Letter Sequence Approval |
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EPID:L-2022-LLR-0036, Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Performance Monitoring of Pressurizer Welds at Byron Nuclear Station (Byron) and Braidwood Nuclear Station (Braidwood) (Approved, Closed) |
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MONTHYEARRS-22-030, Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022
Submittal of Relief Request Associated with the Sixth Inservice Inspection Interval
Project stage: Request
PMNS20220331, Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Performance Monitoring of Pressurizer Welds at Byron Nuclear Station (Byron) and Braidwood Nuclear Station (Braidwood)2022-03-31031 March 2022
Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Performance Monitoring of Pressurizer Welds at Byron Nuclear Station (Byron) and Braidwood Nuclear Station (Braidwood)
Project stage: Request
ML22101A0932022-04-11011 April 2022
NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Relief I6R-01 Related to SLC Nozzle Inner Radius Inspection
Project stage: Acceptance Review
ML22111A2852022-05-0909 May 2022
Summary of April 4, 2022, Meeting Between the U.S. NRC and Constellation Energy Generation, LLC, Regarding Performance Monitoring of Pressurizer Welds (EPIDs L-2022-LLR-0035/36)
Project stage: Meeting
ML22206A0352022-07-13013 July 2022
NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection
Project stage: Draft RAI
RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022
Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval
Project stage: Response to RAI
ML22327A2632022-11-30030 November 2022
Authorization and Safety Evaluation for Alternative Request No. I6R-01, Rev. 0
Project stage: Approval
2022-04-11
[Table View] |
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Category:Code Relief or Alternative
MONTHYEARML23125A0612023-05-0808 May 2023
Proposed Alternative to the Requirements of the ASME Code
ML23041A4262023-02-14014 February 2023
Proposed Alternative to the Requirements of the ASME OM Code
ML23033A0982023-02-0303 February 2023
Authorization and Safety Evaluation for Alternative Request I6R-09, Revision 0,
ML22332A5492022-12-21021 December 2022
Proposed Alternative to the Requirements of the ASME OM Code
ML22327A2632022-11-30030 November 2022
Authorization and Safety Evaluation for Alternative Request No. I6R-01, Rev. 0
ML22256A1152022-09-29029 September 2022
Proposed Alternative to the Requirements of the ASME OM Code
ML22265A0862022-09-28028 September 2022
Proposed Alternative to the Requirements of the ASME OM Code
ML22264A1752022-09-28028 September 2022
Proposed Alternative to the Requirements of the ASME OM Code
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
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
ML20169A5842020-07-15015 July 2020
Relief from the Requirements of the ASME Code
ML20113F0412020-04-30030 April 2020
Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19)
ML20099D9552020-04-17017 April 2020
Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations
ML20036D9622020-02-0404 February 2020
Dresden Nuclear Power Station, Nine Mile Point Nuclear Station, Peach Bottom Atomic Power Station, & Quad Cities Nuclear Power Station - Proposed Alternative to Extend Reactor Pressure Vessel Safety Relief Valve Testing Frequency
RS-20-006, Submittal of Relief Request for Revision to RV-03 Associated with Fifth Inservice Testing Interval2020-01-0202 January 2020
Submittal of Relief Request for Revision to RV-03 Associated with Fifth Inservice Testing Interval
ML19269C5342019-09-27027 September 2019
Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques
ML19161A2572019-06-0404 June 2019
BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019
ML19098A0342019-04-30030 April 2019
Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins
JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019
Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds
JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018
Proposed Alternative to Utilize Code Case N-879
JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018
Proposed Alternative to Utilize Code Cases N-878 and N-880
ML18022A6162018-01-24024 January 2018
Approval of Alternatives to the ASME Code Regarding Reactor Vessel Penetration N-11B - Relief Request 15R-11, Revision 3 (CAC No. MF9286; EPID L-2017-LLR-0004) (RS-17-014)
RS-18-004, Additional Information Supporting Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-112018-01-0404 January 2018
Additional Information Supporting Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11
ML17221A2642017-08-25025 August 2017
Alternative to the Requirements of the ASME Code Regarding Reactor Pressure Vessel Nozzle Assemblies; Relief Request I5R-07 (CAC Nos. MF8989 and MF8990) (RS-16-256)
ML17170A0132017-06-26026 June 2017
Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548)
ML16230A2372016-09-0606 September 2016
Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322)
ML14055A2272014-02-28028 February 2014
Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval Inservice Testing Program MF1462
ML12121A6372012-05-10010 May 2012
Request to Use Code Case N-789
ML0928602592010-02-0202 February 2010
Relief, Alternative to Nozzle to Vessel Weld and Inner Radius Examinations
ML0907700142009-03-26026 March 2009
Request to Partially Implement Subsequent Edition of ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code), Section ISTC-522, Condition-Monitoring Program & Mandatory Appendix...
ML0828201712008-11-25025 November 2008
Relief Request No. RV-30G from Main Steam Electrometric Relief Valve 0203-3C Test Interval
ML0813305572008-06-27027 June 2008
Dresden/Quad Cities Relief Requests from 5-Year Test Interval for Main Steam Safety Valves
ML0809803112008-04-30030 April 2008
Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines..
ML0731300522007-11-20020 November 2007
Relief from 5-Year Test Interval for Main Steam Safety Valves
ML0716300312007-08-0606 August 2007
Relief Request 14R-16 to Extend the First Period of the Fourth 10-year Inservice Inspection Interval for Twenty Reactor Pressure Vessel Welds
ML0508303142005-05-10010 May 2005
Relief, Relief Request CR-39 for Third 10-Year Inservice Inspection Interval
ML0426005632004-10-19019 October 2004
Amendments, Main Steam Line Relief Valves and Associated Relief Requests. TAC Nos. MC1792, MC1793, MC1794, and MC1795
ML0403307562004-02-20020 February 2004
Relief, Fourth 10-Year Inservice Testing Program Interval
ML0335603862004-01-28028 January 2004
Fourth 10-Year Interval Inservice Inspection Relief Requests Nos.14R-01 Through 14R-01 Through 14R-09 (TAC Nos. MB7695 Through MB7712)
RS-03-194, Fourth Interval Inservice Inspection Program Plan2003-10-10010 October 2003
Fourth Interval Inservice Inspection Program Plan
SVP-03-096, Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program2003-09-11011 September 2003
Submittal of Proposed Relief Requests to the Requirements of 10 CFR 50.55a Concerning the Fourth Ten-Year Interval Inservice Testing Program
ML0319201482003-07-24024 July 2003
Relief Request, Witholding Information from Public Disclosure,
ML0314208182003-05-28028 May 2003
Relief Request RV-30E, Inservice Testing Program Relief Regarding Main Steam Electronic Relief Valves and Safety/Relief Valves
RS-03-099, Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program2003-05-16016 May 2003
Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program
ML0312500182003-05-0808 May 2003
Relief, Inservice Testing Program Relief Regarding Main Steam Power Operated Relief Valves, MB8713
RS-03-091, Additional Information Regarding Relief Request RV-30E2003-05-0202 May 2003
Additional Information Regarding Relief Request RV-30E
SVP-02-033, Code Relief Request CR-38, Inservice Inspection Program Relief Re 10 Hour Annual Training Requirements of ASME Section XI, 1995 Edition with 1996 Addenda, Appendix VII2002-04-0808 April 2002
Code Relief Request CR-38, Inservice Inspection Program Relief Re 10 Hour Annual Training Requirements of ASME Section XI, 1995 Edition with 1996 Addenda, Appendix VII
ML0204200152002-02-21021 February 2002
Relief Request CR-37, Inservice Inspection Program Relief Regarding Examination of Pressure Retaining Welds in Piping Subject to Appendix Viii, Supplement 11
SVP-02-001, Request for Code Relief, Examination of Pressure Retaining Welds in Piping Subject to Appendix Viii, Supplement 11, Examination2002-01-0404 January 2002
Request for Code Relief, Examination of Pressure Retaining Welds in Piping Subject to Appendix Viii, Supplement 11, Examination
2023-05-08
[Table view] |
Text
November 30, 2022 QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 - AUTHORIZATION AND SAFETY EVALUATION FOR ALTERNATIVE REQUEST NO. I6R-01, REV. 0 (EPID L-2022-LLR-0036)
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 Road Warrenville, IL 60555 Licensee: Constellation Energy Generation, LLC (CEG)
Plant Name and Units: Quad Cities Power Station Units 1 and 2 (Quad Cities)
Docket Nos.: Quad Cities Unit 1: 50-254 Quad Cities Unit 2: 50-265 APPLICATION INFORMATION Submittal Date: March 25, 2022 Submittal Agencywide Documents Access and Management System (ADAMS) Accession No.: ML22084A597 Supplement Date: August 10, 2022 Supplement ADAMS Accession No.: ML22223A084 Alternative Provision: The applicant requested an alternative under Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.55a(z)(2).
Applicable Code Edition and Addenda: American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME BPV Code), 2017 Edition with no addenda.
Applicable Inservice Inspection (ISI) Program Interval: The sixth 10-year interval which is scheduled to begin April 2, 2023, and end on April 1, 2033 ISI Requirements: For ASME BPV Code Class 1 nozzles, the ISI requirements are those specified in Paragraph IWB-2411 of the ASME BPV Code, Section XI, which requires the licensee to perform volumetric examinations of the inside radii of reactor pressure vessel nozzles as specified in ASME BPV Code, Section XI, Table IWB-2500-1 (Examination Category B-D) once every 10-Year ISI interval.
Examination Category B-D, Item No. B3.100, Nozzle Inside Radius Section Note (6) of Table IWB-2500-1 (B-D) allows a VT-1 visual examination of the nozzle inner radius in accordance with IWB-2500(g) in lieu of the volumetric examination. IWB-2500(g) references mathematical criteria in IWB-2500(f), which must be met in order to perform the visual examination in lieu of the volumetric examination. NRC conditioned IWB-2500 (f) and (g) in 10 CFR 50.55a(b)(2)(xxi)(B) to require, in part, that the licensee maintain records demonstrating that the criteria in IWB-2500(f) are met, in the case that the licensee elects to perform the visual examination in lieu of the volumetric examination.
Brief Description of the Proposed Alternative: In Section 4 of I6R-01, Rev. 0, the licensee described the geometric configuration of the Quad Cities Standby Liquid Control (SBLC) nozzles. The licensee stated that performing the required volumetric examination of the SBLC nozzles would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. The licensee proposed to perform a VT-2 visual examination of the SBLC nozzle as part of the Class 1 leakage test and maintain compliance with technical specification surveillance requirements for reactor coolant pressure boundary leakage, as an alternative to the volumetric examination or VT-1 examination.
For additional details on the licensees request, please refer to the documents located at the ADAMS Accession Nos. identified above.
STAFF EVALUATION The licensee cited several hardships for this case, including the need for low-angle ultrasonic probes, complex metallurgy due to the unique socket configuration of the nozzle, the lack of qualified ultrasonic equipment, and high dose rates for plant personnel. The NRC staff reviewed these factors and determined that, taken together, they constitute a hardship.
As part of their review of the proposed alternative, the NRC staff requested additional information on materials of construction, the examination history of the nozzle-to-vessel weld, the examination history of the subject nozzle inner radius, and the potential to perform a VT-1 examination in accordance with IWB-2500(g) of Section XI. The licensee responded in the supplement dated August 10, 2022. The licensee stated that the reactor pressure vessel plates were fabricated out of SA-302 Grade B low-alloy steel and that the SBLC nozzle forging was fabricated out of SA-336 low-alloy steel. The licensee stated that the nozzle-to-vessel weld has received four ultrasonic examinations with no identified indications. The licensee stated that, while the SBLC nozzle inner radius has not received ultrasonic examination, it has received VT-2 examination. The licensee further stated that plant personnel has not identified any relevant conditions or signs of leakage as part of the VT-2 examination. Finally, the licensee stated that performance of the VT-1 examination in accordance with IWB-2500(g) of Section XI also presents a hardship due to the removal of vessel internals components that would be required to access to the SBLC nozzle inner radius location.
The NRC staff finds that the examination history of the nozzle-to-vessel weld provides confidence in the performance of the nozzle inner radius, since the weld was constructed with similar materials and experiences a similar environment as the nozzle inner radius location.
Regarding the potential for a VT-1 examination, the NRC staff determined that removal of various lower plenum vessel internals components to perform the examination constitutes a hardship. Overall, the NRC staff finds that the licensees responses in the supplement dated August 10, 2022, are acceptable.
CONCLUSION The NRC staff determined that compliance with the specified requirements results in a hardship or unusual difficulty without a compensating increase in quality or safety.
The proposed alternative provides reasonable assurance of leak tightness of the subject components.
The NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(2).
The NRC staff authorizes the use of proposed alternative I6R-01, Rev. 0, at Quad Cities 1 and 2 for the sixth inservice inspection interval which is scheduled to begin April 2, 2023, and to end on April 1, 2033.
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: David Dijamco Date: November 30, 2022 Digitally signed by Nancy Nancy L. L. Salgado Date: 2022.11.30 Salgado 13:20:50 -05'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc: Listserv
ML22327A263 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DNRL/NVIB/BC NRR/DORL/LPL3/BC NAME RKuntz SRohrer DWidrevitz (acting) NSalgado DATE 11/23/2021 11/25/2022 11/5/2022 11/30/2022
