ML22067A027

From kanterella
Jump to navigation Jump to search
Subsequent License Renewal Application Pre-Application Meeting March 16, 2022
ML22067A027
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/16/2022
From: Vera Amadiz M
NRC/NRR/DNRL/NLRP, Xcel Energy
To:
Vera Amadiz M, (301) 415-5861
References
Download: ML22067A027 (19)


Text

MONTICELLO UNIT 1 SUBSEQUENT LICENSE RENEWAL APPLICATION PRE-APPLICATION MEETING MARCH 16, 2022

1 Agenda

  • Monticello Background
  • General Topics
  • Scoping and Screening
  • Ti m e-Limited Aging Analyses (TLAAs)
  • Topics of Interest
  • Questions
  • Action Items
  • Application materials subject to change. 2 Monticello SLR Project Team

Xcel Energy Scott McCall, Director of Projects Paul Young, Manager - Site Routine Projects Max Smith, Project Manager Toutseng Hawj, SLR Senior Engineer (Electrical)

Stephen Sollom, SLR Senior Engineer (Environmental/Chemistry)

Jolynn Oquist, SLR Senior Engineer (Mechanical)

Sharida Ullah, SLR Senior Engineer (Civil)

ENERCON Joanne Aleksick, Project Manager Gary Adkins, LR/SLR Manager Brian Norman, LR/SLR Supervisor Jeff Gromatzky, Technical Lead Mark Miller, Mechanical Lead Ian Miller, AMP Lead Deb Spamer, Electrical Lead Ken Putnam, Civil Lead

3 Monticello Background

Original license renewal application (LRA) approved on November 8, 2006 Current license expiration dates, 9/8/2030

  • Entered PEO 9/8/2010
  • Latest NEI 14-12 AMP effectiveness review completed 3/1/2020 o AMPs effective at managing age-related degradation o Phase IV post-approval site inspection for license renewal completed 6/10/2020

o No findings or violations of more than minor significance; no additional tracking items Licensed core power history

  • 1670 MWt, Initial license

4 General Topics

  • Submittal schedule
  • ePortal Folder Structure
  • Operating Experience (OE) including Keywords
  • Application of lessons learned
  • Scoping and Screening

5 General Topics

  • Submittal schedule

o First Quarter of 2023 - on track

  • ePortal Folder Structure o Folder for each AMP and AMR o Added folders for Instructions, References, Special Topics
  • Audit
  • Operating Experience (OE) including Keywords

o Latest available keywords utilized (196 total) o The AR search covered the period from 10/01/2010 to 07/29/2021

  • 69,000+ initial hits screened, over 10,000 identified for further review o Experience based interviews, in accordance with EPRI TR -110089, Experience-based Interview Process for Power Plant Management, conducted with AMP owners via teleconference o No new aging effects identified

6 General Topics

  • Application of Lessons Learned o Senior, LR/SLR experienced engineers in key positions o Review and incorporation of industry LR operating experience including implementation o Incorporated lessons learned from ENERCON SLRA experience o Review and incorporation of previous RAIs including Peach Bottom, Turkey Point, and Surry SLRA reviews
  • Included as evaluations within the AMP Reports and Technical Reports

7 Scoping and Screening

o NEI 17-01, NUREG -2192

  • (a)(2) scoping consistent with NEI 95-10 Rev. 6, Appendix F

o Walkdowns performed using Spaces Approach

o Preventive Option approach to Non-Safety SSCs Not Directly Connected to Safety Related SSCs

8 Interim Staff Guidance

Incorporation of new ISGs:

o AMPs X.M2 (Neutron Fluence Monitoring), XI.M2 (Water Chemistry), XI.M12 (CASS), XI.M21A (Closed Treated Water), XI.M42 (Internal Coatings)

o AMR line items associated with Fire Protection

o AMP XI.S8 (Protective Coating)

o AMPs XI.E3A (MV Cable), XI.E3B (I&C Cable), XI.E3C (LV Cables)

9 Aging Management Programs

  • Consistency with GALL

10 Aging Management Programs

Consistency with NUREG-2191 and SLR ISGs

  • AMRs (SLRA Section 3) o Very consistent, > 99% A through E notes (~13-line items note greater than E) o No new aging effects
  • Peach Bottom, Turkey Point, and Surry RAIs addressed o Separate section in each AMP basis document summarizes how the RAIs were addressed

11 Aging Management Programs

AMP Category AMPs Consistent AMPs Consistent AMPs AMPS with Exception Plant Specific AMPs with GALL with Enhancement with Exception and Enhancement Existing 38 8 25 2 3 0 New 7 7 0 0 0 0 Total AMPs 45

o XI.M35 - ASME Code Class 1 Small-Bore Piping o XI.M5, BWR Feedwater Nozzle (not in GALL SLR)

o XI.E3B - Electrical Insulation for Inaccessible Instrument and o XI.M6, BWR Control Rod Drive Return Nozzle (not in GALL SLR)

Control Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements o Additional Information

o XI.M42 - Internal Coatings/Linings for in-Scope Piping, Piping o XI.M31, Reactor Vessel Material Surveillance Components, Heat Exchangers, and Tanks"

o XI.M38 - Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components

o XI.M12 - Thermal Aging Embrittlement of CASS

o XI. M29 - Outdoor and Large Atmospheric Metallic Storage Tanks

o XI.M32 - One-Time Inspection 12 Aging Management Programs

  • AMPs with exceptions to GALL:

o XI.M2, Water Chemistry;

o XI.M3, Reactor Head Closure Stud Bolting;

o XI.M9, BWR Vessel Internals;

o XI.M30, Fuel Oil Chemistry;

o XI.S1, ASME Section XI, Subsection IWE.

All exceptions and their bases have precedence in other LRAs and SLRAs.

13 Time-Limited Aging Analyses

  • Fluence Methodology

14 Time-Limited Aging Analyses

  • Identification
  • Vendor
  • Change in Methods
  • General and Plant Specific TLAAs

15 Time-Limited Aging Analyses

  • Fluence Methodology o RAMA Fluence Methodology o Neutron transport followed the guidance of Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel o Methodology has been generically approved for calculations of exposure of the reactor pressure vessel (RPV) beltline and for BWR core shroud and top guide components
  • Exposure Projections - Based on 72 EFPY
  • Reports o RPV Fluence o Reactor Internals o Methods report
  • Reactor Vessel Embrittlement o 3rd Capsule pulled April 2021 16 Topics of Interest
  • Irradiation of Concrete
  • Irradiation of Reactor Vessel (RV) supports

17 Topics of Interest

Irradiation of Concrete/Irradiation of Reactor Vessel (RV) supports Threshold for concern:

  • Neutron: 1E+19 n/cm^2
  • Gamma: 1E+10 rad

18 Questions

© 2021 Xcel Energy 19