Administrative Edits to the Technical Specifications ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques 2023-08-21
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 14, 2014 Mr. Christopher Costanzo Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NOS. 1 AND 2- RE: REQUEST FOR APPROVAL TO USE A LATER ASME CODE SECTION XI EDITION AND ADDENDA FOR EXAMINATION CATEGORIES B-L-1, B-M-1, AND C-G (TAC NOS. MF1316 AND MF1317)
Dear Mr. Costanzo:
By letter dated March 26, 2013, Nine Mile Point Nuclear Station, LLC (the licensee) submitted a request to the Nuclear Regulatory Commission (NRC) for the use of alternatives to certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code),Section XI requirements at Nine Mile Point Nuclear Station, Unit Nos. 1 and 2 (NMP1 and NMP2).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.55a(g)(4)(iv), the licensee requested to use ASME Section XI, 2007 Edition through the 2008 Addenda, for Examination Categories B-L-1, B-M-1, and C-G, for in-service inspection items subject to the limitations and modifications listed in 10 CFR 50.55a(b).
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff approves the licensee's request to use the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI for Examination Categories B-L-1, B-M-1 and C-G at NMP1 for the remainder of the Fourth lSI Interval (scheduled to be completed August 22, 2019) and at NMP2 for the remainder of the Third lSI Interval (scheduled to be completed April 4, 2018).
C. Constanzo 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 lnservice Inspector.
If you have any questions, please contact the Nine Mile Point Nuclear Station Project Manager, Bhalchandra Vaidya, at (301) 415-3308.
Sincerely, Benjamin G. Beasley, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-41 0
Enclosure:
Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR APPROVAL TO USE A LATER ASME CODE SECTION XI EDITION AND ADDENDA FOR EXAMINATION CATEGORIES B-L-1, B-M-1. AND C-G NINE MILE POINT NUCLEAR STATION. LCC NINE MILE POINT NUCLEAR STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-220 AND 50-410
1.0 INTRODUCTION
By letter dated March 26, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13088A045), Nine Mile Point Nuclear Station, LLC (the licensee),
submitted a request to the Nuclear Regulatory Commission (NRC) for the use of a subsequent edition and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI for inservice examinations of certain components, for Nine Mile Point Nuclear Station, Units Nos. 1 and 2 (NMP1 and NMP2), for the NMP1 fourth ten-year inservice inspection (lSI) interval and for the NMP2 third ten-year lSI interval.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(g)(4)(iv),
the licensee requested to use the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI, subject to the conditions listed in 10 CFR 50.55a(b), for examinations of Examination Category B-L-1, B-M-1 and C-G components at NMP1 and NMP2 for the remainder of the current 10-year inservice inspection intervals.
2.0 REGULATORY REQUIREMENTS The NRC staff notes that in its request the licensee proposes an alternative to the requirements of the ASME Code, i.e., the use of a later edition of the Code in accordance with 10 CFR 50.55a(g)(4)(iv). The NRC staff also notes that 10 CFR 50.55a(g)(4)(iv) states, in part that:
lnservice 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 conditions 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.
Given that the licensee has proposed the use of a later edition of the ASME Code pursuant to 10 CFR 50.55a(g)(4)(iv) and that 10 CFR 50.55a(g)(4)(iv) specifically permits the use of later Enclosure
editions of the ASME Code subject to technical criteria which will be considered below, the NRC staff finds that regulatory authority exists to authorize the use of a subsequent edition of the ASME Code, as requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 The Licensee's Request The ASME Code components affected by the licensee's request are as follows:
ASME Section XI, Examination Categories:
- B-L-1, Pressure Retaining Welds in Pump Casings
- B-M-1, Pressure Retaining Welds in Valve Bodies
- C-G, Pressure Retaining Welds in Pumps and Valves The Code of Record for the current NMP1 and NMP2 lSI intervals for Code Class 1, 2 and 3 components is the ASME Section XI, 2004 Edition. The examinations would not be required to be performed under the Code of Record until the last period of the current inspection interval.
The current NMP1 and NMP2 lSI intervals began and are scheduled to end as shown below:
Unit 1 - 41h 10-year interval -August 23, 2009 to August 22, 2019 Unit 2 - 3rd 10-year interval -April 5, 2008 to April 4, 2018 In lieu of the current Code of Record, ASME Section XI, 2004 Edition, the licensee proposes using the ASME Section XI, 2007 Edition through the 2008 Addenda for Category B-L-1, B-M-1 and C-G components. The licensee noted that examination categories B-L-1, B-M-1, and C-G are not included in the 2007 Edition through the 2008 Addenda of the Code.
3.2 NRC Staff Evaluation Paragraph 10 CFR 50.55a(g)(4)(iv) contains 4 criteria which must be met prior to use of a subsequent edition of the ASME Code. These criteria are:
- 1. The proposed edition/addendum of the ASME Code is incorporated by reference in 10 CFR 50.55a(b).
- 2. The proposed edition/addendum of the ASME Code is subject to the conditions listed in 10 CFR 50.55a(b).
- 3. The licensee shall request Commission approval to use the proposed edition/addendum of the ASME Code.
- 4. If only portions of editions or addenda are to be used all related requirements of the respective editions or addenda must be met.
In evaluating the first criterion, i.e., that the proposed edition/addendum of the Code has been incorporated by reference in 10 CFR 50.55a(b), the NRC staff notes that 10 CFR 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 through the 2007 Edition with the 2008 Addenda, which was proposed by the licensee. Therefore, the NRC finds that the first criterion has been satisfied.
In evaluating the second criterion, i.e., that the conditions listed in 10 CFR 50.55a(b) are satisfied for the specific proposed subsequent edition and addenda of the ASME Code,Section XI, the NRC staff notes that 10 CFR 50.55a(b) sets no conditions on Examination Categories 8-L-1, 8-M-1 and C-G of the 2007 Edition, 2008 Addenda of the ASME Code,Section XI. Therefore, the NRC staff finds that the second criterion has been satisfied.
In evaluating the third criterion, i.e., that the licensee shall request Commission approval to use the proposed edition/addendum of the ASME Code, the NRC staff notes that the licensee's relief request constitutes a request to the Commission for approval to use a subsequent edition/addendum of the ASME Code. Therefore, the NRC staff finds that the third criterion has been satisfied.
In evaluating the fourth criterion, i.e., that if portions of subsequent editions or addenda of the ASME Code,Section XI 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 Examination Categories 8-L-1, 8-M-1 and C-G of the 2007 Edition, 2008 Addenda of the ASME Code,Section XI. Therefore, the NRC staff finds that the fourth criterion has been satisfied.
Based on the above, the NRC staff finds that the criteria contained in 10 CFR 50.55a(g)(4)(iv) are satisfied and that the licensee's request to use the 2007 Edition, 2008 Addenda of the ASME Code Section XI for Examination Categories 8-L-1, 8-M-1 and C-G is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the use of a subsequent Edition of ASME Code,Section XI requirements is acceptable. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff authorizes the use of the 2007 Edition through the 2008 Addenda of the ASME Code,Section XI for Examination Categories 8-L-1, 8-M-1 and C-G for the remainder of the NMP1 fourth 10-year lSI interval and the remainder of the NMP2 third 10-year lSI interval which end on August 22, 2019 and April4, 2018 respectively.
All other requirements of the ASME Code for which relief has not been specifically requested and authorized remain applicable, including a third party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: Keith M. Hoffman Date: March 14, 2014
ML14064A339 '*) No Substantial change to SE Input Memo OFFICE LPL 1-1/PM LPL 1-1/LA NRRIEPNB/BC (*) LPL 1-1/BC NAME BVaidya KGoldstein DAlley for Tlupold BBeasley DATE 03/06/14 03/06/14 03/05/14 03/14/14