ML11077A033

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Lr Hearing - Draft Slides
ML11077A033
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 02/24/2009
From: Kimberly Green
License Renewal Projects Branch 2
To: Stroud M
- No Known Affiliation
References
Download: ML11077A033 (48)
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Text

Stuyvenberg, Andrew From: Green, Kimberly Sent: Tuesday, February 24, 2009 8:09 AM To: STROUD, MICHAEL D

Subject:

Draft Slides Attachments: ACRS-Indian Point-Presentation 02-24-09.ppt

Mike, Here are the draft slides. As you can see, I'm still working on the last few (open items).

I've been requested to develop back up slides for items that have been raised in the most recent meetings.

They will not be a part of the slide package that is available at the meeting since I may not have to use them.

I'm having another dry run tomorrow. I will send the final slides by the end of the week. Should anything change between then and the meeting on the 4th, I will let you know.

Kim 1

Advisory Committee on Reactor Safeguards License Renewal Subcommittee 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
  • Section 4: Time-Limited Aging Analyses (TLAAs)
  • Open Items

Overview

  • LRA Submitted by letter dated April 23, 2007
  • Westinghouse 4 4-Loop Loop
  • 3216 MWth, 1080 MWe
  • Operating license DPR-26 DPR 26 (IP2) expires September 28, 2013
  • Operating license DPR-64 (IP3) expires December 1212, 2015
  • Located approximately 25 miles north of NYC limits

Overview

  • Safety Evaluation Report with Open Items was i

issued d JJanuary 15 15, 2009

  • 20 Open items
  • 272 Audit Questions
  • 38 Commitments

Overview

  • Scoping and Screening Methodology Audit

- October 8, 2007 - October 12, 2007

- August 27, 2007 - August 31, 2007

- OOctober t b 22, 22 2007 - October O t b 26,26 2007

- November 27, 2007 - November 29, 2007

- February 19, 2008 - February 21, 2008

  • Regional eg o a License ce se Renewal e e a Inspections spect o s

- January 28, 2008 - February 1, 2008

- February 11, 2008 - February 14, 2008

- March 31, 2008 - April 2, 2008

- J June 2 2008 - June 2, J 6 6, 2008 2008, and d JJune 18 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 has closed out 13 Open Items

Section 2: Structures and Components Subject to Aging Management Review Section 2.1 - Scoping and Screening Methodology

  • 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)

Section 2.2 - Plant-Level Scoping Results

  • IP2 chlorination and IP3 H2 systems initially omitted from scope

Section 2: Structures and Components Subject to Aging Management Review Section 2.3 - Scoping and Screening Results:

Mechanical Systems

  • Mechanical Systems: 59 (IP2 ) and 87 (IP3)
  • Two Tier Review of Balance of Plant systems:

- Tier 1 Review: Review LRA and UFSAR

- Tier 2 Review: Detailed review of LRA, UFSAR, and license renewal drawings

  • 100% of mechanical systems identified by applicant as within the scope of license renewal were reviewed

Section 2: Structures and Components Subject to Aging Management Review Section 2.3 - Scoping and Screening Results:

M h i lS Mechanical Systems t

  • Staff identified omission of nonsafety-related components from scope for IP2 containment spray
  • Applicant re-evaluated re evaluated and identified 3 other systems (IP2 CCW, IP3 CCW, and IP3 BVS)
  • Amended LRA and added components to scope

Section 2: Structures and Components Subject to Aging Management Review Section 2.3 - Scoping and Screening Results M h i lS Mechanical Systems t

  • Three Open Items

- OI 2.3A.3.11 yard hose houses and chamber housings

- OI 2.3.4.2 2 3 4 2-1 1 - feedwater isolation valves

- OI 2.3A.4.5 auxiliary feedwater pump room fire event systems

  • These OIs have been closed

Section 2: Structures and Components Subject to Aging Management Review Section 2.4 - Scoping and Screening Results:

St Structures t

  • Staff concluded that there were no omissions of structures t t or structural t t l components t from f scope of license renewal in accordance with 10 CFR 54 4(a) and no omissions from AMR in 54.4(a),

accordance with 10 CFR 54.21(a)(1).

Section 2: Structures and Components Subject to Aging Management Review Section 2.5 - Scoping and Screening Results:

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 omission of electrical and instrumentation and control system components from the scope of license renewal in accordance with 10 CFR 54.4(a),

54 4(a) and no omissions from AMR in accordance with 10 CFR 54.21(a)(1)

Section 2: Structures and Components Subject to Aging Management Review Section 2.6 - Conclusion for Scoping and Screening

54 4(a) and those SCs subject to an AMR in accordance with 10 CFR 54.21(a)(1).

License Renewal Inspections Glenn Meyer Region I Inspection Team Leader

Inspection p Objectives j

  • Scoping of Non-safety SSCs
  • Review of 2 Systems
  • Followup: IP2 SBO diesel, cable vault, and containment liner

Scoping

  • Scoping of non-safety SSCs - generally accurate and acceptable
  • Structural and spatial interactions reviewed
  • AMP reviews i ffound d 2 componentt scoping i

errors

Existing g AMPs LRA Amendment

  • Structural Monitoring
  • Oil Analysis
  • Diesel Fuel Monitoring
  • Water W t Chemistry Ch i t
  • Metal-Enclosed Bus Inspection

Existing g AMPs Other Issues

  • Exposed rebar on containment
  • Operating p g Experience p for Metal-Enclosed Bus
  • Instrument air heat exchangers
  • AMR for transite material
  • CRs CR on iisolated l t dddegradation d ti

New AMPs

  • Selective Leaching
  • Non-EQ Bolted Cable Connections

Follow Up p Inspections p

  • IP2 SBO diesel - scoping and system review
  • Electrical cable vault
  • Unit 2 containment liner

Inspection p Conclusions

  • Inspection results support a conclusion of reasonablebl assurance that th t aging i effects ff t will be managed and intended functions will ill b be maintained i t i d

Section 3: Aging Management Review R

Resultslt

  • 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 3.6 6 - Electrical and Instrumentation and Controls System

Section 3: Aging Management Review R

Results lt Section 3.0.3 - Aging Management Programs (AMP )

(AMPs)

- 10 N New P Programs

- 31 Existing Programs

  • 15 consistent with GALL Report
  • 18 consistent with GALL Report with enhancements and/or exceptions
  • 8 plant-specific

Section 3: Aging Management Review R

Results lt Section 3.0.3 - AMPs

  • 8 Open Items
  • The following 5 OIs have been closed

- OI 3.0.3.2.7 3 0 3 2 7-1 1 - 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 g

Section 3: Aging Management Review R

Resultslt Section 3.0.3 - AMPs

  • The following 3 OIs are still under review

- OI 3.0.3.2.15 3.0.3.2.15-1 1 - IP2 reactor refueling cavity leakage

- OI 3.0.3.2.15 IP2 spent p fuel p pool leak

- OI 3.0.3.3.2 Exterior containment concrete degradation g

Section 3: Aging Management Review R

Resultslt Section 3.1 - Aging Management of Reactor Vessel, Internals, and RCS

  • OI 3.1.2 3 1 2-1 1 - Nickel alloy components
  • OI 3.1.2.2.7 Inspection of CASS Th These 2 OI OIs have h been b closed l d

Section 3: Aging Management Review R

Results lt Section 3.3 - Aging Management of Auxiliary Systems

  • OI 3.3 3 3-1 1 - Clarification of material/environment/aging effect for titanium components This OI has been closed

Section 3: Aging Management Review R

Results lt Section 3.4 - Aging Management of Steam and Power Conversion Systems

Section 3: Aging Management Review R

Resultslt Section 3.5 - Aging Management of Containments, Structures and Component Supports

  • These 2 OIs are still under staff review

- OI 3.5-1 3 5 1 - Water-cement Water cement ratio for IP concrete

- OI 3.5 Reduction of strength and modulus of concrete due to elevated temperatures

Section 3: Aging Management Review R

Results lt Section 3.5 - Aging Management of Containments, Structures and Component Supports

Section 3: Aging Management Review R

Results lt Section 3.6 - Aging Management of El Electrical i l and d I&C S Systems

  • LRA identified no aging effects for IP2 138-kV hi h lt high-voltage cable bl
  • Staff issued RAI
  • Applicant amended LRA to add cable to Periodic Surveillance and Preventive Maintenance Program g

Section 3: Aging Management Review Results C

Conclusion l i With the exception of the Open Items, the applicant has demonstrated that aging q y managed effects will be adequately g during g the period of extended operation in accordance with 10 CFR 54.21(a)(3)

Section 4: Time-Limited Aging g g Analyses y

  • 4.1 Identification of Time Limited Aging Analyses (TLAAs)
  • 4.2 Reactor Vessel Neutron Embrittlement
  • 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

Section 4.2: Reactor Vessel Neutron Embrittlement - Upper Shelf Energy Limiting Beltline MaterialLower Shell Plate (B2002-3)

Unit 2

% CU 48 EFPY Fluence Initial Charpy V Irradiated Acceptance

((E>1 MeV)) at notch USE Value Charpy V Criterion per 1/4T (ft-lb) notch USE 10 CFR 50, 1019 (n/cm2) Value at App. G 48 EFPY (ft-lb) (ft-lb) 0.25 1.136 74 48.3 >50

Section 4.2: Reactor Vessel Neutron Embrittlement - Upper Shelf Energy Limiting Beltline MaterialLower Shell Plate (B2803-3)

Unit 3

% CU 48 EFPY Fluence Initial Charpy V Irradiated Acceptance

((E>1 MeV)) at notch USE Value Charpy V Criterion per 1/4T (ft-lb) notch USE 10 CFR 50, 1019 (n/cm2) Value at App. G 48 EFPY (ft-lb) (ft-lb) 0.24 0.9298 68 49.8 >50

Section 4.2: Reference Temperature for Pressurized Thermal Shock (PTS) Values Limiting Beltline MaterialLower Shell Plate (B2803-3)

Unit 3

%CU 48 EFPY Fluence Initial Charpy RTPTS Acceptance

%Ni (E>1 MeV) RTNDT 0F Criterion per

(@clad/steel interface) 0F 10 CFR 50.61 1019 (n/cm2) 0F 0.24 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 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 g Analysesy

  • 60-year fatigue analyses were performed for all NUREG/CR-6260 locations, except 2 locations (IP2) and 3 locations (IP3)

37

Section 4: Time-Limited Aging g g Analyses y

Section 4.3 - Class 1 Fatigueg

  • OI 4.3 Number of IP3 plant heatups and cooldowns This OI has been closed

Open Items

  • 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

degradation d ti

  • OI 3.5 Water-cement ratio for IP concrete
  • OI 3.5 Reduction of strength and modulus of concrete due to elevated temperatures

Open p Items

- By letter dated November 16, 16 2007, 2007 the applicant revised LRA Figures 2.5-2 and 2.5-3, the Offsite Power Scoping Diagram(s) for IP2 and IP3, to address staff concerns regarding the IP2 and IP3 primary and secondary offsite power paths.

- By letter dated March 24, 2008, the applicant revised its response to RAI 2.5-1.

- By letter dated August 14, 2008, the applicant clarified its response to RAI 2.5-1.

251

- The staff is completing its review of the applicants information on the SBO scoping boundary and will document its conclusion in the final SER.

Open p Items

  • OI 3.0.3.2.15 IP2 reactor refueling cavity leakage

- The reactor cavity at IP2 has a history of leakage at the upper elevations of the stainless steel cavity liner when flooded during refueling outages.

- Attempts have been made over the last several outages to mitigate this condition, with limited success.

- An action plan is being developed for a permanent fix to this issue.

- Entergy has committed to perform a one-time inspection prior to entering the period off extended operation to confirm f the absence off degradation (Commitment 36).

- Entergy made no commitment for augmented inspection during the extended period of operation operation.

Open p Items

  • OI 3.0.3.2.15 IP2 spent fuel pool leak

Open p Items

  • OI 3.0.3.3.2 Exterior containment concrete degradation

Open p Items

Open p Items

  • OI 3.5 Water-cement ratio for IP concrete

Open p Items

  • OI 3.5 Reduction of strength and modulus of concrete due to elevated temperatures

Questions?

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