ML11083A025
| ML11083A025 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/03/2009 |
| From: | Kimberly Green Division of License Renewal |
| To: | Stroud M Entergy Nuclear Operations |
| References | |
| Download: ML11083A025 (49) | |
Text
1 Stuyvenberg, Andrew From:
Kimberly Green Sent:
Tuesday, March 03, 2009 1:36 PM To:
STROUD, MICHAEL D
Subject:
latest slides Attachments:
ACRS-Indian Point-Presentation 03-03-09.ppt Here are the latest. I don't expect too many changes at this point.
Kim
Advisory Committee on Reactor Safeguards License Renewal Subcommittee Indian Point Nuclear Generating Unit Indian Point Nuclear Generating Unit Nos. 2 and 3 Safety Evaluation Report with Open Items March 4, 2009 Kimberly Green, Project Manager Office of Nuclear Reactor Regulation
Introduction
- Overview
- Section 2: Scoping and Screening Review
- License Renewal Inspections p
- Section 3: Aging Management Program and Review Results Review Results
- Section 4: Time-Limited Aging Analyses (TLAAs) 2
- Open Items
Overview
- LRA Submitted by letter dated April 23, 2007
- Westinghouse 4 Loop
- Westinghouse 4-Loop
- 3216 MWth, 1080 MWe
- Operating license DPR-64 (IP3) expires December 12 2015 December 12, 2015
- Located approximately 25 miles north of NYC limits 3
Overview
- Safety Evaluation Report with Open Items was i
d J 15 2009 issued January 15, 2009
- 20 Open items
- 121 RAIs Issued
- 272 Audit Questions
- 38 Commitments 4
Overview Scoping and Screening Methodology Audit
- October 8, 2007 - October 12, 2007 Aging Management Programs (AMP) Audit Aging Management Programs (AMP) Audit
- August 27, 2007 - August 31, 2007 Aging Management Review (AMR) & Time-Limited Aging Analysis (TLAA) Audit O t b 22 2007 O t b 26 2007
- October 22, 2007 - October 26, 2007
- November 27, 2007 - November 29, 2007
- February 19, 2008 - February 21, 2008 Regional License Renewal Inspections eg o a ce se e e a spect o s
- January 28, 2008 - February 1, 2008
- February 11, 2008 - February 14, 2008
- March 31, 2008 - April 2, 2008 J
2 2008 J
6 2008 d J 18 2008 5
- June 2, 2008 - June 6, 2008, and June 18, 2008
Open Items
- SER issued with 20 open items
- 14 with requests for additional information
- 6 are still under review by staff
- Applicant submitted additional information dated January 27, 2009
- Staff can close out 13 Open Items 6
Section 2: Structures and Components Subject to Aging Management Review Section 2.1 - Scoping and Screening Methodology Subject to Aging Management Review
- Based on audit and review staff concluded that the applicants methodology is consistent with the requirements of 10 CFR 54.4 and 54.21(a)(1) requirements of 10 CFR 54.4 and 54.21(a)(1)
Section 2.2 - Plant-Level Scoping Results
- IP2 chlorination and IP3 H2 systems initially omitted from scope
- Staff concluded applicant identified mechanical systems and structures within the scope of license renewal per 7
Section 2.3 - Scoping and Screening Results:
Mechanical Systems Mechanical Systems
- Mechanical Systems: 59 (IP2 ) and 87 (IP3)
- Two Tier Review of Balance of Plant systems:
Two Tier Review of Balance of Plant systems:
- Tier 1 Review: Review LRA and UFSAR
- Tier 2 Review: Detailed review of LRA, UFSAR, and li l d i
license renewal drawings
- 100% of mechanical systems identified by applicant as within the scope of license renewal applicant as within the scope of license renewal were reviewed 8
Section 2.3 - Scoping and Screening Results:
Mechanical Systems Mechanical Systems
- Staff identified omission of nonsafety-related components from scope for IP2 containment components from scope for IP2 containment spray
- Applicant re-evaluated and identified 3 other Applicant re evaluated and identified 3 other systems (IP2 CCW, IP3 CCW, and IP3 BVS)
Section 2.3 - Scoping and Screening Results Mechanical Systems Mechanical Systems
- Three Open Items OI 2 3A 3 11 1 yard hose houses and chamber
- OI 2.3A.3.11 yard hose houses and chamber housings
- OI 2.3.4.2 feedwater isolation valves
- OI 2.3A.4.5 auxiliary feedwater pump room fire event systems
- These OIs can be closed 10
Section 2.4 - Scoping and Screening Results:
St t
Structures
- Staff concluded that there were no omissions of t
t t
t l
t f structures or structural components from scope of license renewal in accordance with 10 CFR 54 4(a) and no omissions from AMR in 54.4(a), and no omissions from AMR in accordance with 10 CFR 54.21(a)(1).
11
Section 2.5 - Scoping and Screening Results:
Electrical and Instrumentation and Control Electrical and Instrumentation and Control Systems
- OI 2.5 Station blackout scoping
- Issue is under staff evaluation
- With exception of SBO OI scoping, staff concluded no omissions of electrical and concluded no omissions of electrical and instrumentation and control system components from the scope of license renewal in accordance with 10 CFR 54 4(a) and no omissions from with 10 CFR 54.4(a), and no omissions from AMR in accordance with 10 CFR 54.21(a)(1) 12
Section 2.6 - Conclusion for Scoping and Screening Screening
- The applicants scoping and screening methodology is consistent with the requirements methodology is consistent with the requirements of 10 CFR 54.4 and 10 CFR 54.21(a)(1)
- With exception of open items, the applicant adequately identified those SSCs within the scope of license renewal in accordance with 10 CFR 54 4(a) and those SCs subject to an AMR CFR 54.4(a), and those SCs subject to an AMR in accordance with 10 CFR 54.21(a)(1).
13
License Renewal Inspections License Renewal Inspections Glenn Meyer Glenn Meyer Region I Inspection Team Leader Region I Inspection Team Leader
Inspection Objectives p
j
- Scoping of Non-safety SSCs
- 28 Aging Management Programs (AMPs)
- 2 Systems: Auxiliary Feedwater; IP2 SBO diesel generator (DG)
Scoping Scoping
- Scoping of non-safety SSCs - generally
- Scoping of non-safety SSCs - generally accurate and acceptable
- Structural and spatial interactions
- Structural and spatial interactions reviewed AMP i
f d 2 t
i
- AMP reviews found 2 component scoping errors 16
Aging Management Program Review g
g g
g Resolved by LRA Amendment 3:
- Structural Monitoring
- Oil Analysis Oil Analysis
- Diesel Fuel Monitoring W t Ch i t
- Water Chemistry
- Metal-Enclosed Bus Inspection 17
Aging Management Program Review g
g g
g Resolved by LRA Amendment 3:
Resolved by LRA Amendment 3:
- Selective Leaching N
EQ B l d C bl C
i
- Non-EQ Bolted Cable Connections Resolved by LRA Commitment 37:
- Exposed rebar on containment exterior 18 Exposed rebar on containment exterior
Aging Management Program Review g
g g
g Resolved Onsite:
- Metal-Enclosed Bus Operating Experience
- Instrument air heat exchangers g
- AMR for transite material
- Condition Reports on isolated degradation
- Condition Reports on isolated degradation 19
Follow Up Inspections p
p
- IP2 SBO diesel - scoping and system
- IP2 SBO diesel - scoping and system review when operational
- Electrical cable vault when accessible
- Electrical cable vault - when accessible
- Unit 2 containment liner - when accessible 20
Inspection Conclusions p
- Non-safety SSC scoping and aging
- Non-safety SSC scoping and aging management programs are acceptable.
- Inspection results support a conclusion of bl th t i
ff t
reasonable assurance that aging effects will be managed and intended functions ill b i t i d
21 will be maintained
Current Performance
- Both units - Licensee Response Column
- All Findings - Green All Findings Green
- All Performance Indicators (PIs) - Green 22
Section 3: Aging Management Review R
lt Results
- Section 3.0 - Aging Management Programs
- Section 3.1 - Reactor Vessel & Internals
- Section 3.2 - Engineered Safety Features
- Section 3.3 - Auxiliary Systems
- Section 3.4 - Steam and Power Conversion System
- Section 3.5 - Containments, Structures and Component Supports
- Section 3 6 Electrical and Instrumentation and Controls 23
- Section 3.6 - Electrical and Instrumentation and Controls System
Section 3.0.3 - Aging Management Programs (AMP )
(AMPs)
- 41 AMPs 10 New Programs
- 10 New Programs
- 31 Existing Programs
- 15 consistent with GALL Report
- 15 consistent with GALL Report
- 10 consistent with GALL Report with enhancements
- 8 had exceptions
- 8 had exceptions
- 8 plant-specific 24
Section 3.0.3 - AMPs 8 O It
- 8 Open Items
- The following 5 OIs can be closed
- OI 3.0.3.2.7 fire penetration seals
- OI 3.0.3.3.3 acceptance criteria for visual examinations
- OI 3.0.3.3.4 inspection methods, etc. for lubrite sliding supports
- OI 3.0.3.3.4 corrective actions for ISI
- OI 3.0.3.3.7 Periodic Surveillance and Preventive Maintenance Program 25
Section 3.0.3 - AMPs
- The following 3 OIs are still under review
- OI 3.0.3.2.15 IP2 reactor refueling cavity leakage
- OI 3.0.3.2.15 IP2 spent fuel pool leak
- OI 3.0.3.3.2 Exterior containment concrete degradation degradation 26
Section 3.1 - Aging Management of Reactor Vessel, Internals, and RCS
- 2 Open Items p
- OI 3.1.2 Nickel alloy components
- OI 3 1 2 2 7 Inspection of CASS OI 3.1.2.2.7 1 Inspection of CASS These 2 OIs can be closed 27
Section 3.3 - Aging Management of Auxiliary Systems
- OI 3 3 Clarification of OI 3.3 1 Clarification of material/environment/aging effect for titanium components titanium components This OI can be closed 28
Section 3.4 - Aging Management of St d P C
i Steam and Power Conversion Systems
- One Open Item
- OI 3.4 AMR results for a fire in IP2 ili f
d t
auxiliary feedwater pump room This OI is still under staff review 29
Section 3.5 - Aging Management of C
t i t
St t
d Containments, Structures and Component Supports
- 3 Open Items
ti f
IP t
- OI 3.5 Water-cement ratio for IP concrete
- OI 3.5 Reduction of strength and modulus of concrete due to elevated temperatures 30
Section 3.5 - Aging Management of g g g
Containments, Structures and Component Supports Component Supports
- This OI can be closed
- OI 3.5 Aging management of concrete surrounding B1 supports 31
Section 3.6 - Aging Management of Electrical and I&C Systems
- LRA identified no aging effects for IP2 138-kV hi h lt bl high-voltage cable
- Staff issued RAI A
li t
d d LRA t dd bl t
- Applicant amended LRA to add cable to Periodic Surveillance and Preventive Maintenance Program g
32
Section 3 7 Conclusion Section 3.7 Conclusion With the exception of the Open Items, the li t h d
t t d th t i
applicant has demonstrated that aging effects will be adequately managed during the period of extended operation in the period of extended operation in accordance with 10 CFR 54.21(a)(3) 33
Section 4: Time-Limited Aging Analyses
- 4.1 Identification of Time Limited Aging Analyses (TLAAs) g g
y (TLAAs)
- 4.2 Reactor Vessel Neutron Embrittlement
- 4.3 Metal Fatigue 4.3 Metal Fatigue
- 4.4 Environmental Qualification of Electrical Equipment
- 4.5 Concrete Containment Tendon Prestress
- 4.6 Containment Liner Plate and Penetration Fatigue
- 4.7 Other Plant-Specific TLAAs 34
Section 4.2: Reactor Vessel Neutron Embrittlement - Upper Shelf Energy Embrittlement Upper Shelf Energy Limiting Beltline MaterialLower Shell Plate (B2002-3)
Unit 2
% CU 48 EFPY Fluence (E>1 MeV) at Initial Charpy V notch USE Value Irradiated Charpy V Acceptance Criterion per Unit 2
(
)
1/4T 1019 (n/cm2)
(ft-lb) notch USE Value at 48 EFPY (ft-lb) 10 CFR 50, App. G (ft-lb) 0.25 1.136 74 48.3
>50 35
- Equivalent margins analysis submitted which meets Appendix G of ASME Section XI and 10 CFR Part 50, Appendix G
Section 4.2: Reactor Vessel Neutron Embrittlement - Upper Shelf Energy Embrittlement Upper Shelf Energy Limiting Beltline MaterialLower Shell Plate (B2803-3)
Unit 3
% CU 48 EFPY Fluence (E>1 MeV) at Initial Charpy V notch USE Value Irradiated Charpy V Acceptance Criterion per Unit 3
(
)
1/4T 1019 (n/cm2)
(ft-lb) notch USE Value at 48 EFPY (ft-lb) 10 CFR 50, App. G (ft-lb) 0.24 0.9298 68 49.8
>50 36
- Equivalent margins analysis submitted which meets Appendix G of ASME Section XI and 10 CFR Part 50, Appendix G
Section 4.2: Reference Temperature for Pressurized Thermal Shock (PTS) Values Pressurized Thermal Shock (PTS) Values Limiting Beltline MaterialLower Shell Plate (B2803-3)
Unit 3
%CU
%Ni 48 EFPY Fluence (E>1 MeV)
(@clad/steel interface)
Initial Charpy RTNDT 0F RTPTS 0F Acceptance Criterion per 10 CFR 50.61
(@clad/steel interface) 1019 (n/cm2)
F 0F 0.24 0.52 1.56 74 279.5
<270oF 0.52 Commitment 32: As required by 10 CFR 50.61(b)(4), IP3 will submit a plant-specific safety analysis for plate B2803-3 to the NRC three years prior to reaching the RTPTS 37 safety analysis for plate B2803 3 to the NRC three years prior to reaching the RTPTS screening criterion. Alternatively, the site may choose to implement the revised PTS rule when approved.
Section 4.3: Metal Fatigue Analyses
- 60-year fatigue analyses were performed g
y for all NUREG/CR-6260 locations, except 2 locations (IP2) and 3 locations (IP3)
- Entergy will manage aging for NUREG/CR-6260 locations in accordance with 10 CFR 54.21(c)(1)(iii) (Commitment 33) 38
)
Section 4.3: Metal Fatigue Analyses Section 4.3 - Class 1 Fatigue g
y g
- One Open Item
- OI 4 3 Number of IP3 plant heatups and
- OI 4.3 Number of IP3 plant heatups and cooldowns This OI can be closed This OI can be closed 39
Open Items Still Under Staff Review
- OI 3.0.3.2.15 IP2 reactor refueling cavity leakage
- OI 3.0.3.2.15 IP2 spent fuel pool leak
- OI 3.0.3.3.2 Exterior containment concrete d
d ti degradation
- OI 3.4 AMR results for the auxiliary feedwater pump room event
- OI 3.5 Water-cement ratio for IP concrete
- OI 3.5 Reduction of strength and modulus of 40 concrete due to elevated temperatures
- Applicant revised LRA Figures 2.5-2 and 2.5-3, the Offsite Power Scoping Diagram(s) for IP2 and IP3 for primar and secondar offsite po er paths for primary and secondary offsite power paths
- By letters dated March 24, 2008 and August 14, 2008, the applicant revised and clarified its response pp p
- The staff is completing its review of the applicants information on the SBO scoping boundary and will d
t it l
i i
th fi l SER document its conclusion in the final SER 41
- OI 3.0.3.2.15 IP2 reactor refueling cavity leakage IP2 ref eling ca it leaks at the pper ele ations of the stainless
- IP2 refueling cavity leaks at the upper elevations of the stainless steel cavity liner when flooded during refueling outages
- Attempts have been made to mitigate this condition
- An action plan is being developed for permanent fix
- Applicant has committed to perform one-time inspection prior to entering period of extended operation to confirm absence of degradation (Commitment 36)
- Applicant has not identified augmented inspections for period of extended operation
- Staff sent draft RAI to request how the AMP will monitor condition during period of extended operation 42
- OI 3.0.3.2.15 IP2 spent fuel pool leak
- IP2 spent fuel pool (SFP) has experienced leakage
- IP2 SFP does not have leak chase channels Applicant committed to test the groundwater outside
- Applicant committed to test the groundwater outside IP2 SFP every 3 months (Commitment 25)
- Applicant does not plan to perform augmented pp p
p g
inspections of SFP during the period of extended operation.
St ff t d ft RAI t t h th AMP ill
- Staff sent draft RAI to request how the AMP will monitor this condition during period of extended operation 43
- OI 3.0.3.3.2 Exterior containment concrete degradation degradation
- External surfaces of IP2 and IP3 containments have locations of concrete spalling
- Applicant explained that areas of spalling occur at cadweld sleeves and scaffolding anchor locations
- Applicant concluded there is sufficient design margin for exposed rebar
- Applicant committed to perform enhanced inspections of containment (Commitment 37)
- Staff sent draft RAI requesting information on how the applicant will use the above within its Containment Inservice Inspection Program 44
- OI 3.4 AMR results for the IP2 auxiliary feedwater fi t
pump room fire event
- Applicant stated that systems are continuously in operation and monitored
- Applicant stated aging related degradation that occurs during 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is negligible
- Applicant concluded that there are no aging effects; therefore no pp g g AMPs are necessary
- Applicant provided additional information on January 27, 2009
- Staff is still evaluating applicants response Staff is still evaluating applicant s response 45
- OI 3.5 Water-cement ratio for IP concrete
- LRA identified the water-cement ratios for IP concrete
- Staff identified a discrepancy and asked for clarification
- Applicant stated it used Method 2 in ACI 318-63 standard to Applicant stated it used Method 2 in ACI 318 63 standard to determine concrete strength
- Staff sent draft RAI to define water-cement ratios and provide results of original concrete strength tests Alternatively the results of original concrete strength tests. Alternatively, the applicant may identify applicable aging effects and how they will be managed 46
- OI 3.5 Reduction of strength and modulus of concrete due to elevated temperatures p
- LRA stated concrete surrounding IP2 penetrations can reach 250 °F
- GALL Report recommends further evaluation to manage reduction of strength and modulus of concrete structures due to elevated temperature (>200 °F)
- Applicant concluded that reduction of strength and modulus is not an aging effect requiring management
- Applicant determined a reduction in strength of 15% from elevated temperatures which is acceptable
- Staff sent draft RAI about how strength margin was determined and if reduction in modulus of elasticity was considered Alternatively the reduction in modulus of elasticity was considered. Alternatively, the applicant may explain how the aging effect will be managed 47
Questions?
Questions?
48