ML072690529
| ML072690529 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick |
| Issue date: | 09/05/2007 |
| From: | Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| Le, Ngoc, NRR/DLR/RLRB, 415-1458 | |
| Shared Package | |
| ML072690486 | List: |
| References | |
| TAC MD2666 | |
| Download: ML072690529 (40) | |
Text
1 James A.
James A. FitzPatrick FitzPatrick Nuclear Power Plant Nuclear Power Plant ACRS License Renewal Subcommittee Presentation September 5, 2007
2 Brian Finn Site NSA Director John McCann Director of Licensing, White Plains Garry Young Manager, License Renewal Steve Bono Director of Engineering Joe Pechacek Manager, Programs & Components James Costedio Licensing Manager Alan Cox Technical Manager Rick Plasse Licensing Lead Larry Leiter Technical Lead Tom Moskalyk Structural Lead Arturo Smith Class 1 Mechanical Lead Technical Support Personnel James A.
James A. FitzPatrick FitzPatrick Personnel in Attendance Personnel in Attendance
3
- James A. FitzPatrick Site Description
- Current Status
- James A. FitzPatrick Licensing History & Highlights
- License Renewal Project
- Cost-Beneficial SAMAs
- Presentation Topics
- Drywell and Torus Monitoring
- Torus Repair
- Questions Agenda Agenda
4 JAFNPP Site Description JAFNPP Site Description
- General Electric (NSSS & TG), Stone &
Webster (AE and Constructor)
- BWR-4, Mark I Containment
- 2536 MWt Thermal Power; ~ 881 MWe
- Once through cooling from Lake Ontario
- Staff Complement: approximately 650
5 JAFNPP Plant Status JAFNPP Plant Status
- Startup from RFO 17 - November 4, 2006
- Current Plant Status
- Next outage Sept 2008
6 Construction Permit May 20, 1970 Operating License October 17, 1974 Commercial Operation July 28, 1975 Uprated Power License (4%) December 6, 1996 License Transfer to Entergy November 21, 2000 LR Application Submitted July 31, 2006 Operating License Expires October 17, 2014 Licensing History Licensing History
7 Major Improvements Major Improvements 1978-1983 Mark I Containment Modifications 1988 Hydrogen Water Chemistry 1989 Zinc Injection 1990 Power Uprate Equipment Upgrades 1998 ECCS Suction Strainers Replaced 1999 Noble Metals Application 2004 LP Turbine Rotor Replacement 2004 Noble Metals Application 2 2006 HP Turbine Rotor Replacement 2006 Offgas Condenser Replacement 2006 HPCI Discharge Exhaust Sparger Added
8 Future Improvements Future Improvements 2008 Main Transformer Replacement 2008 Core Spray Motor Replacement 2008 345KV Breaker Replacement
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- LRA Prepared by experienced, multi-discipline Entergy team (utilized corporate and on-site resources)
- Incorporated lessons learned from previous applications
- Peer review conducted
- All comments resolved prior to submittal JAFNPP License Renewal Project JAFNPP License Renewal Project
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- License Renewal Commitments
- Refined during audit/inspection process
- Tracked by Entergy commitment tracking and engineering work tracking systems
- 36 Aging Management Programs
- 17 Programs in Place w/o Enhancements
- 9 Programs will be Enhanced
- 10 New Programs
- GALL Consistancy
- 10 Consistent
- 20 Consistent with exceptions / enhancements
- 6 Plant Specific JAFNPP License Renewal Project JAFNPP License Renewal Project
11 Program Implementation Plan
- Develop fleet approach for Entergy plants that have submitted an LRA
- Develop schedule using industry experience JAFNPP License Renewal Project JAFNPP License Renewal Project
12 Scoping of Non safety-Related Systems, Structures, and Components (10 CFR 54.4a(2))
- Utilized site component database, P&IDs, and isometric drawings
- Reviewed safety related cable / piping locations
- Performed walkdowns for a(2) scope verification JAFNPP License Renewal Project JAFNPP License Renewal Project
13 Scoping of Non safety-Related Systems, Structures, and Components (10 CFR 54.4a(2))
- Regional Inspection verified a(2) scoping for in-plant areas and systems
- 10 CFR 54.4a(2) scope changes made in LRA Amendment 11
- Regional Inspection concluded that JAF had implemented an acceptable method of scoping and screening of non-safety related SSCs and that this method resulted in accurate scoping determinations JAFNPP License Renewal Project JAFNPP License Renewal Project
14 Draft SER Summary
- Open Items - 2 Reactor Vessel Fluence Environmentally Assisted Fatigue
- Confirmatory Items - None JAFNPP License Renewal Project JAFNPP License Renewal Project
15 Reactor Vessel Neutron Fluence Current P-T curves valid through 2014 (32EFPY)
Submit RG 1.190 calculations by September 2007 Evaluated TLAAs to determine limiting fluence (RG 1.99)
Adjusted Reference Temperatures (<200F)
Upper Shelf Energy (>50 ft-lb)
RPV welds RPV nozzles near beltline
- ART and USE values will not be challenged at 54 EFPY JAFNPP License Renewal Project JAFNPP License Renewal Project
16 Environmentally Assisted Fatigue
- JAF will demonstrate that cumulative usage factors (CUF) of the most fatigue sensitive locations are less than 1.0 throughout the license renewal period by first using Option (1) of commitment #20
- Analysis methods for determination of stresses and fatigue usage will be in accordance with NRC endorsed ASME Boiler and Pressure Vessel Code
- JAF will utilize design transient specifications and information from BWR-4 references to bound operational transients JAFNPP License Renewal Project JAFNPP License Renewal Project
17 Environmentally Assisted Fatigue Environmental effects on fatigue usage will be assessed consistent with the Generic Aging Lessons Learned Report, NUREG-1801, Rev. 1.
If Option (2) becomes necessary, plant inspection program will be described in terms of the ten elements specified in Branch Technical Position RLSB-1.
If Option (3) becomes necessary, repair or replacement will be in accordance with plant procedures that meet ASME Section XI requirements.
Above actions will be incorporated into the Fatigue Monitoring Program.
The Fatigue Montoring Program will manage the effects of EAF in accordance with 10 CFR 54.21(c)(1)(iii).
JAFNPP License Renewal Project JAFNPP License Renewal Project
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- Six Potentially Cost-Beneficial SAMAs Identified
- No Age-Related SAMAs
- Implementation will be evaluated using the plant cost-benefit analysis process Cost Cost--Beneficial Beneficial SAMAs SAMAs
19 Presentation Topics Presentation Topics
- Drywell and Torus Monitoring
- Torus Repair
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21 Drywell and Torus Monitoring James A.
James A. FitzPatrick FitzPatrick
22 James A.
James A. FitzPatrick FitzPatrick
23 James A.
James A. FitzPatrick FitzPatrick
24 James A.
James A. FitzPatrick FitzPatrick
25 Drywell Monitoring Drywell Monitoring Sand Cushion Inspections. No Evidence of Moisture (Boroscopic Inspection).
Visual Inspection of Interior Drywell Caulk Seal.
Drywell Interior Coating System (Carbozinc 11 and Dupont Corlar Epoxy) Inspection IAW IWE Program during RFO.
26 Torus Monitoring Torus Monitoring Torus Interior Shell Inspection 1998 (Installation of ECCS Suction Strainers).
Torus Interior Coating System (Carbozinc 11) inspected.
Torus Interior/Exterior Inspected IAW JAF IWE Program.
27 Drywell Shell Construction Photo Drywell Shell Construction Photo
28 Drywell Shell Construction Photo Drywell Shell Construction Photo
29 Drywell Shell Construction Photo Drywell Shell Construction Photo
30 Drywell Shell Construction Photo Drywell Shell Construction Photo
31 James A.
James A. FitzPatrick FitzPatrick Torus Repair
32 Torus Repair Torus Repair Torus shell through-wall leak reported in June 2005 Leak was located in same bay as HPCI Steam Discharge pipe near ring girder gusset plate weld ASME Section XI code repair performed in July 2005 by removing the flaw and adding a circular repair plate Root cause of flaw was vibration fatigue from HPCI steam condensation oscillation loading
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34 Torus Leak 2005 Torus Indication 2006 HPCI Open End Discharge Ring Girder Gusset Plate
35 Torus Repair Torus Repair A HPCI Steam Exhaust Sparger assembly was added during refueling outage October 2006 The sparger directs steam flow away from the Torus shell The sparger significantly reduces loads on the Torus shell from HPCI Steam condensation oscillation
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37 Torus Repair Torus Repair Extent of condition actions from Root Cause required additional shell exams during refueling outage October 2006 ASME visual exams of similar ring girder gusset welds performed at HPCI and RCIC steam discharge locations General visual exams of similar ring girder gusset welds performed at several locations throughout the Torus Exam results reported shell base metal flaws at two additional locations in the HPCI discharge bay
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39 Torus Repair Torus Repair ASME Section XI code repairs were performed by grinding to remove the flaws and welding to restore configuration Review was performed to confirm the HPCI steam discharge loading also caused these flaws
40 Comments and Questions Comments and Questions