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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023
2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
L-MT-23-024, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Inspection (ISI) Interval, RR-002 (L-MT-23-024)2023-07-11011 July 2023
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Inspection (ISI) Interval, RR-002 (L-MT-23-024)
L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022
Sixth Interval Inservice Testing (1ST) Plan
ML22067A0842022-03-0707 March 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-28 (LMT-22-007)
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
L-MT-21-051, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-22 (L-MT-21-051)2021-12-23023 December 2021
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-22 (L-MT-21-051)
ML21305A0672021-11-0101 November 2021
Clone of 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing (IST) Ten-Year Interval PR-02 (L-MT-21-054)
ML21278A1852021-10-0505 October 2021
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-02 (LMT-21-049)
L-MT-21-041, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-05 (L-MT-21-041)2021-08-31031 August 2021
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-05 (L-MT-21-041)
L-MT-21-038, 2021 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2021-08-17017 August 2021
2021 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
L-MT-20-004, 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2020-02-14014 February 2020
10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval
L-MT-20-001, 10 CFR 50.55a(z)(1) Request Vr 05: Request for Approval of an Alternative for Pressure Isolation Valve Testing2020-01-16016 January 2020
10 CFR 50.55a(z)(1) Request Vr 05: Request for Approval of an Alternative for Pressure Isolation Valve Testing
L-MT-19-028, 2019 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report; Second Steam Dryer Inspection Summary2019-08-0909 August 2019
2019 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report; Second Steam Dryer Inspection Summary
L-MT-17-059, 2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report2017-08-0909 August 2017
2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report
L-MT-15-064, Cycle 27 Inservice Inspection Summary Report2015-08-26026 August 2015
Cycle 27 Inservice Inspection Summary Report
ML14212A0712014-07-30030 July 2014
10 CFR 50.55a Request No. Vr 05: Proposed Alternative to Lnservice Testing Requirements Pursuant to 10 CFR 50.55a(a)(3)(ii)
L-MT-14-037, CFR 50.55a Request No. 009: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fifth Ten-Year Lnservice Inspection Interval2014-06-0606 June 2014
CFR 50.55a Request No. 009: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fifth Ten-Year Lnservice Inspection Interval
L-MT-14-021, Proposed Alternative in Accordance with 10 CFR 50.55a Request RR-008 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2014-02-28028 February 2014
Proposed Alternative in Accordance with 10 CFR 50.55a Request RR-008 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval
ML13308B2192013-10-11011 October 2013
Enclosure 3 - MNGP Evaluation EC-22537 - 2013 H8-H9 Shroud Support Structure Indications Update
ML13308B2182013-10-0808 October 2013
Enclosure 2- BWRVIP Inspection Summary Report
ML13308B2172013-10-0808 October 2013
Enclosure 1 - Cycle No. 26 and 1R26 2013 Refueling Outage Inservice Inspection: Interval 4, Period 3 and Interval 5, Period 1, Owner'S Activity Report (OAR-1)
L-MT-13-060, Response to Request for Additional Information Regarding Fifth 10-Year Inservice Inspection Program Plan Review2013-07-17017 July 2013
Response to Request for Additional Information Regarding Fifth 10-Year Inservice Inspection Program Plan Review
L-MT-12-094, In-service Testing (IST) Program Plan for Safety Related Seismic Restraints (Snubbers) for the Fifth 10-Year Interval2012-11-30030 November 2012
In-service Testing (IST) Program Plan for Safety Related Seismic Restraints (Snubbers) for the Fifth 10-Year Interval
L-MT-12-019, CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval2012-02-28028 February 2012
CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval
L-MT-12-017, CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Inspection Interval2012-02-28028 February 2012
CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Inspection Interval
L-MT-12-020, Fifth Ten-Year Lnservice Testing Plan2012-02-28028 February 2012
Fifth Ten-Year Lnservice Testing Plan
L-MT-12-018, Fifth Ten-Year Lnservice Inspection Plan2012-02-28028 February 2012
Fifth Ten-Year Lnservice Inspection Plan
L-MT-12-011, Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals2012-02-15015 February 2012
Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals
L-MT-11-046, Cycle 25 Inservice Inspection Summary Report2011-08-23023 August 2011
Cycle 25 Inservice Inspection Summary Report
L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements2009-08-0707 August 2009
Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements
L-MT-07-058, Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements2007-07-27027 July 2007
Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements
L-MT-05-088, 10 CFR 50.55a Request No. 13: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Inservice Inspection Interval2005-09-27027 September 2005
10 CFR 50.55a Request No. 13: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Inservice Inspection Interval
L-MT-05-078, Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements2005-07-12012 July 2005
Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements
L-MT-05-039, Fourth Interval Inservice Inspection Examination Plan. Revision 32005-04-26026 April 2005
Fourth Interval Inservice Inspection Examination Plan. Revision 3
L-MT-04-050, Fourth Interval Inservice Inspection Examination Plan, Revision 22004-09-16016 September 2004
Fourth Interval Inservice Inspection Examination Plan, Revision 2
L-MT-03-056, Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements2003-08-25025 August 2003
Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements
L-MT-03-023, Response to Request for Additional Information Regarding Fourth 10-Year Interval Inservice Testing Program Relief Request Number No.VR-012003-04-29029 April 2003
Response to Request for Additional Information Regarding Fourth 10-Year Interval Inservice Testing Program Relief Request Number No.VR-01
ML0235205912002-12-0606 December 2002
to Engineering Work Instruction EWI-09.04.01, Inservice Testing Program.
ML0233806832002-11-22022 November 2002
Part 2 of 2, Monticello, Request for Review and Approval of Relief Request Associated with Fourth 10-Year Interval Inservice Testing Program Plan Submittal
ML0233701072002-11-22022 November 2002
Part 1 of 2, Monticello, Request for Review and Approval of Relief Request Associated with Fourth 10-Year Interval Inservice Testing Program Plan Submittal
ML0217102272002-06-0606 June 2002
Inservice Testing Program for Engineering Work Instruction, Revision 8
ML0211905312002-04-0101 April 2002
Revision 7 to EWI-09.04.01, Inservice Testing Program.
ML0208603482002-03-12012 March 2002
Part 1 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements
ML0208605512002-03-12012 March 2002
Part 2 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613
ML0208606762002-03-12012 March 2002
Part 3 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613
ML0208606932002-03-12012 March 2002
Part 4 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613
ML0203203662002-01-11011 January 2002
Inservice Inspection Plan Submittal of Relief Request Number 14 for the Third Ten Year Interval
2023-07-31
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Text
WEB-BASED PROPOSED ALTERNATIVE SUBMISSION 10 CFR 50.55a(z)(1)
Submission Date: July 11, 2023 Submitted By: Ron Jacobson Document Sensitivity: Non-Sensitive Licensee: Xcel Energy Plant Unit(s) and Docket No(s): Monticello(05000263)
Licensee
Contact:
Ron Jacobson ronald.g.jacobson@xcelenergy.com 6123306542
- 1. Project
Title:
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Inspection (ISI) Interval, RR-002 (L-MT-23-024)
- 11. Proposed Alternative Number or Identifier:
ISI RR-002
- 6. Request Type:
10 CFR 50.55a(z)(1)
- 7. Inservice Inspection (ISI) or Inservice Testing (IST)
Inservice Inpection (ISI)
- 10. Requested Completion Date:
August 30, 2024
- 12. Brief Description of Proposed Alternative Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), hereby requests NRC authorization of this 10 CFR 50.55a alternative for the Monticello Nuclear Generating Plant (MNGP).
Pursuant to 10 CFR 50.55a(z)(1), NSPM proposes that the use of IWB-2500(f) be permitted even though the maximum fluence cited in IWB-2500(f)(8) and the number of heatup/cooldown cycles cited in IWB-2500(f)(9) are exceeded.
- 13. Proposed Duration of Alternative (in terms of ISI/IST Program Interval with Start and End Dates):
The proposed alternative will be used for the Sixth ISI Interval until the end of the current extended operating period on September 8, 2030; this is earlier than the expected end of the Sixth ISI Interval, which is scheduled to end on or about May 31, 2033. NSPM has applied for a subsequent renewed operating license (ML23009A353); however, a revised plant-specific probabilistic fracture mechanics (PFM) analysis will be required to evaluate this proposed alternative beyond September 8, 2030. A later 50.55a request covering the additional years of operation would be submitted with that PFM analysis to extend this alternative beyond September 8, 2030.
- 14. Applicable ASME Code Requirements Table IWB-2500-1 (B-D), Note (6) states: "For [boiling water Reactors (BWRs)], the alternative criteria in IWB-2500(f) may be used."
IWB-2500(f) states, in part: "For BWRs, in lieu of examining all nozzles, at least 25% of nozzle inner radii and nozzle-to-shell welds, including at least one nozzle for each system and nominal pipe size, may be examined for Table IWB-2500-1 (B-D), Item Nos. B3.90 and B3.100, provided the following conditions are met:"
IWB-2500(f)(8) states: "Fluence levels do not exceed [1E+17] n/cm2 on any portion of the examined component."
IWB-2500(f)(9) states: "The total number of heatup and cooldown cycles from plant startup for the component will not exceed 40 by the end of the interval. A cycle consists of both a heat-up and a cooldown."
- 15. Applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV Code), or ASME Operation and Maintenance of Nuclear Power Plants (OM Code), Edition and Addenda American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," (ASME Section XI),
2019 Edition.
- 16. Current ISI or IST Program Interval Number and Start/End Dates MNGP started the Sixth Inservice Inspection Interval on June 1, 2023 and is scheduled to conclude on May 31, 2033.
- 17. Applicable ASME Code Components and/or System Description Code Class: 1. Component Numbers: N2, N3, N5, N6, & N8 Nozzles-to-shell welds with associated inner radius sections. Examination Category: B-D. Item Number(s): B3.90 & B3.100.
Description:
Alternative to ASME Section XI, IWB-2500(f)(8) and IWB-2500(f)(9).
- 18. Reason for Request The proposed alternative examination provides an acceptable level of quality and safety based on a plant-specific evaluation using a PFM methodology endorsed by the NRC in Electrical Power Research Institute (EPRI) Technical Report BWRVIP-108-A, "Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Inner Radii,"
[Reference 1].
- 19. Full Description of Proposed Alternative Pursuant to 10 CFR 50.55a(z)(1), NSPM proposes that the use of IWB-2500(f) be permitted even though the maximum fluence cited in IWB-2500(f)(8) and the number of heatup/cooldown cycles cited in IWB-2500(f)(9) are exceeded during the Sixth ISI Interval. The number of heatup/cooldown cycles projected through 2030 is 181. The maximum fast neutron fluence at the inner surface of the N2 nozzles at
54 effective full power years (EFPY) / 60 years of operation is projected to be 1.01E 18 n/cm2.
- 20. Description of Basis for Use IWB-2500(f) is the incorporation of ASME Section XI Code Case N-702, except that the information contained in IWB-2500(f)(8) and IWB-2500(f)(9) was taken from BWRVIP-108-A [Reference 1] which served as the technical basis for the code case. BWRVIP-108-A noted that fluence was considered negligible at the nozzle locations and that the heatup/cooldown cycles considered were limited to 40 for a design life of 40 years. As part of NSPMs request to use Code Case N-702 in the Fifth Interval, by letter, NSPM informed the NRC that the fluence values and heatup/cooldown cycles cited in BWRVIP-108-A would be exceeded [Reference 2].
Also, as part of that submittal, NSPM provided a supplemental plant-specific probabilistic fracture mechanics (PFM) analysis based on a fluence and a number of heatup/cooldown cycles projected for, or beyond, 60-years of operation. That analysis was revised to address NRC requests for additional information and a revised MNGP plant-specific PFM analysis was provided [Reference 4]. The plant-specific PFM analysis indicated that the vessel probability of failure, P(F/E), is 1.17E-7 per year for normal condition and 1.05E-6 per year for Low Temperature Overpressure Protection (LTOP) transient considering 60 years of operation. Since both the plant-specific probabilities of failure P(F/E) values for 60-years of operation are less than the NRC safety goal of 5E-6 per year for the pressurized thermal shock (PTS), the NRC accepted the increase in fluence and heatup/shutdown cycles and approved the use of Code Case N-702 [Reference 3]. A plant-specific PFM analysis [Reference 4] was used to evaluate conditions for the request approved for the Fifth Interval, and is the basis for applying the provisions of ASME Section XI, IWB-2500(f). The conditions of the PFM analysis bound the fluence and heatup/cooldown cycles projected for the remainder of MNGPs extended period of operation, which will expire before the end of the Sixth Interval.
- 21. Include Any Additional Information Submission Date: July 11, 2023 Submitted By: Ron Jacobson Plant Unit(s) and Docket No(s): Monticello (05000263)
22. Precedents
NSPM made a similar request (RR-002) during their Fifth ISI Interval [Reference 5] and provided the MNGP plant-specific PFM analysis [Reference 4] for use of
Code Case N-702. The NRCs safety evaluation accepted the use of Code Case N-702
[Reference 3] with fluence and heatup/cooldown cycles exceeding those used in BWRVIP-108-A [Reference 1]. Although the basis [Reference 4] supporting RR-002 is written with reference to Code Case N-702, it is also technically applicable to the requirements of ASME Section XI, IWB-2500(f).
- 23. References
- 1. BWRVIP-108-A, "BWR Vessel and Internal Project, Technical Basis for the Reduction of Inspection Requirements for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii", dated Oct 2002. 2. NSPM Letter to NRC, "Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Inservice Inspection Ten-Year Intervals," dated February 15, 2012
[Accession No. ML120470088] 3. NRC Letter to NSPM, "Monticello Nuclear Generation Plant (MNGP) - Revised Safety Evaluation for Relief Request RR-002, for the Fifth 10-year Inservice Inspection Interval (TAC ME3527, ME8087, and ME9160)," dated August 28, 2012. [Accession No. ML12236A280] 4. SIA Calculation Pkg., "Monticello N2 Nozzle Code Case N-702 Relief Request," dated August 7, 2012 [Accession No. ML12230A098] 5. NSPM Letter to NRC, "10CFR50.55a Requests Associated with the Fifth Inservice Inspection Ten-Year Interval," dated September 28, 2011 [Accession No. ML112720147]
- 24. Attachments
