Letter Sequence Approval |
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EPID:L-2022-LLR-0056, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 (Approved, Closed) |
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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
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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
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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
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Request to Use Code Case N-789
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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
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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
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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..
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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
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Amendments, Main Steam Line Relief Valves and Associated Relief Requests. TAC Nos. MC1792, MC1793, MC1794, and MC1795
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Relief Request, CR-26 for Third 10-Year Inservice Inspection Interval. TAC No MC3269 and MC3270
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Relief Request, CR-27 for Third 10-Year Inservice Inspection Interval. TAC No. MC3268
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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
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Relief Request for Fourth 10-Year Inservice Testing Interval, MB8741, MB8742, MB8743, MB8744, MB8745, and MB8746
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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
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RS-03-101, Additional Information Regarding Inservice Inspection Program Relief Request I4R-022003-05-29029 May 2003
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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
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Relief Request, PR-22 for Third 10-year Inservice Inspection Interval (MB4030, MB4031)
2023-09-27
[Table view] |
Text
January 12, 2023
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 - AUTHORIZATION AND SAFETY EVALUATION FOR ALTERNATIVE REQUEST I6R-09 (EPID: L-2022-LLR-0056)
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 third containment inservice inspection (CISI) will be modified to end on January 19, 2023, which will permit commencement of the next (i.e., fourth) CISI interval to coincide with the start date of the upcoming sixth ISI interval sc heduled 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: The third interval of the Dresden, Units 2 and 3, containment inservice inspection (CISI) program is based on Section XI of the 2013 Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME) Code.
Applicable Code Requirements: ASME Code,Section XI, Subsection IWA, Article IWA-2430(b) requires that The inspection interval shall be determined by calendar years following placement of the plant into commercial service.
IWA-2430(c)(1) requires, in part, that Each inspection interval may be extended by as much as 1 year and may be reduced without restriction, provided the examinations required for the interval have been completed. Successive intervals shall not extend more than 1 year beyond the original pattern of 10 -year intervals and shall not exceed 11 years in length.
IWA-2430(c)(3) requires, in part, that That portion of an inspection interval described as an inspection period may be extended by as much as 1 year and may be reduced without restriction, provided the examinations required for that period have been completed.
IWA-2431(b) requires that successive inspection intervals shall be 10 years following the previous inspection interval.
IWE-2411(a) requires, in part, that Examinations shall be completed during each successive inspection interval, in accordance with Table IWE-2411-1. Table IWE-2411-1 specifies that inspection periods shall terminate at the end of years 3, 7, and 10, within the inspection interval.
Brief Description of the Proposed Alternative: Pursuant to 10 CFR 50.55a(z)(1), an alternative was requested from the specified requirements of IWA-2430(b), IWA-2430(c)(1),
IWA-2430(c)(3), IWA-2431(b), and IWE-2411(a). Specifically, the proposed alternative requested to reduce the duration of the third CISI program interval.
The request for alternative sought to end the third CISI interval for Dresden, Units 2 and 3, on January 19, 2023, which will permit commencement of the next (i.e., fourth) CISI interval to coincide with the start date of the upcoming sixth ISI interval on January 20, 2023. This will result in both the ISI and CISI programs being on the same pattern of intervals and being under the same edition of the ASME Code, for the next and successive intervals.
TECHNICAL EVALUATION
To determine whether the proposed alternative will provide an acceptable level of quality and safety, the NRC staffs review focused on its effect on the implementation of the ASME Code-required ISI. The proposed alternative will allow the use of a common ASME Code,Section XI, edition for both CISI and ISI activities on Class 1, 2, 3, and major components, starting on January 20, 2023. This will facilitate program and inspection procedures being maintained and implemented to one common ASME Code edition and associated set of requirements. The common ASME Code edition will reduce the chance of applying incorrect ISI and CISI requirements for specific component examinat ions. Common interval dates, procedures, and documents will also maintain the quality and safety of the CISI and ISI programs in accordance with the latest regulations, codes, and standards.
The supplementary information contained within section 2.2 of former Final Rule (67 FR 60520) dated September 26, 2002, contains statements supporting the proposed alternative for modifying the CISI interval. Specifically, the information pointed out that 10 CFR 50.55a(g)(4)(ii) does not prohibit licensees from updating to a later edition and addenda of ASME Code,Section XI, midway through a 10-year IWE examination interval. Additionally, the information advised that Licensees wishing to synchronize their 120-month intervals may submit a request in accordance with section 50.55a(a)(3) to obtain authorization to extend or reduce 120-month intervals.
Based on the above discussion, NRC staff approves this proposed alternative request I6R-09.
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CONCLUSION
The 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 I6R-09 at Dresden, Units 2 and 3 for the fourth CISI interval to coincide with the sixth ISI interv al.
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: Nan Chien
Date: January 12, 2023
Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
cc: Listserv
ML23003A178 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/SCPB/BC NRR/DORL/LPL3/BC NAME SArora SRohrer HWagage (for BWittick) NSalgado DATE 12/22/2022 1/5/2023 1/11/2023 1/12/2023
