Letter Sequence Approval |
|---|
|
|
MONTHYEARML22229A0762022-08-16016 August 2022
NRR E-mail Capture - NRC Acceptance Review Dresden, Units 2 and 3 Request for Relief 16R-10
Project stage: Acceptance Review
ML23004A1712023-01-0606 January 2023
Authorization and Safety Evaluation for Alternative Request I6R-10,
Project stage: Approval
2022-08-16
[Table View] |
|
|---|
Category:Code Relief or Alternative
MONTHYEARML23265A1322023-09-27027 September 2023
Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval
ML23003A1782023-01-12012 January 2023
Authorization and Safety Evaluation for Alternative Request I6R-09
ML23004A1712023-01-0606 January 2023
Authorization and Safety Evaluation for Alternative Request I6R-10,
ML22335A5442022-12-20020 December 2022
Authorization and Safety Evaluation for Alternative Request I6R-01,
RS-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022
Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10
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
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
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-17-158, Fifth Inservice Inspection Interval Relief Request 15R-162017-11-0707 November 2017
Fifth Inservice Inspection Interval Relief Request 15R-16
ML17073A1212017-06-28028 June 2017
Issuance of Safety Evaluation Inservice Inspection Interval Proposed Alternative (I5R-08)
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)
ML15265A1642015-10-30030 October 2015
Request 14R-17 Relief from the Requirements of the ASME Code
RS-15-126, Additional Information Supporting Relief Request I4R-17, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval2015-05-21021 May 2015
Additional Information Supporting Relief Request I4R-17, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval
ML12121A6372012-05-10010 May 2012
Request to Use Code Case N-789
ML1206000112012-03-19019 March 2012
Request for Exemption from 10 CFR 50, Appendix R, Section Iii. L - Unacceptable with the Opportunity to Supplement
JAFP-11-0112, Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP2011-10-0303 October 2011
Relief Request (RR-8), Alternative Examination Requirements for Nozzle-to-Vessel Shell Welds and Nozzle Inner Radius Sections Using American Society of Mechanical Engineers Code Case N-702 and BWRVIP-108NP
ML0929404362009-11-0303 November 2009
Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations
RS-09-044, Request for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations2009-03-13013 March 2009
Request for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations
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..
ML0723500872007-09-20020 September 2007
Relief, Request for Relief from ASME OM Code 5-year Test Interval Requirements
ML0611103302006-05-0808 May 2006
Relief Request CR-28 for Third 10-Year Inservice Inspection Interval
SVPLTR 05-0018, Relief Request CR-28, Inservice Inspection Program Relief Regarding Reactor Pressure Vessel Longitudinal Shell Weld Examination Coverage for Third 10-Year Inservice Inspection Interval2005-05-0606 May 2005
Relief Request CR-28, Inservice Inspection Program Relief Regarding Reactor Pressure Vessel Longitudinal Shell Weld Examination Coverage 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
ML0423003862004-10-0101 October 2004
Relief Request, CR-26 for Third 10-Year Inservice Inspection Interval. TAC No MC3269 and MC3270
ML0423603442004-09-16016 September 2004
Relief Request, CR-27 for Third 10-Year Inservice Inspection Interval. TAC No. MC3268
ML0405603992004-03-25025 March 2004
Relief Request, Third 10-Year Inservice Inspection Interval, for Approval of a Flaw Evaluation for Dresden Nuclear Power Station (Dnps), Unit 2, So That the Affected Weld Could Be Left as Is Without Repair
ML0327308692003-10-0202 October 2003
Relief Request for Fourth 10-Year Inservice Testing Interval, MB8741, MB8742, MB8743, MB8744, MB8745, and MB8746
ML0323704802003-09-0404 September 2003
Relief Request, Fourth 10-Year Inservice Inspection Interval
RS-03-157, Additional Information Regarding Inservice Testing Program Relief Requests2003-08-0606 August 2003
Additional Information Regarding Inservice Testing Program Relief Requests
ML0316110032003-07-0101 July 2003
Relief Request, CR-25 for Third 10-Year Inservice Inspection Interval
RS-03-101, Additional Information Regarding Inservice Inspection Program Relief Request I4R-022003-05-29029 May 2003
Additional Information Regarding Inservice Inspection Program Relief Request I4R-02
RS-02-187, Request for Relief from Certain Requirements of 10 CFR 50.55a(g)(4)(ii) Regarding Control Rod Drive Housing Welds (Relief Request Number CR-25)2002-10-25025 October 2002
Request for Relief from Certain Requirements of 10 CFR 50.55a(g)(4)(ii) Regarding Control Rod Drive Housing Welds (Relief Request Number CR-25)
ML0225902032002-10-0404 October 2002
Relief Request, PR-22 for Third 10-year Inservice Inspection Interval (MB4030, MB4031)
2023-09-27
[Table view] |
Text
January 6, 2023 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - AUTHORIZATION AND SAFETY EVALUATION FOR ALTERNATIVE REQUEST I6R-10 (EPID: L-2022-LLR-0057)
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 Plant Name and Units: Dresden Nuclear Power Station (Dresden), Units 2 and 3 Docket Nos.: 50-237 and 50-249 APPLICATION INFORMATION Submittal Date: July 19, 2022 Submittal Agencywide Documents Access and Management System (ADAMS) Accession No.: ML22200A258 Applicable inservice inspection (ISI) program interval and interval start/end dates: The sixth 10-year ISI interval is scheduled to begin on January 20, 2023, and end on January 19, 2033.
Alternative Provision: The applicant requested an alternative under Title 10 of the Code of Federal Regulations (10 CFR), paragraph 50.55a(z)(1).
Applicable Code Edition and Addenda: American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, 2017 Edition.
Applicable Code Requirements: The alternative requested approval of the continued use of certain nondestructive examination (NDE) requirements of the ASME Code, Section XI, 2013 Edition in lieu of the 2017 Edition of the Code.
Brief Description of the Proposed Alternative: In lieu of the requirements specified in the 2017 Edition of the ASME Code, the licensee proposes to continue to use the provisions in the 2013 Edition of ASME Code, Section XI, for NDE activities associated with ISIs during the first period of the sixth ISI interval. These NDE activities are driven from ASME Code, Section XI,
Subarticles IWA-2100, IWA-2200, and IWA-2300. The licensee would comply with all applicable conditions and limitations specified in 10 CFR 50.55a(b)(2) related to the NDE requirements of the ASME Code, Section XI, 2013 Edition.
This request does not apply to the balance of the ISI program including the selection, planning, and scheduling, of ISI examinations and tests as defined in IWB-, IWC-, IWD-, IWE-, and IWF-2500 or approved ISI alternatives. Therefore, ISI examinations and tests will be selected, planned, and scheduled, in accordance with the sixth interval code of record, which will be the 2017 Edition of ASME Code, Section XI.
An inspection period is defined in ASME Code, Section XI, Table IWB-2411-1, as being the first 3 years of the 10-year inspection interval, with the option to extend the first inspection period by as much as 1 year and it may be reduced without restriction.
For additional details on the licensees request, please refer to the documents located at the ADAMS Accession No. identified above.
TECHNICAL EVALUATION The 2013 Edition of ASME Code, section XI, is conditionally approved for use in 10 CFR 50.55a(a)(1)(ii)(C)(53). The 2013 Edition of the ASME Code, Section XI, is the basis for the ISI programs in many nuclear power plants in the United States. Extending the use of the 2013 Edition of the ASME Code, as conditioned in 10 CFR 50.55a, for an additional 3 to 4 years would have a negligible effect on safety at Dresden, Units 2 and 3. Standardizing the NDE programs across the Constellation Energy Generation fleet will help prevent compliance errors and optimize the use of internal operating experience.
CONCLUSION The Nuclear Regulatory Commission (NRC) staff has determined that the proposed alternative in the licensees request referenced above would provide an acceptable level of quality and safety.
The NRC staff 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 16R-10 at Dresden, Units 2 and 3, for the first inspection period of the sixth 10-year ISI interval.
All other ASME 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: Stephen Cumblidge Date: January 6, 2023 Digitally signed by Robert Robert F. F. Kuntz Date: 2023.01.06 Kuntz 13:53:51 -05'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc: Listserv
ML23004A171 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DNRL/NPHP/BC NRR/DORL/LPL3/BC NAME SArora SRohrer MMitchell NSalgado (RKuntz for)
DATE 12/22/2022 1/5/2023 12/20/2022 1/6/2023
