Letter Sequence Approval |
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EPID:L-2023-LLR-0017, Presentation Slides for Information Call on 4/13/23 N2E Recirc Discharge Nozzle Weld Repair 2nd Request for Alternative (Approved, Closed) |
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Category:Request for Code Relief or Alternative
MONTHYEARNMP2L2851, 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
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
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
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)
NMP1L3526, Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication2023-04-13013 April 2023
Submittal of Emergency Relief Request I5R-14 Concerning a Proposed Alternative Associated with N2E Safe End-to-Nozzle Dissimilar Metal Weld Repair with Laminar Indication
ML23094A1422023-04-0505 April 2023
Approval of Alternative Request I5R-13 to Utilize Specific Provisions of Code Case N-716-3
NMP1L3519, Submittal of Emergency 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)2023-03-30030 March 2023
Submittal of Emergency 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)
NMP1L3518, Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 12023-03-29029 March 2023
Proposed Alternative to Utilize Specific Provisions of Code Case N-716-3, Alternative Classification and Examination Requirements Section XI, Division 1
NMP1L3485, Proposed Alternative Associated with a Weld Overlay Repair to the Torus2022-12-0808 December 2022
Proposed Alternative Associated with a Weld Overlay Repair to the Torus
RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022
Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
NMP1L3454, Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-03-0202 March 2022
Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps
NMP1L3366, Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2020-12-0101 December 2020
Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting
2023-08-04
[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
[Table view] |
Text
June 22, 2023 NINE MILE POINT NUCLEAR STATION, UNIT NO. 1- AUTHORIZATION AND SAFETY EVALUATION FOR ALTERNATIVE RELIEF REQUEST I5R-14 ASSOCIATED WITH N2E SAFE END-TO-NOZZLE DISSIMILAR METAL WELD REPAIR WITH LAMINAR INDICATION (EPID: L-2023-LLR-0017)
LICENSEE INFORMATION Recipients Name and Address: Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Rd Warrenville, IL 60555 Licensee: Constellation Energy Generation, LLC (CEG)
Plant Name and Unit: Nine Mile Point Nuclear Station, Unit No. 1 Docket No.: 50-220 APPLICATION INFORMATION Application Date: April 13, 2023 Application Agencywide Documents Access and Management System (ADAMS)
Accession No.: ML23103A404 Licensee Proposed Alternative No. or Identifier: I5R-14 Applicable Inservice Inspection (ISI) Program Interval and Interval Start/End Dates: The fifth 10-year ISI interval for Nine Mile Point Nuclear Station, Unit No. 1 (Nine Mile Point, Unit 1),
began on April 23, 2019, and is scheduled to end August 22, 2029.
Alternative Provision: The applicant requested an alternative under Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.55a(z)(1).
ISI Requirement: American Society of Mechanical Engineer (ASME) Boiler & Pressure Vessels Code (Code),Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, IWA-4411, IWA-4411(a), IWA-4411(b), IWA-4412, IWA-4611and IWB-3640.
Applicable Code Edition and Addenda: The applicable code of record for the fifth 10-year ISI interval at Nine Mile Point, Unit 1, is ASME Code,Section XI, 2013 Edition.
Verbal Authorization:
On April 14, 2023 (ML23104A347), the U.S. Nuclear Regulatory Commission (NRC) verbally authorized the use of Relief Request I5R-14 at Nine Mile Point, Unit 1, on the basis that the proposed alternative provides an acceptable level of quality and safety, and the structural integrity and leak tightness of the subject overlaid weld will be maintained until the end of the next refueling outage (N1R28). This safety evaluation documents the technical basis for the NRC's verbal authorization.
Background:
On March 31, 2023 (ML23090A130), the NRC verbally authorized the use of Relief Request I5R-11 at Nine Mile Point, Unit 1, on the basis that the proposed alternative provides an acceptable level of quality and safety, and the structural integrity and leak tightness of the subject overlaid weld will be maintained until the end of the next refueling outage (N1R28).
Relief Request I5R-11 proposed a design weld overlay (WOL) on N2E safe end-to-nozzle dissimilar metal (DM) weld 32-WD-208. Relief Request I5R-11 is based on Code Cases N-740-2, N-638-10 and ASME Code Section XI, Appendix Q. The examination acceptance criteria for the WOL are based on the acceptance criteria in Code Case N-740-2.
Upon examination of the completed weld overlay, the licensee discovered three weld indications, identified as laminar indications 1, 2, and 3. Indication (flaw) number 2 does not meet the acceptance criteria in Code Case N-740-2. The current proposed alternative, Relief Request I5R-14, seeks to use WOL acceptance criteria in Section XI, Non-Mandatory Appendix Q, in lieu of the acceptance criteria specified in Code Case N-740-2.
The applicable Code requirements for which the licensee seeks relief are the same for I5R-11 and I5R-14. The applicable Code requirements are ASME Code Section IX, IWA-4411, IWA-4411(a), IWA-4411(b), IWA-4412, IWA-4611, and IWB-3640.
Brief Description of the Proposed Alternative:
Pursuant to 10 CFR 50.55a(z)(1), CEG proposes an alternative to the ASME Code requirements as specified above to permit a laminar flaw (indication 2) to remain in place for the upcoming cycle at Nine Mile Point, Unit 1.
The laminar flaw acceptance criteria of Code Case N-740-2 (as verbally authorized by the NRC for Relief Request I5R-11, ML23090A130) will not be used for indication 2. In lieu of these requirements, the flaw acceptance criteria of ASME Section XI, Non-Mandatory Appendix Q, Section Q-4100 will be met.
This alternative is proposed for use until the end of the Nine Mile Point, Unit 1 refueling outage N1R28 in 2025 during which a full structural WOL repair will be performed on the N2E safe end-to-nozzle weld.
For additional details on the licensees request, please refer to the documents located at the ADAMS Accession No(s) identified above.
STAFF EVALUATION As stated above, the licensees NRC approved alternative to install a design WOL on N2E safe end-to-nozzle DM weld 32-WD-208 was verbally approved on March 31, 2023, and specifies that the acceptance criteria for the WOL will be the acceptance criteria listed in Code Case N-740-2. Code Case N-740-2 Section 3(a)(3)(a) specifies the acceptance standards of Section XI, IWB-3514, with the additional limitations that the total laminar flaw area shall not exceed 10 percent of the weld surface area and that no linear dimension of the laminar flaw area shall exceed the greater of 3 inches (76 mm) or 10 percent of the pipe circumference.
Laminar flaw (indication 2) was measured at 0.3 inches wide and approximately 12.2 inches long. The pipe diameter is 91.3 inches resulting a flaw with a length representing 13.4 percent of the pipe dimeter. Therefore, the WOL (flaw) indication 2 does not meet the second limitation in Code Case N-740-2, Section 3(a)(3)(a).
Appendix Q, Q-4000(c)(1) requires that laminar flaws meet the acceptance standards of Table IWB-3514-3, which allows a laminal flaw area of 7.5-in.2 but does not have the limitation in N-740-2 that no linear dimension of a laminar flaw area shall exceed the greater of 3 inches (76 mm) or 10 percent of the pipe circumference. The staff notes that the area of laminar flaw 2 is 3.66-in.2 and the total area of all laminar flaws (indications 1, 2 and 3) added together is 6.37 in.2 Figures showing the design WOL and the location laminar flaw number 2 and indications 1 and 3, in relation to the original axial flaw that was mitigated by the design WOL, can be found on page 4 of 6 in the licensees submittal dated April 13, 2023. Laminar flaw (indication 2), the subject of the currently proposed alternative, is located at the interface of the stainless-steel safe end and the ER 309L buffer layer, which is applied to mitigate potential welding issue if Alloy 52M were to be placed directly on the stainless-steel safe end material.
Laminar flaw (indication 2) is 1.5 inches from the toe of the original weld and approximately 22.5 inches clockwise from the original axial flaw. This laminar flaw is embedded and is therefore not in contact with reactor coolant. Laminar flaw (indication 2) is located sufficiently far from the original flaw to not impact the ability to examine the required NDE volume including the susceptible material (Alloy 82/182) in DM weld 32-WD-208. The licensee performed a bounding analysis of the laminar flaw by assuming a 0.3-inch-wide laminar flaw 360 degrees around the pipe, taking into account internal pressure and a bending moment. The staff finds this conservative given that the assumed flaw is substantially larger than the actual flaw. The analysis shows an insignificant difference in the applied stress with and without the laminar flaw.
Hence, the laminar flaw has no impact on the material performance of the weld overlay.
Therefore, the NRC staff finds the licensees proposed alternative acceptable because the axial flaw is not near the laminar flaw, the licensees analysis shows that the laminar flaw does not significantly increase applied stresses, and Appendix Q provides appropriate acceptance criteria for the subject laminar flaw for the one operating cycle duration requested under Relief Request I5R-14.
CONCLUSION The NRC staff has determined that the licensees proposed alternative provides an acceptable level of quality and safety, and that the structural integrity and leak tightness of the subject overlaid weld will be maintained until the end of the next refueling outage (N1R28). The NRC concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1).
The NRC staff authorizes the use of proposed alternative, Relief Request I5R-14, at Nine Mile Point, Unit 1, until the next refueling outage (N1R28).
All other ASME BPV Code,Section XI requirements for which an alternative was not specifically requested and authorized remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: Robert Davis Date: June 22, 2023 Digitally signed by Hipolito Hipolito J. J. Gonzalez Date: 2023.06.22 Gonzalez 15:52:57 -04'00' Hipólito J. González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc: Listserv
ML23156A683 NRC-001 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DNRL/NPHP/BC NAME RGuzman KEntz MMitchell DATE 06/06/2023 06/08/2023 06/01/2023 OFFICE NRR/DORL/LPL1/BC NAME HGonzález DATE 06/22/2023
