ML19343D054
| ML19343D054 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/04/2019 |
| From: | Bennett Brady NRC/NRR/DNRL/NLRP |
| To: | |
| Brady B, NRR-DNRL 415-2981 | |
| References | |
| Download: ML19343D054 (16) | |
Text
Advisory Committee on Reactor Safeguards Peach Bottom Atomic Power Station Units 2 and 3 Subsequent License Renewal December 4, 2019 Bennett Brady, Senior Project Manager Division of New and Renewed Licenses (DNRL)
Office of Nuclear Reactor Regulation
Presentation Outline Overview of Safety Review of Peach Bottom SLRA SER Section 2, Scoping and Screening Review SER Section 3, Aging Management Review SER Section 4, Time-Limited Aging Analyses Closure of Confirmatory Item SLRA Review Conclusion Region I Initial License Renewal Inspection and Plant Material Conditions and Conclusion Summary Conclusion 2
Overview of Safety Review of Peach Bottom SLRA 3
- Application Submitted - July 10, 2018
- Acceptance Determination - September 6, 2018
- Safety Evaluation Report with Confirmatory Item -
October 7, 2019
- Safety Evaluation Report - November 19, 2019 Unit Initial License Initial License Renewal Application Renewed License Expiration Date Subsequent License Renewal Application 2
10/25/1973 07/02/2001 05/07/2003 08/08/2033 07/10/2018 3
07/02/1974 07/02/2001 05/07/2003 07/02/2034 07/10/2018
4 Dates Location Operating Experience Audit September 17-27, 2018 Rockville, MD In-office Audit November 13, 2018 - April 29, 2019 Rockville, MD SLRA Audits and Inspections
SER Overview
- SER with Confirmatory Item Issued October 7, 2019
- Confirmatory Item 3.0.3.2.3-1 on BWR Vessel Internals
- Safety Evaluation Report issued November 19, 2019
- Confirmatory Item 3.0.3.2.3-1 closed
- Requests for Additional Information (RAIs)
- 48 RAIs issued, 4 of which were follow-up RAIs 5
SER Section 2 Structures and Components Subject to Aging Management Review (AMR)
- Section 2.1 Scoping and Screening Methodology
- Section 2.2 Plant Level Scoping Results
- Sections 2.3, 2.4, and 2.5 Scoping and Screening Results 6
Aging Management Review (AMR)
- Section 3.0 Use of the Generic Aging Lessons Learned Report
- Section 3.1 Reactor Vessel, Internals, and Reactor Coolant System
- Section 3.2 Engineered Safety Features
- Section 3.3 Auxiliary Systems
- Section 3.4 Steam and Power Conversion Systems
- Section 3.5 Containment, Structures, and Component Supports
- Section 3.6 Electrical and Instrumentation and Control Commodities 7
SER Section 3
SLRA - Original Disposition of AMPs 11 new GALL programs 8 consistent 3 consistent with exceptions 35 existing GALL programs 8 consistent 27 consistent with enhancements/exceptions 1 plant specific with enhancement SER - Final Disposition of AMPs 11 new GALL programs 8 consistent 3 consistent with exceptions 35 existing GALL programs 8 consistent 27 consistent with enhancements/exceptions 1 plant specific with enhancement 8
3.0.3 - Aging Management Programs (AMPs)
SER Section 3
Time-Limited Aging Analyses (TLAAs) 4.1 Identification of TLAAs 4.2 Reactor Vessel and Internals Neutron Embrittlement Analyses 4.3 Metal Fatigue Analyses 4.4 Environmental Qualification of Electric Equipment 4.5 Concrete Containment Tendon Prestress Analysis 4.6 Primary Containment Fatigue Analysis 4.7 Other Plant-Specific TLAAs 9
SER Section 4
Closure of Confirmatory Item 3.0.3.2.3-1 BWR Vessel Internals 10 Issue SLRA, AMP B.2.1.7 BWR Vessel Internals proposed and enhancement to either:
install core plate wedges or submit for NRC approval an inspection plan for the core plate rim hold-down bolts to mitigate stress corrosion cracking.
Resolution Applicant revised the AMP B.2.1.7 enhancement to be in accordance with BWRVIP-25, Revision 1 to:
install wedges or inspect core plate rim hold-down bolts, or demonstrate instead via analysis that the installation of wedges and inspections of the core plate rim hold-down bolts are not required.
On the basis of its review of the SLRA and the resolution of the confirmatory item, the staff determined that the requirements of 10 CFR 54.29(a) have been met for the subsequent license renewal of Peach Bottom Atomic Power Station Units 2 and 3.
11 SLRA Review Conclusion
- Five to ten years following the entry into the period of extended operation the Region conducts one additional license renewal team inspectionIP 71003 Phase 4.
- The team examines a sample of AMPs to verify the effects of aging were being managed effectively to ensure structures, systems, and components in the scope of these programs maintained the ability to perform their intended functions.
12 Region I Initial License Renewal Inspections
Flow Accelerated Corrosion Program (existing)
Maintenance Rule Structural Monitoring Program (existing)
Ventilation System Inspection and Testing Activities (enhanced)
Outdoor, Buried and Submerged Component Inspection Activities (enhanced)
Fire Protection Activities (enhanced)
In-accessible Medium Voltage Cables not subject to 10 CFR 50.49 Environmental Qualification Requirements (New) 13 Region I AMP Inspections The Peach Bottom IP 71003 Phase 4 initial license renewal inspection was performed in November 2018 on both Units 2 and 3.
Inspection of Plant Material Condition
- Reactor Oversight Process performance indicators and findings indicate plant material condition meets regulatory requirements.
- Resident Inspector routine plant walkdowns support this conclusion.
- Resident and Region based inspectors continue to inspect and assess the licensee performance to manage the effects of aging through the baseline inspection program.
14
The inspectors found the licensees aging management programs were being effectively implemented in accordance with the facilitys renewed license. The NRC will continue to monitor AMPs using the baseline Reactor Oversight Process.
15 NRC Inspection Results
Summary Conclusion
- The staff has completed its presentation and conclusions on the safety review of the Peach Bottom SLRA and the Region I conclusions on inspections and plant material conditions.
- Additional questions 16